Development of Demonstration Facility Design Technology for Advanced Nuclear Fuel Cycle Process

International Nuclear Information System (INIS)

Cho, Il Je; You, G. S.; Choung, W. M.

2010-04-01

The main objective of this R and D is to develop the PRIDE (PyRoprocess Integrated inactive DEmonstration) facility for engineering-scale inactive test using fresh uranium, and to establish the design requirements of the ESPF (Engineering Scale Pyroprocess Facility) for active demonstration of the pyroprocess. Pyroprocess technology, which is applicable to GEN-IV systems as one of the fuel cycle options, is a solution of the spent fuel accumulation problems. PRIDE Facility, pyroprocess mock-up facility, is the first facility that is operated in inert atmosphere in the country. By using the facility, the functional requirements and validity of pyroprocess technology and facility related to the advanced fuel cycle can be verified with a low cost. Then, PRIDE will contribute to evaluate the technology viability, proliferation resistance and possibility of commercialization of the pyroprocess technology. The PRIDE evaluation data, such as performance evaluation data of equipment and operation experiences, will be directly utilized for the design of ESPF

Status and Prospect of Safeguards By Design for the Pyroprocessing Facility

International Nuclear Information System (INIS)

Kim, Hodong; Shin, H.S.; Ahn, S.K.

2010-01-01

The concept of Safeguards-By-Design (SBD), which is proposed and developed by the United States and the IAEA, is now widely acknowledged as a fundamental consideration for the effective and efficient implementation of safeguards. The application of a SBD concept is of importance especially for developmental nuclear facilities which have new technological features and relevant challenges to their safeguards approach. At this point of time, the examination of the applicability of SBD on a pyroprocessing facility, which has been being developed in the Republic of Korea (ROK), would be meaningful. The ROK developed a safeguards system with the concept of SBD for Advanced spent fuel Conditioning Process Facility (ACPF) and DUPIC Fuel Development Facility (DFDF) before the SBD concept was formally suggested. Currently. The PRIDE (PyRoprocess Integrated Inactive Demonstration) facility for the demonstration of pyroprocess using 10 ton of non-radioactive nuclear materials per year is being constructed in the ROK. The safeguards system for the facility has been designed in cooperation with a facility designer from the design phase, and the safeguards system would be established according to the future construction schedule. In preparing the design of Engineering Scale Pyroprocess Facility (ESPF), which will use spent fuels in an engineering scale and be constructed in 2016, a research on the safeguards system for this facility is also being conducted. In this connection, a project to support for development of safeguards approach for a reference pyroprocessing facility has been carried out by KAERI in cooperation with KINAC and the IAEA through an IAEA Member State Support Program (MSSP). When this MSSP project is finished in August, 2011, a safeguards system model and safeguards approach for a reference pyroprocessing facility would be established. Maximizing these early experiences and results, a safeguards system of ESPF based on the concept of SBD would be designed and

General Guidelines for Remote Operation and Maintenance of Pyroprocess Equipment

Energy Technology Data Exchange (ETDEWEB)

Kim, S. H.; Park, B. S.; Park, H. S.; Lee, H. J.; Choi, C. W.; Lee, J. K

2007-12-15

As the pyroprocess handle the high radioactive materials, a high radioactive material handling facility required high safety, radioactive shielding, strict quality control, and the remote handling equipment of high technology. This report describes the guidelines of for pyroprocess based the design guides for radioactive material handling facility and equipment from American Nuclear Society(ANS), design guidelines for remotely maintained equipment from Oak Ridge National Laboratory(ORNL), and the experience of design for ACP equipment installed at the ACPF(Advanced Conditioning Process Facility). The General guidelines in this report are as follows. The General guidelines for remote operation and maintenance of pyroprocess equipment: Pyroprocess, Remote handling equipment for pyroprocess, General guide for remote operation and maintenance, general guidelines for the design of remotely operated and maintained equipment, Estimation and analysis for remote maintenance.

Development of nuclear fuel cycle remote handling technology

International Nuclear Information System (INIS)

Kim, K. H.; Park, B. S.; Kim, S. H.

2012-04-01

This report presents the development of remote handling systems and remote equipment for use in the pyprocessing verification at the PRIDE (PyRoprocess Integrated inactive Demonstration facility). There are four areas conducted in this work. In first area, the prototypes of an engineering-scale high-throughput decladding voloxidizer which is capable of separating spent fuel rod-cuts into hulls and powder and collecting them separately, and an automatic equipment which is capable of collecting residual powder remaining on separated hulls were developed. In second area, a servo-manipulator system was developed to operate and maintain pyroprocess equipment located at the argon cell of the PRIDE in a remote manner. A servo-manipulator with dual arm that is mounted on the lower part of a bridge transporter will be installed on the ceiling of the in-cell and can travel the length of the ceiling. In third area, a digital mock-up and a remote handling evaluation mock-up were constructed to evaluate the pyroprocess equipments from the in-cell arrangements, remote operability and maintainability viewpoint before they are installed in the PRIDE. In last area, a base technology for remote automation of integrated pyroprocess was developed. The developed decladding voloxidizer and automatic equipment will be utilized in the development of a head-end process for pyroprocessing. In addition, the developed servo-manipulator will be used for remote operation and maintenance of the pyroprocess equipments in the PRIDE. The constructed digital mock-up and remote handling evaluation mock-up will be also used to verify and improve the pyroprocess equipments for the PRIDE application. Moreover, these remote technologies described above can be directly used in the PRIDE and applied for the KAPF (Korea Advanced Pyroprocess Facility) development

Preliminary Evaluation on Characteristics of Waste from Pyro-processing (FS v5.1)

International Nuclear Information System (INIS)

Kim, In-Young; Choi, Heui-Joo

2016-01-01

In this study, characteristic of waste from pyro-processing which based on material balance FS v5.1 is evaluated for revising of A-KRS concept. To reduce volume and toxicity of PWR SNFs, the P and T Technology using pyro-processing and SFR is under development in KAERI. In accordance with this R and D, the A-KRS was developed by KAERI for disposal of waste from pyro-processing. After A-KRS concept development, material balance has been revised and characteristics of waste have been changed. To solve impending saturation of storage capacity of NPP sites, national policy on SNF management seems to be determined shortly. Demand on detailed analysis on impact of P and T using pyro-processing and SFR as base data is increasing. To compare direct disposal scenario to the P and T scenario using pyro-processing and SFR, updating of A-KRS reflecting amendment of material balance is required. In this study, characteristic of waste from pyro-processing which based on material balance FS v5.1 is evaluated. Every 15 types of outputs generated from pyro-processing are evaluated. Great reduction can be achieved by complete reuse of U/TRU/RE in SFR, because most of decay heat, radioactivity and radiotoxicity are generated from U/TRU/RE ingot. Within about 300 years, the fly ash filter containing Cs, Sr containing salt waste are important waste in perspective of decay heat and radioactivity. Importance of RE containing salt waste reduced. Management of hold-ups must be clarified because hold-ups take large portion of decay heat, radioactivity in the material balance FS v5.1

Preliminary Evaluation on Characteristics of Waste from Pyro-processing (FS v5.1)

Energy Technology Data Exchange (ETDEWEB)

Kim, In-Young; Choi, Heui-Joo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

In this study, characteristic of waste from pyro-processing which based on material balance FS v5.1 is evaluated for revising of A-KRS concept. To reduce volume and toxicity of PWR SNFs, the P and T Technology using pyro-processing and SFR is under development in KAERI. In accordance with this R and D, the A-KRS was developed by KAERI for disposal of waste from pyro-processing. After A-KRS concept development, material balance has been revised and characteristics of waste have been changed. To solve impending saturation of storage capacity of NPP sites, national policy on SNF management seems to be determined shortly. Demand on detailed analysis on impact of P and T using pyro-processing and SFR as base data is increasing. To compare direct disposal scenario to the P and T scenario using pyro-processing and SFR, updating of A-KRS reflecting amendment of material balance is required. In this study, characteristic of waste from pyro-processing which based on material balance FS v5.1 is evaluated. Every 15 types of outputs generated from pyro-processing are evaluated. Great reduction can be achieved by complete reuse of U/TRU/RE in SFR, because most of decay heat, radioactivity and radiotoxicity are generated from U/TRU/RE ingot. Within about 300 years, the fly ash filter containing Cs, Sr containing salt waste are important waste in perspective of decay heat and radioactivity. Importance of RE containing salt waste reduced. Management of hold-ups must be clarified because hold-ups take large portion of decay heat, radioactivity in the material balance FS v5.1.

A novel framework for intelligent signal detection via artificial neural networks for cyclic voltammetry in pyroprocessing technology

International Nuclear Information System (INIS)

Rakhshan Pouri, Samaneh; Manic, Milos; Phongikaroon, Supathorn

2018-01-01

Highlights: •First time ANN implementation toward pyroprocessing safeguards. •Real time monitoring in terms of intelligent materials detection and accountability. •CV simulation via ANN showing a high accuracy of prediction for the unseen situation. •Elimination of trial and error approach to avoid overfitting in learning. -- Abstract: Electrorefiner (ER) is the heart of pyroprocessing technology which contains different fission, rare-earth, and transuranic chloride compositions during the operation. This is still a developing technology that needs to be advanced for the commercial reprocessing design of used nuclear fuel (UNF) in terms of intelligent materials detection and accountability towards safeguards. A novel signal detection, artificial neural network (ANN), has been proposed in this study to apply on massive ER systemic parameters to simulate cyclic voltammetry (CV) graphs for the unseen situation. ANN could be trained to mimic the system by driving the data sets interrelation between variables to provide current and potential simulated data sets with a high accuracy of prediction. For this purpose, over 230,000 experimental data points reported in literature have been explored—0.5–5 wt% of zirconium chloride (ZrCl 4 ) in LiCl-KCl molten salt with different scan rates at 773 K. This study has illustrated a new framework of ANN implementation to eliminate trial and error approach by comparing the average error of one to three hidden layers with different number of neurons. In addition, this framework results in finding a preferable balance between underfitting and overfitting in deep learning. Furthermore, simulated CV graphs were compared with the experimental data and illustrated a reasonable prediction. The results reveal two structures with three hidden layers providing a good prediction with a low average error. The outcomes indicate that ANN has a strong potential in applying toward safeguards for pyroprocessing technology.

Development of demonstration facility design technology for advanced nuclear fuel cycle process

International Nuclear Information System (INIS)

Cho, Il Je; You, G. S.; Choung, W. M.; Lee, E. P.; Hong, D. H.; Lee, W. K.; Ku, J. H.; Moon, S. I.; Kwon, K. C.; Lee, K. I. and other

2012-04-01

PRIDE Facility, pyroprocess mock-up facility, is the first facility that is operated in inert atmosphere in the country. By using the facility, the functional requirements and validity of pyroprocess technology and facility related to the advanced fuel cycle can be verified with a low cost. Then, PRIDE will contribute to evaluate the technology viability, proliferation resistance and possibility of commercialization of the pyroprocess technology. It is essential to develop design technologies for the advanced nuclear fuel cycle demonstration facilities and complete the detailed design of PRIDE facility with capabilities of the stringent inert atmosphere control, fully remote operation which are necessary to develop the high-temperature molten salts technology. For these, it is necessary to design the essential equipment of large scale inert cell structure and the control system to maintain the inert atmosphere, and evaluate the safety. To construct the hot cell system which is appropriate for pyroprocess, some design technologies should be developed, which include safety evaluation for effective operation and maintenance, radiation safety analysis for hot cell, structural analysis, environmental evaluation, HVAC systems and electric equipment

Development of a Remote Handling System in an Integrated Pyroprocessing Facility

Directory of Open Access Journals (Sweden)

Hyo Jik Lee

2013-10-01

Full Text Available Over the course of a decade-long research programme, the Korea Atomic Energy Research Institute (KAERI has developed several remote handling systems for use in pyroprocessing research facilities. These systems are now used successfully for the operation and maintenance of processing equipment. The most recent remote handling system is the bridge-transported dual arm servo-manipulator system (BDSM, which is used for remote operation at the world's largest pyroprocess integrated inactive demonstration facility (PRIDE. Accurate and reliable servo-control is the basic requirement for the BDSM to accomplish any given tasks successfully in a hotcell environment. To achieve this end, the hardware and software of a digital signal processor-based remote control system were fully custom-developed and implemented to control the BDSM. To reduce the residual vibration of the BDSM, several input profiles, including input shaping, were carefully chosen and evaluated. Furthermore, a time delay controller was employed to achieve good tracking performance and systematic gain tuning. The experimental results demonstrate that the applied control algorithms are more effective than conventional approaches. The BDSM successfully completed its performance tests at a mock-up and was installed at PRIDE for real-world operation. The remote handling system at KAERI is expected to advance the actualization of pyroprocessing.

Development of nuclear fuel cycle remote handling technology

International Nuclear Information System (INIS)

Kim, K. H.; Park, B. S.; Kim, S. H.

2010-04-01

This report presents the development of remote handling systems and remote equipment for use in the pyprocessing verification at the PRIDE (PyRoprocess Integrated inactive Demonstration facility). There are three areas conducted in this work. In first area, developed were the prototypes of an engineering-scale high-throughput decladding voloxidizer which is capable of separating spent fuel rod-cuts into hulls and powder and collecting them separately and an automatic equipment which is capable of collecting residual powder remaining on separated hulls. In second area, a servo-manipulator prototype was developed to operate and maintain pyroprocess equipment located at the argon cell of the PRIDE in a remote manner. A servo-manipulator with dual arm that is mounted on the lower part of a bridge transporter will be installed on the ceiling of the in-cell and can travel the length of the ceiling. In last area, a simulator was developed to simulate and evaluate the design developments of the pyroprocess equipment from the in-cell arrangements, remote operability and maintainability viewpoint in a virtual process environment in advance before they are constructed. The developed decladding voloxidizer and automatic equipment will be utilized in the development of a head-end process for pyroprocessing. In addition, the developed servo-manipulator will be installed in the PRIDE and used for remote operation and maintenance of the pyroprocess equipment. The developed simulator will be also used to verify and improve the design of the pyroprocess equipment for the PRIDE application. Moreover, these remote technologies described above can be directly used in the PRIDE and applied for the ESPF (Engineering Scale Pyroprocess Facility) and KAPF (Korea Advanced Pyroprocess Facility) development

Development of High-Temperature Transport System for Molten Salt in Pyroprocessing

International Nuclear Information System (INIS)

Lee, Sung Ho; Kim, In Tae; Park, Sung Bin

2014-01-01

The electrorefining process, which is a key process in pyroprocessing, is composed of two parts, electrorefining to deposit a uranium with a solid cathode and electrowinning to co-deposit TRU and RE with a liquid cadmium cathode (LCC). As the electrorefining operation proceedes, TRU and RE are accumulated in electrolyte LiCl-KCl salt, and after the electrorefining process, the molten salt used in an electrorefining reactor should by transported to the next process, the electrowinning process, to recover U/TRU/RE; Thus, a molten salt transfer system by suction is now being developed. An apparatus for suction transport experiments was designed and constructed for the development of high- temperature molten salt transport technology. Suction transport experiments were performed using LiC-KCl eutectic salt. The feasibility of pyro-reprocessing has been demonstrated through many laboratory-scale experiments. In pyroprocessing, a eutectic LiCl-KCl salt was used as a liquid elextrolyte for a recovery of actinides. However, reliable transport technologies for these high temperature liquids have not yet been developed. A preliminary study on high-temperature transport technology for molten salt by suction is now being carried out. In this study, three different salt transport technologies (gravity, suction pump, and centrifugal pump) were investigated to select the most suitable method for molten salt transport. An apparatus for suction transport experiments was designed and installed for the development of high-temperature molten salt transport technology. Basic preliminary suction transport experiments were carried out using the prepared LiC-KCl eutectic salt at 500 .deg. C to observe the transport behavior of LiCl-KCl molten salt. In addition, a PRIDE salt transport system was designed and installed for an engineering-scale salt transport demonstration. Several types of suction transport experiments using molten salt (LiCl-KCl eutectics) for the development of a high

Development of High-Temperature Transport System for Molten Salt in Pyroprocessing

Energy Technology Data Exchange (ETDEWEB)

Lee, Sung Ho; Kim, In Tae; Park, Sung Bin [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-05-15

The electrorefining process, which is a key process in pyroprocessing, is composed of two parts, electrorefining to deposit a uranium with a solid cathode and electrowinning to co-deposit TRU and RE with a liquid cadmium cathode (LCC). As the electrorefining operation proceedes, TRU and RE are accumulated in electrolyte LiCl-KCl salt, and after the electrorefining process, the molten salt used in an electrorefining reactor should by transported to the next process, the electrowinning process, to recover U/TRU/RE; Thus, a molten salt transfer system by suction is now being developed. An apparatus for suction transport experiments was designed and constructed for the development of high- temperature molten salt transport technology. Suction transport experiments were performed using LiC-KCl eutectic salt. The feasibility of pyro-reprocessing has been demonstrated through many laboratory-scale experiments. In pyroprocessing, a eutectic LiCl-KCl salt was used as a liquid elextrolyte for a recovery of actinides. However, reliable transport technologies for these high temperature liquids have not yet been developed. A preliminary study on high-temperature transport technology for molten salt by suction is now being carried out. In this study, three different salt transport technologies (gravity, suction pump, and centrifugal pump) were investigated to select the most suitable method for molten salt transport. An apparatus for suction transport experiments was designed and installed for the development of high-temperature molten salt transport technology. Basic preliminary suction transport experiments were carried out using the prepared LiC-KCl eutectic salt at 500 .deg. C to observe the transport behavior of LiCl-KCl molten salt. In addition, a PRIDE salt transport system was designed and installed for an engineering-scale salt transport demonstration. Several types of suction transport experiments using molten salt (LiCl-KCl eutectics) for the development of a high

Investigations for the Recycle of Pyroprocessed Uranium

Science.gov (United States)

Westphal, B. R.; Price, J. C.; Chambers, E. E.; Patterson, M. N.

Given the renewed interest in uranium from the pyroprocessing of used nuclear fuel in a molten salt system, the two biggest hurdles for marketing the uranium are radiation levels and transuranic content. A radiation level as low as possible is desired so that handling operations can be performed directly with the uranium. The transuranic content of the uranium will affect the subsequent waste streams generated and, thus also should be minimized. Although the pyroprocessing technology was originally developed without regard to radiation and transuranic levels, adaptations to the process have been considered. Process conditions have been varied during the distillation and casting cycles of the process with increasing temperature showing the largest effect on the reduction of radiation levels. Transuranic levels can be reduced significantly by incorporating a pre-step in the salt distillation operation to remove a majority of the salt prior to distillation.

Basic requirements for a preliminary conceptual design of the Korea advanced pyroprocess facility (KAPF)

Energy Technology Data Exchange (ETDEWEB)

Lee, Ho Hee; Ko, Won Il; Chang, Hong Lae; Song, Dae Yong; Kwon, Eun Ha; Lee, Jung Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-12-15

Korea Atomic Energy Research Institute (KAERI) has been developing technologies for pyroprocessing for spent PWR fuels. This study is part of a long term R and D program in Korea to develop an advanced recycle system that has the potential to meet and exceed the proliferation resistance, waste minimization, resource minimization, safety and economic goals of approved Korean Government energy policy, as well as the Generation IV International Forum (GIF) program. To support this R and D program, KAERI requires that an independent estimate be made of the conceptual design and cost for construction and operation of a 'Korea Advanced Pyroprocessing Facility', This document describes the basic requirements for preliminary conceptual design of the Korea Advanced Pyroprocess Facility (KAPF). The presented requirements will be modified to be more effective and feasible on an engineering basis during the subsequent design process.

Basic requirements for a preliminary conceptual design of the Korea advanced pyroprocess facility (KAPF)

International Nuclear Information System (INIS)

Lee, Ho Hee; Ko, Won Il; Chang, Hong Lae; Song, Dae Yong; Kwon, Eun Ha; Lee, Jung Won

2008-12-01

Korea Atomic Energy Research Institute (KAERI) has been developing technologies for pyroprocessing for spent PWR fuels. This study is part of a long term R and D program in Korea to develop an advanced recycle system that has the potential to meet and exceed the proliferation resistance, waste minimization, resource minimization, safety and economic goals of approved Korean Government energy policy, as well as the Generation IV International Forum (GIF) program. To support this R and D program, KAERI requires that an independent estimate be made of the conceptual design and cost for construction and operation of a 'Korea Advanced Pyroprocessing Facility', This document describes the basic requirements for preliminary conceptual design of the Korea Advanced Pyroprocess Facility (KAPF). The presented requirements will be modified to be more effective and feasible on an engineering basis during the subsequent design process

Discrete Event System Based Pyroprocessing Modeling and Simulation: Oxide Reduction

International Nuclear Information System (INIS)

Lee, H. J.; Ko, W. I.; Choi, S. Y.; Kim, S. K.; Hur, J. M.; Choi, E. Y.; Im, H. S.; Park, K. I.; Kim, I. T.

2014-01-01

Dynamic changes according to the batch operation cannot be predicted in an equilibrium material flow. This study began to build a dynamic material balance model based on the previously developed pyroprocessing flowsheet. As a mid- and long-term research, an integrated pyroprocessing simulator is being developed at the Korea Atomic Energy Research Institute (KAERI) to cope with a review on the technical feasibility, safeguards assessment, conceptual design of facility, and economic feasibility evaluation. The most fundamental thing in such a simulator development is to establish the dynamic material flow framework. This study focused on the operation modeling of pyroprocessing to implement a dynamic material flow. As a case study, oxide reduction was investigated in terms of a dynamic material flow. DES based modeling was applied to build a pyroprocessing operation model. A dynamic material flow as the basic framework for an integrated pyroprocessing was successfully implemented through ExtendSim's internal database and item blocks. Complex operation logic behavior was verified, for example, an oxide reduction process in terms of dynamic material flow. Compared to the equilibrium material flow, a model-based dynamic material flow provides such detailed information that a careful analysis of every batch is necessary to confirm the dynamic material balance results. With the default scenario of oxide reduction, the batch mass balance was verified in comparison with a one-year equilibrium mass balance. This study is still under progress with a mid-and long-term goal, the development of a multi-purpose pyroprocessing simulator that is able to cope with safeguards assessment, economic feasibility, technical evaluation, conceptual design, and support of licensing for a future pyroprocessing facility

Safety aspects of the IFR pyroprocess fuel cycle

International Nuclear Information System (INIS)

Forrester, R.J.; Lineberry, M.J.; Charak, I.; Tessier, J.H.; Solbrig, C.W.; Gabor, J.D.

1989-01-01

This paper addresses the important safety considerations related to the unique Integral Fast Reactor (IFR) fuel cycle technology, the pyroprocess. Argonne has been developing the IFR since 1984. It is a liquid metal cooled reactor, with a unique metal alloy fuel, and it utilizes a radically new fuel cycle. An existing facility, the Hot Fuel Examination Facility-South (HFEF/S) is being modified and equipped to provide a complete demonstration of the fuel cycle. This paper will concentrate on safety aspects of the future HFEF/S operation, slated to begin late next year. HFEF/S is part of Argonne's complex of reactor test facilities located on the Idaho National Engineering Laboratory. HFEF/S was originally put into operation in 1964 as the EBR-II Fuel Cycle Facility (FCF) (Stevenson, 1987). From 1964--69 FCF operated to demonstrate an earlier and incomplete form of today's pyroprocess, recycling some 400 fuel assemblies back to EBR-II. The FCF mission was then changed to one of an irradiated fuels and materials examination facility, hence the name change to HFEF/S. The modifications consist of activities to bring the facility into conformance with today's much more stringent safety standards, and, of course, providing the new process equipment. The pyroprocess and the modifications themselves are described more fully elsewhere (Lineberry, 1987; Chang, 1987). 18 refs., 5 figs., 2 tabs

Spent fuel pyroprocessing demonstration

International Nuclear Information System (INIS)

McFarlane, L.F.; Lineberry, M.J.

1995-01-01

A major element of the shutdown of the US liquid metal reactor development program is managing the sodium-bonded spent metallic fuel from the Experimental Breeder Reactor-II to meet US environmental laws. Argonne National Laboratory has refurbished and equipped an existing hot cell facility for treating the spent fuel by a high-temperature electrochemical process commonly called pyroprocessing. Four products will be produced for storage and disposal. Two high-level waste forms will be produced and qualified for disposal of the fission and activation products. Uranium and transuranium alloys will be produced for storage pending a decision by the US Department of Energy on the fate of its plutonium and enriched uranium. Together these activities will demonstrate a unique electrochemical treatment technology for spent nuclear fuel. This technology potentially has significant economic and technical advantages over either conventional reprocessing or direct disposal as a high-level waste option

Development of Pyro-separation Technology Based on Molten Salt Electrolysis

Energy Technology Data Exchange (ETDEWEB)

Shim, Joon Bo; Kim, E. H.; Yoo, J. H. (and others)

2007-06-15

The focus of this study was to develop recovery technologies in the pyroprocessing. The unit processes of the project can be classified into two groups; electro-refining process to recover uranium and long-lived nuclides, and cathode processing to produce a metal ingot both from a salt-contained metal and from Cd-contained metal. This project has been carried out for the third phase period of the long-term nuclear R and D program, and focused on the development of key technologies of the pyroprocessing such as electrorefining, draw down and cathode processing. Mock-up system of 1 kg-U/batch was built for performance tests which were conducted to ensure the adequacy of the research and development of the pyroprocessing technology. The experiments were carried out through bench-scale inactive tests except for uranium. In particular, the sticking problem was inevitable in the US's Mark-V and PEER electrorefiner. As a result of this study, a graphite cathode was developed, which exhibited self-scraping behavior and did not need scraping step. The design of an electrorefiner could be simplified, and the throughput was enhanced due to an increased cathode area. A long-term R and D plan was established to develop pyroprocessing technology. In the near term, the results of the current project will be utilized in the next phase of the R and D plan ('07 - '10), and long-term wise, is expected to contribute to recovering fuel materials for transmutation in a Gen-IV reactor.

Development of Pyro-separation Technology Based on Molten Salt Electrolysis

International Nuclear Information System (INIS)

Shim, Joon Bo; Kim, E. H.; Yoo, J. H.

2007-06-01

The focus of this study was to develop recovery technologies in the pyroprocessing. The unit processes of the project can be classified into two groups; electro-refining process to recover uranium and long-lived nuclides, and cathode processing to produce a metal ingot both from a salt-contained metal and from Cd-contained metal. This project has been carried out for the third phase period of the long-term nuclear R and D program, and focused on the development of key technologies of the pyroprocessing such as electrorefining, draw down and cathode processing. Mock-up system of 1 kg-U/batch was built for performance tests which were conducted to ensure the adequacy of the research and development of the pyroprocessing technology. The experiments were carried out through bench-scale inactive tests except for uranium. In particular, the sticking problem was inevitable in the US's Mark-V and PEER electrorefiner. As a result of this study, a graphite cathode was developed, which exhibited self-scraping behavior and did not need scraping step. The design of an electrorefiner could be simplified, and the throughput was enhanced due to an increased cathode area. A long-term R and D plan was established to develop pyroprocessing technology. In the near term, the results of the current project will be utilized in the next phase of the R and D plan ('07 - '10), and long-term wise, is expected to contribute to recovering fuel materials for transmutation in a Gen-IV reactor

Development of a methodology to evaluate material accountability in pyroprocess

Science.gov (United States)

Woo, Seungmin

This study investigates the effect of the non-uniform nuclide composition in spent fuel on material accountancy in the pyroprocess. High-fidelity depletion simulations are performed using the Monte Carlo code SERPENT in order to determine nuclide composition as a function of axial and radial position within fuel rods and assemblies, and burnup. For improved accuracy, the simulations use short burnups step (25 days or less), Xe-equilibrium treatment (to avoid oscillations over burnup steps), axial moderator temperature distribution, and 30 axial meshes. Analytical solutions of the simplified depletion equations are built to understand the axial non-uniformity of nuclide composition in spent fuel. The cosine shape of axial neutron flux distribution dominates the axial non-uniformity of the nuclide composition. Combined cross sections and time also generate axial non-uniformity, as the exponential term in the analytical solution consists of the neutron flux, cross section and time. The axial concentration distribution for a nuclide having the small cross section gets steeper than that for another nuclide having the great cross section because the axial flux is weighted by the cross section in the exponential term in the analytical solution. Similarly, the non-uniformity becomes flatter as increasing burnup, because the time term in the exponential increases. Based on the developed numerical recipes and decoupling of the results between the axial distributions and the predetermined representative radial distributions by matching the axial height, the axial and radial composition distributions for representative spent nuclear fuel assemblies, the Type-0, -1, and -2 assemblies after 1, 2, and 3 depletion cycles, is obtained. These data are appropriately modified to depict processing for materials in the head-end process of pyroprocess that is chopping, voloxidation and granulation. The expectation and standard deviation of the Pu-to-244Cm-ratio by the single granule

Partition of actinides and fission products between metal and molten salt phases: Theory, measurement, and application to IFR pyroprocess development

International Nuclear Information System (INIS)

Ackerman, J.P.; Johnson, T.R.

1993-01-01

The chemical basis of Integral Fast Reactor fuel reprocessing (pyroprocessing) is partition of fuel, cladding, and fission product elements between molten LiCl-KCl and either a solid metal phase or a liquid cadmium phase. The partition reactions are described herein, and the thermodynamic basis for predicting distributions of actinides and fission products in the pyroprocess is discussed. The critical role of metal-phase activity coefficients, especially those of rare earth and the transuranic elements, is described. Measured separation factors, which are analogous to equilibrium constants but which involve concentrations rather than activities, are presented. The uses of thermodynamic calculations in process development are described, as are computer codes developed for calculating material flows and phase compositions in pyroprocessing

Partition of actinides and fission products between metal and molten salt phases: Theory, measurement, and application to IFR pyroprocess development

Energy Technology Data Exchange (ETDEWEB)

Ackerman, J.P.; Johnson, T.R.

1993-10-01

The chemical basis of Integral Fast Reactor fuel reprocessing (pyroprocessing) is partition of fuel, cladding, and fission product elements between molten LiCl-KCl and either a solid metal phase or a liquid cadmium phase. The partition reactions are described herein, and the thermodynamic basis for predicting distributions of actinides and fission products in the pyroprocess is discussed. The critical role of metal-phase activity coefficients, especially those of rare earth and the transuranic elements, is described. Measured separation factors, which are analogous to equilibrium constants but which involve concentrations rather than activities, are presented. The uses of thermodynamic calculations in process development are described, as are computer codes developed for calculating material flows and phase compositions in pyroprocessing.

The IFR pyroprocessing for high-level waste minimization

International Nuclear Information System (INIS)

Laidler, J.J.

1993-01-01

The process developed for the recycle of integral fast reactor (IFR) spent fuel utilizes a combination of pyrometallurgical and electrochemical methods and has been termed pyroprocessing. The process has been operated at full scale with simulated spent fuel using nonradioactive fission product elements. A comprehensive demonstration of the pyroprocessing of irradiated IFR fuel will begin later this year. Pyroprocessing involves the anodic dissolution of all the constituent elements of the IFR spent fuel and controlled electrotransport (electrorefining) to separate the actinide elements from the fission products present in the spent fuel. The process be applied to the processing of spent light water reactor (LWR) fuel as well, requiring only the addition of a reduction step to convert the LWR fuel as well, requiring only the addition of a reduction step to convert the LWR oxide fuel to metallic form and a separation step to separate uranium from the transuranic (TRU) elements. The TRU elements are then recovered by electroefining in the same manner as the actinides from the IFR high-level wastes arising from pyroprocessing are virtually free of actinides, and the volume of the wastes is minimized by the intrinsic characteristics of the processing of the processing method

Pyroprocessing as a waste management strategy

International Nuclear Information System (INIS)

Hannum, W.H.; Chang, Y.I.; McPheeters, C.C.

1991-01-01

Pyroprocessing, as incorporated in the Integral Fast Reactor (IFR) program, is being developed as a resource-efficient means of providing fuel for a reactor which has outstanding safety characteristics and performance potential. This process has been shown to be an effective way to partition uranium, transuranic elements, and fissions products. Being a gross separation process, it is not compatible with production of pure plutonium, but permits the recycle of essentially all the transuranic material to the Integral Fast Reactor for consumption. Whether this process can also significantly simplify the LWR waste disposal problem depends on the outcome of process development -- estimated to take five years, and of the subsequent applications development programs. If successful, this program could influence the ultimate waste loading of the first repository and modify the requirements for a second repository. This document, discusses the possibility of pyroprocessing being utilized in waste management strategies

Development and characterization of new high-level waste form containing LiCl KCl eutectic salts for achieving waste minimization from pyroprocessing

International Nuclear Information System (INIS)

Cho, Yong Zun; Kim, In Tae; Park, Hwan Seo; Ahn, Byeung Gil; Eun, Hee Chul; Son, Seock Mo; Ah, Su Na

2011-12-01

The purpose of this project is to develop new high level waste (HLW) forms and fabrication processes to dispose of active metal fission products that are removed from electrorefiner salts in the pyroprocessing based fuel cycle. The current technology for disposing of active metal fission products in pyroprocessing involves non selectively discarding of fission product loaded salt in a glass-bonded sodalite ceramic waste form. Selective removal of fission products from the molten salt would greatly minimize the amount of HLW generated and methods were developed to achieve selective separation of fission products during a previous I NERI research project (I NERI 2006 002 K). This I NERI project proceeds from the previous project with the development of suitable waste forms to immobilize the separated fission products. The Korea Atomic Energy Research Institute (KAERI) has focused primarily on developing these waste forms using surrogate waste materials, while the Idaho National Laboratory (INL) has demonstrated fabrication of these waste forms using radioactive electrorefiner salts in hot cell facilities available at INL. Testing and characterization of these radioactive materials was also performed to determine the physical, chemical, and durability properties of the waste forms

Measurement of Irradiated Pyroprocessing Samples via Laser Induced Breakdown Spectroscopy

Energy Technology Data Exchange (ETDEWEB)

Phongikaroon, Supathorn [Virginia Commonwealth Univ., Richmond, VA (United States)

2016-10-31

The primary objective of this research is to develop an applied technology and provide an assessment to remotely measure and analyze the real time or near real time concentrations of used nuclear fuel (UNF) dissolute in electrorefiners. Here, Laser-Induced Breakdown Spectroscopy (LIBS), in UNF pyroprocessing facilities will be investigated. LIBS is an elemental analysis method, which is based on the emission from plasma generated by focusing a laser beam into the medium. This technology has been reported to be applicable in the media of solids, liquids (includes molten metals), and gases for detecting elements of special nuclear materials. The advantages of applying the technology for pyroprocessing facilities are: (i) Rapid real-time elemental analysis|one measurement/laser pulse, or average spectra from multiple laser pulses for greater accuracy in < 2 minutes; (ii) Direct detection of elements and impurities in the system with low detection limits|element specific, ranging from 2-1000 ppm for most elements; and (iii) Near non-destructive elemental analysis method (about 1 g material). One important challenge to overcome is achieving high-resolution spectral analysis to quantitatively analyze all important fission products and actinides. Another important challenge is related to accessibility of molten salt, which is heated in a heavily insulated, remotely operated furnace in a high radiation environment with an argon atmosphere.

Development of interface technology between unit processes in E-Refining process

Energy Technology Data Exchange (ETDEWEB)

Lee, S. H.; Lee, H. S.; Kim, J. G. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2010-10-15

The pyroprocessing is composed mainly four subprocesses, such as an electrolytic reduction, an electrorefining, an electrowinning, and waste salt regeneration/ solidification processes. The electrorefining process, one of main processes which are composed of pyroprocess to recover the useful elements from spent fuel, is under development by Korea Atomic Energy Research Institute as a sub process of pyrochemical treatment of spent PWR fuel. The CERS(Continuous ElectroRefining System) is composed of some unit processes such as an electrorefiner, a salt distiller, a melting furnace for the U-ingot and U-chlorinator (UCl{sub 3} making equipment) as shown in Fig. 1. In this study, the interfaces technology between unit processes in E-Refining system is investigated and developed for the establishment of integrated E-Refining operation system as a part of integrated pyroprocessing

Program of enhancing the Korea-USA cooperation research for the development of proliferation resistant fuel cycle technology

International Nuclear Information System (INIS)

Yang, Myung Seung; Ahn, D. H.; Ko, W. I.

2007-03-01

The objective of the Program is to develop the fuel cycle technology of GEN-IV SFR (Sodium Fast Reactor) system through the Korea-USA cooperation research in order to improve the efficiency of the technology development and to increase the transparency of the research. Since the pyroprocessing research by using actual spent nuclear fuel can not be performed in Korea at present, the active demonstration research will be performed by using the USA national research facilities under the Korea-USA cooperation. Moreover, the development of safeguards technology and the methodology for the evaluation of the proliferation resistance will also be performed under the cooperation. The current cooperation national laboratories of the safeguards and pyroprocessing technology development are LANL (Los Alamos National Lab.) and INL (Idaho National Lab.), respectively. Practical research experience and technical data for the pyroprocessing technology can be achieved through the demonstration of the inactive research results, which was performed in Korea, by using actual spent nuclear fuel. The scope of the cooperation study encompass the electrolytic reduction of oxide spent fuel, electrorefining, liquid cadmium cathode process, TRU fuel fabrication, fuel performance evaluation and related safeguards technology development

Use of pyroprocessing in the preparation of spent fuel for transmutation

Energy Technology Data Exchange (ETDEWEB)

Laidler, J.J. [Argonne National Laboratory, IL (United States)

1995-10-01

Pyrochemical processing, or {open_quotes}pyroprocessing,{close_quotes} of spent fuel offers a number of unique advantages, particularly in comparison with coventional aqueous solvent extraction techniques. Pyroprocessing, in its present version, has been under development for nearly ten years. Emphasis has been placed on the development of a simple, efficient process that features compact, inexpensive process equipment. Particular attention has been paid to the minimization of waste volumes and to the development of a process that is both economic and environmentally sound as well as proliferation-resistant.

Pyroprocess Deployment Analysis and Remote Accessibility Experiment using Digital Mockup and Simulation

International Nuclear Information System (INIS)

Kim, K. H.; Park, H. S.; Kim, S. H.; Choi, C. H.; Lee, H. J.; Park, B. S.; Yoon, G. S.; Kim, K. H.; Kim, H. D.

2009-11-01

Nuclear fuel cycle facility that treats with spent fuel must be designed and manufactured a Pyroprcess facility and process with considering a speciality as every process have to be processed remotely. To prevent an unexpected accident under a circumstance that must operate with a remote manipulator after done the Pyroprocess facility, an procedure related Pyroprocess operation and maintenance need to establish it in the early design stage. To develop the simulator that is mixed by 3D modelling and simulation, a system architecture was designed. A full-scale digital mockup with a real pyroprocess facility was designed and manufactured. An inverse kinematics algorithm of remote manipulator was created in order to simulate an accident and repair that could happen in pyroprocess operation and maintenance under a virtual digital mockup environment. Deployment analysis of process devices through a workspace analysis was carried out and Accessibility analysis by using haptic device was examined

Development of hotcell transportation system technology for high radioactive material

International Nuclear Information System (INIS)

Seo, K. S.; Seo, C. S.; Lee, J. C.

2012-04-01

In the first stage of the research, the transportation and storage characteristics analysis of the pyroprocess materials, the development of horizontal type hot cell transportation system, and the design of interim storage system for the pyroprocess material are conducted. The optimized capacity, transportation frequency and operation period of pyroprocess facility are found using the logistics analysis program developed in this project. A new hot cell transportation system was designed. Through the safety analysis and test for the hot cell transportation system, the design license has been approved. A new type hot cell docking system with superior performance has been developed with a patented rotating lid system. We have reached to a unique concept of interim storage of pyroprocess materials and selected a system through a comparative evaluation of existing ones. In the second stage of the research, transportation/storage/sealing devices for PRIDE recovered material/wastes were developed. And test model for the devices in engineering scale facility were also developed. The design requirements for a vertical docking system were evaluated and the performance assessment using a scaled mock-up was conducted. Integrated storage management technology was evaluated for an efficient management of process materials. A heat transfer simulation and characteristics analysis for the storage system were conducted. The derivation of design requirements, design and fabrication of a canister test model, and preliminary safety assessment were conducted

Current Status of Advanced Nuclear Fuel Cycle technologies

International Nuclear Information System (INIS)

Hwang, Yong Soo; Lee, Jong Hyun

2009-07-01

To expand the use of nuclear energy, SNF from nuclear power plants must be managed in a safe and environmental friendly and the problem of decreasing uranium should be solved. To resolve this, a dry processing technology Pyroprocessing is focused on. The government started to develop of Pyroprocessing technology in 1997. According to the decision of government based of Atomic Energy Commission in December 2008, the Korea Atomic Energy Research Institute will construct PRIDE (Pyroprocess Integrated Inactive DEmonstration Facility) by 2011 to prove a consistent process. If Pyroprocessing technology will be developed in the near future, the size of radioactive waste disposal site can be reduced to 100 times compared to the direct disposal. When this technology will be connected to Fast Reactor. high level nuclear waste management of Hundreds of thousands of years may be reduced to hundreds years. However for the commercialization of Pyroprocessing technology, there are some problems to solve. First, because of none commercial facilities in the world of executive experience, so that the facility design, measurement. management and material flow, the critical need for data accumulation. Second, High-level nuclear waste have been known to generate more than the wet methods, it should continue to reduce technology development. In addition, a careful consideration of the residual uranium generating on process also can maximize the efficiency of reducing. The new concept is being developed in Korea Atomic Energy Research Institute Pyroprocessing technology and nuclear waste processing technology to overcome these drawbacks sUQQested a way

Depreciation cost for the capital investment of a pyroprocess facility

Energy Technology Data Exchange (ETDEWEB)

Kim, S. K.; Lee, S. H.; Ko, W. I. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-10-15

The pyroprocess produces U/TRU metal ingots using four important processes, pretreatment, electrochemical reduction, electrorefining and electrowinning, in order to recycle spent fuel. KAPF+'s capacity is shown the cost that is injected into the KAPF+. The pyroprocess unit cost is data that are essential for inputting to calculate the pyroprocess-Sodiumcooled Fast Reactor (SFR) nuclear fuel cycle cost. Moreover, since the pyroprocess facility's depreciation cost is included in the manufacturing indirect cost of the pyroprocess cost, it can become an important element for judging the pyroprocess' economic viability. Since the pyroprocess unit cost calculates the sum of the costs that are incurred each year by dividing with the total amount of U/TRU ingot produced, the pyroprocess unit cost uncertainty increases as well when the uncertainty of the costs incurred by each year increases. KAPF+, which is a commercialization facility, was set as the cost object, and the existing methods (straightline method and fixed percentage of declining-balance method) used today and the depreciation cost of the ADDM were subjected to a comparative analysis. The results are as follows. First, in case of the straight-line method that calculated the durable period as 40 years, and in case of ADDM that factored in a 5% deceleration rate, the difference in the depreciation costs of $65.26/kgHM and $119.05/kgHM resulted during the first and last years, respectively. Accordingly, it was analyzed that there is a significant difference in terms of the cost of the capital investment every year depending on the depreciation method. Secondly, since the depreciation cost is a component of the manufacturing indirect cost, it is necessary to maintain a trend that is similar to that of the direct labor cost in addition to the direct material cost.

Depreciation cost for the capital investment of a pyroprocess facility

International Nuclear Information System (INIS)

Kim, S. K.; Lee, S. H.; Ko, W. I.

2015-01-01

The pyroprocess produces U/TRU metal ingots using four important processes, pretreatment, electrochemical reduction, electrorefining and electrowinning, in order to recycle spent fuel. KAPF+'s capacity is shown the cost that is injected into the KAPF+. The pyroprocess unit cost is data that are essential for inputting to calculate the pyroprocess-Sodiumcooled Fast Reactor (SFR) nuclear fuel cycle cost. Moreover, since the pyroprocess facility's depreciation cost is included in the manufacturing indirect cost of the pyroprocess cost, it can become an important element for judging the pyroprocess' economic viability. Since the pyroprocess unit cost calculates the sum of the costs that are incurred each year by dividing with the total amount of U/TRU ingot produced, the pyroprocess unit cost uncertainty increases as well when the uncertainty of the costs incurred by each year increases. KAPF+, which is a commercialization facility, was set as the cost object, and the existing methods (straightline method and fixed percentage of declining-balance method) used today and the depreciation cost of the ADDM were subjected to a comparative analysis. The results are as follows. First, in case of the straight-line method that calculated the durable period as 40 years, and in case of ADDM that factored in a 5% deceleration rate, the difference in the depreciation costs of $65.26/kgHM and $119.05/kgHM resulted during the first and last years, respectively. Accordingly, it was analyzed that there is a significant difference in terms of the cost of the capital investment every year depending on the depreciation method. Secondly, since the depreciation cost is a component of the manufacturing indirect cost, it is necessary to maintain a trend that is similar to that of the direct labor cost in addition to the direct material cost

Advanced depreciation cost analysis for a commercial pyroprocess facility in Korea

Energy Technology Data Exchange (ETDEWEB)

Kim, Sung Ki; Ko, Won Il [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Youn, Sae Rom; Gao, Ruxing [University of Science and Technology, Daejeon (Korea, Republic of); Chung, Yang Hon; Bang, Sung Sig [Dept. of Business and Technology Management, University of Science and Technology, Daejeon (Korea, Republic of)

2016-06-15

The purpose of this study is to present a rational depreciation method for a pyroprocess cost calculation. Toward this end, the so-called advanced decelerated depreciation method (ADDM) was developed that complements the limitations of the existing depreciation methods such as the straight-line method and fixed percentage of declining-balance method. ADDM was used to show the trend of the direct material cost and direct labor cost compared to the straight-line or fixed percentage of the declining-balance methods that are often used today. As a result, it was demonstrated that the depreciation cost of the ADDM, which assumed a pyroprocess facility's life period to be 40 years with a deceleration rate of 5%, takes up 4.14% and 27.74% of the pyroprocess unit cost ($781/kg heavy metal) in the 1st and final years, respectively. In other words, it was found that the ADDM can cost the pyroprocess facility's capital investment rationally every year. Finally, ADDM's validity was verified by confirming that the sum of the depreciation cost by year, and the sum of the purchasing cost of the building and equipment, are the same.

Advanced depreciation cost analysis for a commercial pyroprocess facility in Korea

International Nuclear Information System (INIS)

Kim, Sung Ki; Ko, Won Il; Youn, Sae Rom; Gao, Ruxing; Chung, Yang Hon; Bang, Sung Sig

2016-01-01

The purpose of this study is to present a rational depreciation method for a pyroprocess cost calculation. Toward this end, the so-called advanced decelerated depreciation method (ADDM) was developed that complements the limitations of the existing depreciation methods such as the straight-line method and fixed percentage of declining-balance method. ADDM was used to show the trend of the direct material cost and direct labor cost compared to the straight-line or fixed percentage of the declining-balance methods that are often used today. As a result, it was demonstrated that the depreciation cost of the ADDM, which assumed a pyroprocess facility's life period to be 40 years with a deceleration rate of 5%, takes up 4.14% and 27.74% of the pyroprocess unit cost ($781/kg heavy metal) in the 1st and final years, respectively. In other words, it was found that the ADDM can cost the pyroprocess facility's capital investment rationally every year. Finally, ADDM's validity was verified by confirming that the sum of the depreciation cost by year, and the sum of the purchasing cost of the building and equipment, are the same

The pretreatment cost of a pyroprocess facility in Korea

International Nuclear Information System (INIS)

Kim, S. K.; Youn, S. R.; Lee, S. H.; Lee, H. J.; Ko, W. I.

2015-01-01

Shale gas still has many disadvantages such as significant technological difficulties and high costs even when the fracking technology is used to extract shale gas since shale gas is dispersed widely. Moreover, it is estimated that the shale gas can be used for about 60 years, which is comparable to the period estimated for oil deposits. Another concern is that the climate may change due to the discharge of harmful gas produced during the gas extraction process. PRIDE facility producing 10 ton/year uranium ingot was set as the cost object for the cost estimation, and it was possible to increase cost calculation's accuracy level since labor cost and expenses incurred in this facility were the costs incurred in actuality. In the end, First-In, First Out process costing method was used to calculate the pretreatment cost of pyroprocess. According to the cost calculation results, the pretreatment cost was estimated as $195/kgHM and the cost share of the pretreatment of pyroprocess was calculated as 20%. Accordingly, electrochemical reduction process is the process requires most cost, followed by the cost of electro-winning process

The pretreatment cost of a pyroprocess facility in Korea

Energy Technology Data Exchange (ETDEWEB)

Kim, S. K.; Youn, S. R.; Lee, S. H.; Lee, H. J.; Ko, W. I. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-05-15

Shale gas still has many disadvantages such as significant technological difficulties and high costs even when the fracking technology is used to extract shale gas since shale gas is dispersed widely. Moreover, it is estimated that the shale gas can be used for about 60 years, which is comparable to the period estimated for oil deposits. Another concern is that the climate may change due to the discharge of harmful gas produced during the gas extraction process. PRIDE facility producing 10 ton/year uranium ingot was set as the cost object for the cost estimation, and it was possible to increase cost calculation's accuracy level since labor cost and expenses incurred in this facility were the costs incurred in actuality. In the end, First-In, First Out process costing method was used to calculate the pretreatment cost of pyroprocess. According to the cost calculation results, the pretreatment cost was estimated as $195/kgHM and the cost share of the pretreatment of pyroprocess was calculated as 20%. Accordingly, electrochemical reduction process is the process requires most cost, followed by the cost of electro-winning process.

Development of System Engineering Technology for Nuclear Fuel Cycle

International Nuclear Information System (INIS)

Kim, Hodong; Choi, Iljae

2013-04-01

The development of efficient process for spent fuel and establishment of system engineering technology to demonstrate the process are required to develop nuclear energy continuously. The demonstration of pyroprocess technology which is proliferation resistance nuclear fuel cycle technology can reduce spent fuel and recycle effectively. Through this, people's trust and support on nuclear power would be obtained. Deriving the optimum nuclear fuel cycle alternative would contribute to establish a policy on back-end nuclear fuel cycle in the future, and developing the nuclear transparency-related technology would contribute to establish amendments of the ROK-U. S. Atomic Energy Agreement scheduled in 2014

Electrochemical Reduction Process for Pyroprocessing

Energy Technology Data Exchange (ETDEWEB)

Choi, Eun-Young; Hong, Sun-Seok; Park, Wooshin; Im, Hun Suk; Oh, Seung-Chul; Won, Chan Yeon; Cha, Ju-Sun; Hur, Jin-Mok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-06-15

Nuclear energy is expected to meet the growing energy demand while avoiding CO{sub 2} emission. However, the problem of accumulating spent fuel from current nuclear power plants which is mainly composed of uranium oxides should be addressed. One of the most practical solutions is to reduce the spent oxide fuel and recycle it. Next-generation fuel cycles demand innovative features such as a reduction of the environmental load, improved safety, efficient recycling of resources, and feasible economics. Pyroprocessing based on molten salt electrolysis is one of the key technologies for reducing the amount of spent nuclear fuel and destroying toxic waste products, such as the long-life fission products. The oxide reduction process based on the electrochemical reduction in a LiCl-Li{sub 2}O electrolyte has been developed for the volume reduction of PWR (Pressurized Water Reactor) spent fuels and for providing metal feeds for the electrorefining process. To speed up the electrochemical reduction process, the influences of the feed form for the cathode and the type of anode shroud on the reduction rate were investigated.

Discrete event dynamic system (DES)-based modeling for dynamic material flow in the pyroprocess

International Nuclear Information System (INIS)

Lee, Hyo Jik; Kim, Kiho; Kim, Ho Dong; Lee, Han Soo

2011-01-01

A modeling and simulation methodology was proposed in order to implement the dynamic material flow of the pyroprocess. Since the static mass balance provides the limited information on the material flow, it is hard to predict dynamic behavior according to event. Therefore, a discrete event system (DES)-based model named, PyroFlow, was developed at the Korea Atomic Energy Research Institute (KAERI). PyroFlow is able to calculate dynamic mass balance and also show various dynamic operational results in real time. By using PyroFlow, it is easy to rapidly predict unforeseeable results, such as throughput in unit process, accumulated product in buffer and operation status. As preliminary simulations, bottleneck analyses in the pyroprocess were carried out and consequently it was presented that operation strategy had influence on the productivity of the pyroprocess.

Assessment of activity-based pyroprocess costs for an engineering-scale facility in Korea

Energy Technology Data Exchange (ETDEWEB)

Kim, Sung Ki; Ko, Won Il [Nuclear Fuel Cycle Analysis Department, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Bang, Sung Sig [Dept. of Business and Technology Management, Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

2015-12-15

This study set the pyroprocess facility at an engineering scale as a cost object, and presented the cost consumed during the unit processes of the pyroprocess. For the cost calculation, the activity based costing (ABC) method was used instead of the engineering cost estimation method, which calculates the cost based on the conceptual design of the pyroprocess facility. The calculation results demonstrate that the pyroprocess facility's unit process cost is $194/kgHM for pretreatment, $298/kgHM for electrochemical reduction, $226/kgHM for electrorefining, and $299/kgHM for electrowinning. An analysis demonstrated that the share of each unit process cost among the total pyroprocess cost is as follows: 19% for pretreatment, 29% for electrochemical reduction, 22% for electrorefining, and 30% for electrowinning. The total unit cost of the pyroprocess was calculated at $1,017/kgHM. In the end, electrochemical reduction and the electrowinning process took up most of the cost, and the individual costs for these two processes was found to be similar. This is because significant raw material cost is required for the electrochemical reduction process, which uses platinum as an anode electrode. In addition, significant raw material costs are required, such as for Li3PO4, which is used a lot during the salt purification process.

Electrochemical processing of spent nuclear fuels: An overview of oxide reduction in pyroprocessing technology

Directory of Open Access Journals (Sweden)

Eun-Young Choi

2015-12-01

Full Text Available The electrochemical reduction process has been used to reduce spent oxide fuel to a metallic form using pyroprocessing technology for a closed fuel cycle in combination with a metal-fuel fast reactor. In the electrochemical reduction process, oxides fuels are loaded at the cathode basket in molten Li2O–LiCl salt and electrochemically reduced to the metal form. Various approaches based on thermodynamic calculations and experimental studies have been used to understand the electrode reaction and efficiently treat spent fuels. The factors that affect the speed of the electrochemical reduction have been determined to optimize the process and scale-up the electrolysis cell. In addition, demonstrations of the integrated series of processes (electrorefining and salt distillation with the electrochemical reduction have been conducted to realize the oxide fuel cycle. This overview provides insight into the current status of and issues related to the electrochemical processing of spent nuclear fuels.

Methodology for categorization of nuclear material in pyroprocessing facility

Energy Technology Data Exchange (ETDEWEB)

Lee, Chanki; Choi, Sungyeol [UNIST, Ulsan (Korea, Republic of); Kim, Woo Jin; Kim, Min Su; Jeong, Yon Hong [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2016-10-15

For the pyroprocessing facility to be commercialized in future, current regulations should be evaluated and developed in advance, based on the new types of nuclear materials in the facility. Physical protection system, especially, requires reasonable and reliable categorization of nuclear materials, to prevent from the theft of nuclear materials. In this paper, therefore, current categorization methods of nuclear material are investigated and applied to the pyroprocessing facility. After inconsistencies and gaps are found among methods, they are compared and discussed based on eight considering points (i.e, degrees of attractiveness, levels of category, discount factor, physical barriers, chemical barriers, isotopic barriers, radiological barriers, and capabilities of adversaries), to roughly suggest a new method for categorization. Current categorization methods of nuclear material, including IAEA's INFCIRC/225, U.S. DOE's method, newly expected U.S. NRC's method, FOM, and Bunn's approach, are different and can bring inconsistencies of physical protection requirements. The gap among methods will be significant if advanced fuel cycles are applied to them for the future. For example, the categorization results of 5 target materials in pyroprocessing facility show clear inconsistencies, while TRU ingot is considered the most attractive material. To resolve inconsistencies, it is necessary to determine new method suitable to pyroproessing facility, by considering the effects of eight points (i.e, degrees of attractiveness, levels of category, discount factor, physical barriers, chemical barriers, isotopic barriers, radiological barriers, and capabilities of adversaries)

Methodology for categorization of nuclear material in pyroprocessing facility

International Nuclear Information System (INIS)

Lee, Chanki; Choi, Sungyeol; Kim, Woo Jin; Kim, Min Su; Jeong, Yon Hong

2016-01-01

For the pyroprocessing facility to be commercialized in future, current regulations should be evaluated and developed in advance, based on the new types of nuclear materials in the facility. Physical protection system, especially, requires reasonable and reliable categorization of nuclear materials, to prevent from the theft of nuclear materials. In this paper, therefore, current categorization methods of nuclear material are investigated and applied to the pyroprocessing facility. After inconsistencies and gaps are found among methods, they are compared and discussed based on eight considering points (i.e, degrees of attractiveness, levels of category, discount factor, physical barriers, chemical barriers, isotopic barriers, radiological barriers, and capabilities of adversaries), to roughly suggest a new method for categorization. Current categorization methods of nuclear material, including IAEA's INFCIRC/225, U.S. DOE's method, newly expected U.S. NRC's method, FOM, and Bunn's approach, are different and can bring inconsistencies of physical protection requirements. The gap among methods will be significant if advanced fuel cycles are applied to them for the future. For example, the categorization results of 5 target materials in pyroprocessing facility show clear inconsistencies, while TRU ingot is considered the most attractive material. To resolve inconsistencies, it is necessary to determine new method suitable to pyroproessing facility, by considering the effects of eight points (i.e, degrees of attractiveness, levels of category, discount factor, physical barriers, chemical barriers, isotopic barriers, radiological barriers, and capabilities of adversaries)

A Deterministic Safety Assessment of a Pyro-processed Waste Repository

International Nuclear Information System (INIS)

Lee, Youn Myoung; Jeong, Jong Tae; Choi, Jong Won

2012-01-01

A GoldSim template program for a safety assessment of a hybrid-typed repository system, called 'A-KRS', in which two kinds of pyro-processed radioactive wastes, low-level metal wastes and ceramic high-level wastes that arise from the pyro-processing of PWR nuclear spent fuels are disposed of, has been developed. This program is ready both for a deterministic and probabilistic total system performance assessment which is able to evaluate nuclide release from the repository and farther transport into the geosphere and biosphere under various normal, disruptive natural and manmade events, and scenarios. The A-KRS has been deterministically assessed with 5 various normal and abnormal scenarios associated with nuclide release and transport in and around the repository. Dose exposure rates to the farming exposure group have been evaluated in accordance with all the scenarios and then compared among other.

PYRO - new capability for isotopic mass tracking in pyroprocess simulation

International Nuclear Information System (INIS)

Liaw, J.R.; Ackerman, J.P.

1990-01-01

A new computational code package called PYRO has been developed to support the IFR fuel recycle demonstration project in the HFEF/S facility at ANL-W. The basic pyrochemical code PYRO1 1 models the atomic mass flows and phase compositions of 48 essential chemical elements involved in the pyroprocess. It has been extended to PYRO1 2 by linking with the ORIGEN code to track more than 1000 isotopic species, their radioactive decays, and related phenomena. This paper first describes the pyroprocess to be modeled and the pyrochemical capability that has been implemented in PYRO1 1 , and then gives a full account on the algorithm of extending it to PYRO1 2 for isotopic mass tracking. Results from several scoping and simulation runs will be discussed to illustrate the significance of modeling in process radioactive decays

Developing a Signature Based Safeguards Approach for the Electrorefiner and Salt Cleanup Unit Operations in Pyroprocessing Facilities

Energy Technology Data Exchange (ETDEWEB)

Murphy, Chantell Lynne-Marie [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-01-27

Traditional nuclear materials accounting does not work well for safeguards when applied to pyroprocessing. Alternate methods such as Signature Based Safeguards (SBS) are being investigated. The goal of SBS is real-time/near-real-time detection of anomalous events in the pyroprocessing facility as they could indicate loss of special nuclear material. In high-throughput reprocessing facilities, metric tons of separated material are processed that must be accounted for. Even with very low uncertainties of accountancy measurements (<0.1%) the uncertainty of the material balances is still greater than the desired level. Novel contributions of this work are as follows: (1) significant enhancement of SBS development for the salt cleanup process by creating a new gas sparging process model, selecting sensors to monitor normal operation, identifying safeguards-significant off-normal scenarios, and simulating those off-normal events and generating sensor output; (2) further enhancement of SBS development for the electrorefiner by simulating off-normal events caused by changes in salt concentration and identifying which conditions lead to Pu and Cm not tracking throughout the rest of the system; and (3) new contribution in applying statistical techniques to analyze the signatures gained from these two models to help draw real-time conclusions on anomalous events.

PYRO: New capability for isotopic mass tracking in pyroprocess simulation

International Nuclear Information System (INIS)

Liaw, J.R.; Ackerman, J.P.

1990-01-01

A new computational code package called PYRO has been developed to support the IFR fuel recycle demonstration project in the HFEF/S facility at ANL-W. The basic pyrochemical code PYRO1-1 models the atomic mass flows and phase compositions of 48 essential chemical elements involved in the pyroprocess. It has been extended to PYRO1-2 by linking with the ORIGEN code to track more than 1000 isotopic species, their radioactive decays, and related phenomena. This paper first describes the pyroprocess to be modeled and the pyrochemical capability that has been implemented in PYRO1-1, and then gives a full account on the algorithm of extending it to PYRO1-2 for isotopic mass tracking. Results from several scoping and simulation runs will be discussed to illustrate the significance of modeling in-process radioactive decays. 16 refs., 8 figs., 2 tabs

Cost analysis of a commercial pyroprocess facility on the basis of a conceptual design in Korea

International Nuclear Information System (INIS)

Kim, S.K.; Ko, W.I.; Youn, S.R.; Gao, Ruxing

2015-01-01

Highlights: • Pyroprocess facility’s direct cost was calculated based on the conceptual design. • The unit cost of pyroprocess was calculated as $781/kgHM. • The unit cost was increased by 3%, considering labor allocation standards. • The operating and maintenance cost was identified as a main cost driver. - Abstract: This study postulated a commercial pyroprocess facility (KAPF+: Korea Advanced Pyroprocess Facility Plus) with a processing capacity of 400 tons/year as a cost object, and utilized an engineering cost estimation method based on a conceptual design to present the results of the total cost and unit cost estimation. According to the calculation results, the total cost and unit cost were calculated with k$779,386 and $781/kgHM, respectively. Moreover, the key cost driver was manifested as the operating and maintenance costs. In particular, equipment replacement cost was identified as an important cost driver. In addition, for an increasingly accurate cost estimation, the calculation results and allocation method of the indirect cost were reanalyzed. Finally the pyroprocess unit cost increased $5 when calculated the indirect cost using the labor time as the allocation standard. Meanwhile, the pyroprocess unit cost increased $22 as a result of allocating the indirect cost using the uniform labor cost as the cost allocation standard. Accordingly, an indirect cost allocation standard was manifested as the factor that exerts a significant effect on the pyroprocess unit cost

A Probabilistic Safety Assessment of a Pyro-processed Waste Repository

International Nuclear Information System (INIS)

Lee, Youn Myoung; Jeong, Jong Tae

2012-01-01

A GoldSim template program for a safety assessment of a hybrid-typed repository system, called A-KRS, in which two kinds of pyro-processed radioactive wastes, low-level metal wastes and ceramic high-level wastes that arise from the pyro-processing of PWR nuclear spent fuels are disposed of, has been developed. This program is ready both for a deterministic and probabilistic total system performance assessment which is able to evaluate nuclide release from the repository and farther transport into the geosphere and biosphere under various normal, disruptive natural and manmade events, and scenarios. The A-KRS has been probabilistically assessed with 9 selected input parameters, each of which has its own statistical distribution for a normal release and transport scenario associated with nuclide release and transport in and around the repository. Probabilistic dose exposure rates to the farming exposure group have been evaluated. A sensitivity of 9 selected parameters to the result has also been investigated to see which parameter is more sensitive and important to the exposure rates.

An International Peer Review of the Programme for the Deep Geological Disposal of High Level Radioactive Waste from Pyro-Processing in the Republic of Korea. Report of an IAEA International Review Team

International Nuclear Information System (INIS)

2013-09-01

The development of a radioactive waste disposal system is indispensable in maintaining the sustainability of nuclear energy. The Korea Atomic Energy Research Institute (KAERI) has studied the direct geological disposal of spent nuclear fuel since 1997. KAERI has also focused on the development of processes suitable for reducing the volume of spent nuclear fuel and the recycling of valuable fissile material. One of the most promising technologies investigated by KAERI is the pyro-processing of spent nuclear fuel followed by the geological disposal of the generated high level waste (HLW). Since 2007, KAERI has been running a research programme focusing on the recycling of spent nuclear fuel, as well as studies aimed at the development of a relevant geological disposal system able to accept the resulting HLW. The core aims of the KAERI study were to characterize the geological media, design a repository system and assess the overall safety of the disposal system. The development of pyro-processing technology is ongoing and has not yet been demonstrated at the commercial level. Thus, the government of the Republic of Korea requested an assessment of the technical feasibility of this technology. The assessment also included the appraisal of a disposal solution for waste generated by pyro-processing. With regard to the latter, KAERI requested that the IAEA review the status of the disposal project within the Waste Management Assessment and Technical Review Programme (WATRP). Peer reviews are increasingly being acknowledged as an important element in building broader stakeholder confidence in the safety and viability of related facilities. This report presents the consensus view of the international group of experts convened by the IAEA to perform the review

Preliminary conceptual design of a geological disposal system for high-level wastes from the pyroprocessing of PWR spent fuels

Energy Technology Data Exchange (ETDEWEB)

Choi, Heui-Joo, E-mail: hjchoi@kaeri.re.kr [Korea Atomic Energy Research Institute, 1045 Daeduk-Daero, Yuseong, Daejon 305-353 (Korea, Republic of); Lee, Minsoo; Lee, Jong Youl [Korea Atomic Energy Research Institute, 1045 Daeduk-Daero, Yuseong, Daejon 305-353 (Korea, Republic of)

2011-08-15

Highlights: > A geological disposal system consists of disposal overpacks, a buffer, and a deposition hole or a disposal tunnel for high-level wastes from a pyroprocessing of PWR spent fuels is proposed. The amount and characteristics of high-level wastes are analyzed based on the material balance of pyroprocessing. > Four kinds of deposition methods, two horizontal and two vertical, are proposed. Thermal design is carried out with ABAQUS program. The spacing between the disposal modules is determined for the peak temperature in buffer not to exceed 100 deg. C. > The effect of the double-layered buffer is compared with the traditional single-layered buffer in terms of disposal density. Also, the effect of cooling time (aging) is illustrated. > All the thermal calculations are represented by comparing the disposal area of PWR spent fuels with the same cooling time. - Abstract: The inventories of spent fuels are linearly dependent on the production of electricity generated by nuclear energy. Pyroprocessing of PWR spent fuels is one of promising technologies which can reduce the volume of spent fuels remarkably. The properties of high-level wastes from the pyroprocessing are totally different from those of spent fuels. A geological disposal system is proposed for the high-level wastes from pyroprocessing of spent fuels. The amount and characteristics of high-level wastes are analyzed based on the material balance of pyroprocessing. Around 665 kg of monazite ceramic wastes are expected from the pyroprocessing of 10 MtU of PWR spent fuels. Decay heat from monazite ceramic wastes is calculated using the ORIGEN-ARP program. Disposal modules consisting of storage cans, overpacks, and a deposition hole or a disposal tunnel are proposed. Four kinds of deposition methods are proposed. Thermal design is carried out with ABAQUS program and geological data obtained from the KAERI Underground Research Tunnel. Through the thermal analysis, the spacing between the disposal modules

Technology development for safeguards

Energy Technology Data Exchange (ETDEWEB)

Kim, Ho Dong; Kang, H. Y.; Song, D. Y. [and others

2005-04-01

The objective of this project are to establish the safeguards technology of the nuclear proliferation resistance to the facilities which handle with high radioactivity nuclear materials like the spent fuel, to provide the foundation of the technical independency for the establishment of the effective management of domestic spent fuels, and to construct the base of the early introduction of the key technology relating to the back-end nuclear fuel cycle through the development of the safeguards technology of the DFDF of the nuclear non-proliferation. The essential safeguards technologies of the facility such as the measurement and account of nuclear materials and the C/S technology were carried out in this stage (2002-2004). The principal results of this research are the development of error reduction technology of the NDA equipment and a new NDA system for the holdup measurement of process materials, the development of the intelligent surveillance system based on the COM, the evaluation of the safeguardability of the Pyroprocessing facility which is the core process of the nuclear fuel cycle, the derivation of the research and development items which are necessary to satisfy the safeguards criteria of IAEA, and the presentation of the direction of the technology development relating to the future safeguards of Korea. This project is the representative research project in the field of the Korea's safeguards. The safeguards technology and equipment developed while accomplishing this project can be applied to other nuclear fuel cycle facilities as well as DFDF and will be contributed to increase the international confidence in the development of the nuclear fuel cycle facility of Korea and its nuclear transparency.

A Preliminary Shielding Study on the Integrated Operation Verification System in the Head-End Hot-Cell of the Pyro-processing

Energy Technology Data Exchange (ETDEWEB)

Kim, Jinhwam; Kim, Yewon; Park, Se-Hwan; Ahn, Seong-Kyu; Cho, Gyuseong [KAIST, Daejeon (Korea, Republic of)

2016-10-15

Nuclear power accounts for more than 30 percent of power production in Korea. Its significance has annually been increased. Disposal spent fuel containing uranium, transuranic elements, and fission products is unavoidable byproduct of nuclear power production. it is recognized that finding appropriate sites for interim storage of disposal spent fuel is not easy because isolated sites should be required. Pyro-processing technology, Pyro-processing should be operated under high radiation environment in hot-cell structures. Because of this reason, all workers should be unauthorized to access inside the hot-cell areas under any circumstances except for acceptable dose verification and a normal operation should be remotely manipulated. For the reliable normal operation of pyroprocessing, it is noted that an evaluation of the space dose distribution in the hot-cell environments is necessary in advance in order to determine which technologies or instruments can be utilized on or near the process as the Integrated Operation Verification System (IOVS) is measured. Not like the electroreduction and electro-refining hot-cells, the head-end hot-cell equips Camera Radiation Detector (CRD) in which plutonium is securely measured and monitored for the safeguard of the pyro-processing. Results have been obtained using F2 surface tally in order to observe the magnitude of the gamma-ray and neutron flux which pass through the surface of the process cell. Furthermore, T-mesh tally has also been used to obtain the space dose distribution in the headend hot-cell. The hot-cell was divided into 7,668 cells in which each dimension was 1 x 1 x 1m for the T-mesh tally. To determine the position of the CRD and the surveillance camera, divergent approaches were required. Because the purpose of the CRD which contains a gamma-ray detector and a neutron detector is to identify the material composition as the process proceeds, the position in which detectable flux is exposed is required, whereas

Analysis on the Present Status of Conceptually Designed Pyroprocessing Facilities for Determining a Reference Pyroprocessing Facility

International Nuclear Information System (INIS)

Shin, Hee Sung; Ahn, Seong Kyu; Song, Dae Yong; Lee, Tae Hoon; Kim, Ho Dong; Seo, Ji Sun; Im, Hye In; Jang, Je Nam

2009-12-01

In this report, pyro processing facility concepts suggested by US, Japan, and Republic of Korea have been summarized and analyzed, and the determination principles were established to determine a reference pyro processing facility concept. Three proposals for a reference pyro processing facility concept were suggested based on these principles. The 1st proposal is based on the GEN-IV PR/PP model except the metal fuel fabrication process. It may be possible to later add the metal fuel fabrication process, UO2 recovery process of Japan, and continuous electrorefining process invented in Republic of Korea to be the generic model including all pyroprocessing facility concepts in the world. The 2nd proposal is based on INL and ANL model which is simple for the most part and has basic essential processes. The 3rd proposal is determined to be the ESPF of KAERI, which is almost identical with that of the 2nd proposal except in regards to utilization of an input accountability tank and continuous electrorefining process and the 3rd proposal is planned to be realized in 7 years. After the review of the IAEA and discussions at 3rd Working Group Meeting held in IAEA headquarters, the 3rd proposal has been determined as the final version of a reference pyroprocessing facility concept

Analysis of Unit Process Cost for an Engineering-Scale Pyroprocess Facility Using a Process Costing Method in Korea

Directory of Open Access Journals (Sweden)

Sungki Kim

2015-08-01

Full Text Available Pyroprocessing, which is a dry recycling method, converts spent nuclear fuel into U (Uranium/TRU (TRansUranium metal ingots in a high-temperature molten salt phase. This paper provides the unit process cost of a pyroprocess facility that can process up to 10 tons of pyroprocessing product per year by utilizing the process costing method. Toward this end, the pyroprocess was classified into four kinds of unit processes: pretreatment, electrochemical reduction, electrorefining and electrowinning. The unit process cost was calculated by classifying the cost consumed at each process into raw material and conversion costs. The unit process costs of the pretreatment, electrochemical reduction, electrorefining and electrowinning were calculated as 195 US$/kgU-TRU, 310 US$/kgU-TRU, 215 US$/kgU-TRU and 231 US$/kgU-TRU, respectively. Finally the total pyroprocess cost was calculated as 951 US$/kgU-TRU. In addition, the cost driver for the raw material cost was identified as the cost for Li3PO4, needed for the LiCl-KCl purification process, and platinum as an anode electrode in the electrochemical reduction process.

Development of DUPIC safeguards technology

International Nuclear Information System (INIS)

Kim, H. D.; Kang, H. Y.; Ko, W. I.

2002-05-01

DUPIC safeguards R and D in the second phase has focused on the development of nuclear material measurement system and its operation and verification, the development of nuclear material control and accounting system, and the development of remote and unmanned containment/surveillance system. Of them, the nuclear material measurement system was authenticated from IAEA and officially used for IAEA and domestic safeguards activities in DFDF. It was also verified that the system could be used for quality control of DUPIC process. It is recognised that the diagnostic software using neural network and remote and unmanned containment/surveillance system developed here could be key technologies to go into remote and near-real time monitoring system. The result of this project will eventually contribute to similar nuclear fuel cycles like MOX and pyroprocessing facility as well as the effective implementation of DUPIC safeguards. In addition, it will be helpful to enhance international confidence build-up in the peaceful use of spent fuel material

A Probabilistic Consideration on Nuclide Releases from a Pyro-processed Waste Repository

Energy Technology Data Exchange (ETDEWEB)

Lee, Youn Myoung; Jeong, Jong Tae [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2012-05-15

Very recently, a GoldSim template program, GSTSPA, for a safety assessment of a conceptual hybrid-typed repository system, called 'A-KRS,' in which two kinds of pyroprocessed radioactive wastes, low-level metal wastes and ceramic high-level wastes that arise from the pyroprocessing of PWR nuclear spent fuels, has been developed and is to be disposed of by 'separate disposal' strategies. The A-KRS is considered to be constructed at two different depths in geological media: at a 200m depth, at which a possible human intrusion is considered to be limited after closure, for the pyroprocessed metal wastes with lower or no decay heat producing nuclides, and at a 500m depth, believed to be the reducing condition for nuclides with a rather higher radioactivity and heat generation rate. This program is ready for a probabilistic total system performance assessment (TSPA) which is able to evaluate nuclide release from the repository and farther transport into the geosphere and biosphere under various normal, disruptive natural and manmade events, and scenarios that can occur after a failure of a waste package and canister with associated uncertainty. To quantify the nuclide release and transport through the various possible pathways in the near- and far-fields of the A-KRS repository system under a normal groundwater flow scenario, some illustrative evaluations have been made through this study. Even though all parameter values associated with the A-KRS were assumed for the time being, the illustrative results should be informative since the evaluation of such releases is very important not only in view of the safety assessment of the repository, but also for design feedback of its performance

A Probabilistic Consideration on Nuclide Releases from a Pyro-processed Waste Repository

International Nuclear Information System (INIS)

Lee, Youn Myoung; Jeong, Jong Tae

2012-01-01

Very recently, a GoldSim template program, GSTSPA, for a safety assessment of a conceptual hybrid-typed repository system, called 'A-KRS,' in which two kinds of pyroprocessed radioactive wastes, low-level metal wastes and ceramic high-level wastes that arise from the pyroprocessing of PWR nuclear spent fuels, has been developed and is to be disposed of by 'separate disposal' strategies. The A-KRS is considered to be constructed at two different depths in geological media: at a 200m depth, at which a possible human intrusion is considered to be limited after closure, for the pyroprocessed metal wastes with lower or no decay heat producing nuclides, and at a 500m depth, believed to be the reducing condition for nuclides with a rather higher radioactivity and heat generation rate. This program is ready for a probabilistic total system performance assessment (TSPA) which is able to evaluate nuclide release from the repository and farther transport into the geosphere and biosphere under various normal, disruptive natural and manmade events, and scenarios that can occur after a failure of a waste package and canister with associated uncertainty. To quantify the nuclide release and transport through the various possible pathways in the near- and far-fields of the A-KRS repository system under a normal groundwater flow scenario, some illustrative evaluations have been made through this study. Even though all parameter values associated with the A-KRS were assumed for the time being, the illustrative results should be informative since the evaluation of such releases is very important not only in view of the safety assessment of the repository, but also for design feedback of its performance

Influence of Groundwater Flow Rate on Nuclide Releases from Pyro-processed Waste Repository

International Nuclear Information System (INIS)

Lee, Youn Myoung; Jeong, Jong Tae

2011-01-01

Since the early 2000s several template programs for the safety assessment of a high-level radioactive waste repository as well as a low- and intermediate level radioactive waste repository systems have been developed by utilizing GoldSim and AMBER at KAERI. Very recently, another template program for a conceptual hybrid-typed repository system, called 'A-KRS' in which two kinds of pyroprocessed radioactive wastes, low-level metal wastes and ceramic high-level wastes that arise from pyroprocessing of PWR nuclear spent fuels has been developed and are to be disposed of by separate disposal strategies. The A-KRS is considered to be constructed at two different depths in geological media: 200m depth, at which a possible human intrusion is considered to be limited after closure, for the pyroprocessed metal wastes with lower or no decay heat producing nuclides, and 500m depth, believed to be in the reducing condition for nuclides with a rather higher radioactivity and heat generation rate. This program is ready for total system performance assessment which is able to evaluate nuclide release from the repository and farther transport into the geosphere and biosphere under various normal, disruptive natural and manmade events, and scenarios that can occur after a failure of waste package and canister. To quantify a nuclide release and transport through the possible various pathways especially in the near-fields of the A-KRS repository system, some illustrative evaluations have been made through the study. Even though all parameter values associated with the A-KRS were assumed for the time being, the illustrative results should be informative since the evaluation of such releases is very important not only in view of the safety assessment of the repository, but also for design feedback of its performance

Projected Salt Waste Production from a Commercial Pyroprocessing Facility

Directory of Open Access Journals (Sweden)

Michael F. Simpson

2013-01-01

Full Text Available Pyroprocessing of used nuclear fuel inevitably produces salt waste from electrorefining and/or oxide reduction unit operations. Various process design characteristics can affect the actual mass of such waste produced. This paper examines both oxide and metal fuel treatment, estimates the amount of salt waste generated, and assesses potential benefit of process options to mitigate the generation of salt waste. For reference purposes, a facility is considered in which 100 MT/year of fuel is processed. Salt waste estimates range from 8 to 20 MT/year from considering numerous scenarios. It appears that some benefit may be derived from advanced processes for separating fission products from molten salt waste, but the degree of improvement is limited. Waste form production is also considered but appears to be economically unfavorable. Direct disposal of salt into a salt basin type repository is found to be the most promising with respect to minimizing the impact of waste generation on the economic feasibility and sustainability of pyroprocessing.

Estimation of the Waste Mass from a Pyro-Process of Spent Nuclear Fuel

Energy Technology Data Exchange (ETDEWEB)

Lee, Min Soo; Choi, Jong Won; Choi, Heui Joo (and others)

2008-04-15

Pyro-Process is now developing to retrieve reusable uranium and TRU, and to reduce the volume of high level waste from a nuclear power plant. In this situation, it is strongly required for the estimation of expected masses and their physical properties of the wastes. In this report, the amount of wastes and their physical properties are presupposed through some assumptions in regard to 10MTHM of Oxide Fuel with 4.5wt% U-235, 45,000 MWD/MTU, and 5yrs cooling. The produced wastes can be divided into three categories such as metal, CWF(Ceramic Waste Form), and VWF(Vitrified Waste Form). The 42 nuclrides in a spent nuclear fuel are distributed into the waste categories on the their physical and thermodynamic properties when they exist in metal, oxide, or chloride forms. The treated atomic groups are Uranium, TRU, Noble metal, Rare earth, Alkali metal, Halogens, and others. The mass of each waste is estimated by the distribution results. The off-gas waste is included into a CWF. The heat generations by the wastes in this Pyro-Process are calculated using a ORIGEN-ARP program. It is possible to estimate the amounts of wastes and their heat generation rates in this Pyro-Process analysis. These information are very helpful to design a waste container and its quantity also can be determined. The number of container and its heat generation rate will be key factor for the construction of interim storage facilities including a underground disposal site.

Technology Development of Safeguards

Energy Technology Data Exchange (ETDEWEB)

Kim, Ho Dong; Kang, H. Y.; Ko, W. I. (and others)

2007-04-15

The objective of this project is to perform R and D on the essential technologies in nuclear material measurement and surveillance and verification system, and to improve the state of being transparent on the nuclear material management of DUPIC Fuel Development Facility (DFDF) through the evaluation of safeguard ability on non-proliferation fuel cycle and nuclear proliferation resistance. Nuclear material position scan system for the reduction of measurement error was developed for the spatial distribution search of spent fuel in DUPIC facility. Web-based realtime remote monitoring system was designed and constructed for satisfying the IAEA's performance criteria of continuous monitoring, and also developed a software for the function of remote control and message. And diversion paths in a proliferation resistant pyroprocess for SFR were analyzed and its protecting system against the diversion paths were suggested for enhancing proliferation resistance of advanced nuclear fuel cycle. These results could be used for planning the further R and D items in the area of safeguards. Those R and D results mentioned above would be helpful for increasing Korean nuclear transparency in the future.

Modeling of oxide reduction in repeated-batch pyroprocessing

International Nuclear Information System (INIS)

Lee, Hyo Jik; Im, Hun Suk; Park, Geun Il

2016-01-01

Highlights: • Pyroprocessing is a complicated batch-type operation. • Discrete event system modeling was used to create an integrated operation model. • Simulation showed that could be accomplished. • The dynamic material flow helps us understand the process operation. • We showed that complex material flow could be simulated in terms of mass balance. - Abstract: Pyroprocessing is a complicated batch-type operation, involving a highly complex material flow logic with a huge number of unit processes. Discrete event system modeling was used to create an integrated operation model for which simulation showed that dynamic material flow could be accomplished to provide considerable insight into the process operation. In the model simulation, the amount of material transported upstream and downstream in the process satisfies a mass balance equation while considering the hold-up incurred by every batch operation. This study also simulated, in detail, an oxide reduction group process embracing electrolytic reduction, cathode processing, and salt purification. Based on the default operation scenario, it showed that complex material flows could be precisely simulated in terms of the mass balance. Specifically, the amount of high-heat elements remaining in the molten salt bath is analyzed to evaluate the operation scenario.

A Study on Data Base for the Pyroprocessing Material Flow and MUF Uncertainty Simulation

International Nuclear Information System (INIS)

Sitompul, Yos Panagaman; Shin, Heesung; Han, Boyoung; Kim, Hodong

2011-01-01

The data base for the pyroprocessing material flow and MUF uncertainty simulation has been implemented well. There is no error in the data base processing and it is relatively fast by using OLEDB and MySQL. The important issue is the data base size. In OLEDB the data base size is limited to 2 Gb. To reduce the data base size, we give an option for users to filter the input nuclides based on their masses and activities. A simulation program called PYMUS has been developed to study the pyroprocessing material flow and MUF. In the program, there is a data base system that controls the data processing in the simulation. The data base system consists of input data base, data processing, and output data base. The data base system has been designed in such a way to be efficient. One example is using the OLEDB and MySQL. The data base system is explained in detail in this paper. The result shows that the data base system works well in the simulation

Review of GIF PR and PP Evaluation Case Study for Application to Pyroprocessing

Energy Technology Data Exchange (ETDEWEB)

Kim, H. M.; Ahn, S. K.; Kwon, E. H.; Kim, H. D. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-05-15

This paper has summarized and reviewed the ESFR case study, as it relates to the application of the evaluation methods to pyroprocessing facilities as well as the sodium fast reactor fuel cycle in the future as a self-assessment study. The GIF PR and PP evaluation methodology and the case study both addressed physical protection, but this paper focuses only on proliferation resistance. It does not consider physical protection. The Generation IV International Forum (GIF) emphasizes proliferation resistance and physical protection (PR and PP) as one of the main aspects to be considered regarding future nuclear energy systems (NESs). As such, the PR and PP Working Group developed an evaluation methodology and applied it to the Example Sodium Fast Reactor (ESFR) as a case study. This paper has summarized and reviewed the ESFR case study, as it relates to the application of the evaluation methods to pyroprocessing facilities as well as the sodium fast reactor fuel cycle in the future as a self-assessment study. The GIF PR and PP evaluation methodology and the case study both addressed physical protection, but this paper focuses only on proliferation resistance. It does not consider physical protection.

Review of GIF PR and PP Evaluation Case Study for Application to Pyroprocessing

International Nuclear Information System (INIS)

Kim, H. M.; Ahn, S. K.; Kwon, E. H.; Kim, H. D.

2014-01-01

This paper has summarized and reviewed the ESFR case study, as it relates to the application of the evaluation methods to pyroprocessing facilities as well as the sodium fast reactor fuel cycle in the future as a self-assessment study. The GIF PR and PP evaluation methodology and the case study both addressed physical protection, but this paper focuses only on proliferation resistance. It does not consider physical protection. The Generation IV International Forum (GIF) emphasizes proliferation resistance and physical protection (PR and PP) as one of the main aspects to be considered regarding future nuclear energy systems (NESs). As such, the PR and PP Working Group developed an evaluation methodology and applied it to the Example Sodium Fast Reactor (ESFR) as a case study. This paper has summarized and reviewed the ESFR case study, as it relates to the application of the evaluation methods to pyroprocessing facilities as well as the sodium fast reactor fuel cycle in the future as a self-assessment study. The GIF PR and PP evaluation methodology and the case study both addressed physical protection, but this paper focuses only on proliferation resistance. It does not consider physical protection

Dry refabrication technology development of spent nuclear fuel

International Nuclear Information System (INIS)

Park, Geun Il; Lee, J. W.; Song, K. C.

2012-04-01

Key technologies highly applicable to the development of advanced nuclear fuel cycle for the spent fuel recycling were developed using spent fuel and simulated spent fuel (SIMFUEL). In the frame work of dry process oxide products fabrication and the property characteristics of dry process products, hot cell experimental data for decladding, powdering and oxide product fabrication from low and high burnup spent fuel have been produced, basic technology for fabrication of spent fuel standard material has been developed, and remotely modulated welding equipment has been designed and fabricated. Also, fabrication technology of simulated dry process products was established and property models were developed based on reproducible property measurement data. In the development of head-end technology for dry refabrication of spent nuclear fuel and key technologies for volume reduction of head-end process waste which are essential in back-end fuel cycle field including pyro-processing, advanced head-end unit process technology development includes the establishment of experimental conditions for synthesis of porous fuel particles using a granulating furnace and for preparation of UO2 pellets, and fabrication and performance demonstration of engineering scale equipment for off-gas treatment of semi-volatile nuclides, and development of phosphate ceramic technology for immobilization of used filters. Radioactivation characterization and treatment equipment design of metal wastes from pretreatment process was conducted, and preliminary experiments of chlorination/electrorefining techniques for the treatment of hull wastes were performed. Based on the verification of the key technologies for head-end process via the hot-cell tests using spent nuclear fuel, pre-conceptual design for the head-end equipments was performed

Dry refabrication technology development of spent nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Park, Geun Il; Lee, J. W.; Song, K. C.; and others

2012-04-15

Key technologies highly applicable to the development of advanced nuclear fuel cycle for the spent fuel recycling were developed using spent fuel and simulated spent fuel (SIMFUEL). In the frame work of dry process oxide products fabrication and the property characteristics of dry process products, hot cell experimental data for decladding, powdering and oxide product fabrication from low and high burnup spent fuel have been produced, basic technology for fabrication of spent fuel standard material has been developed, and remotely modulated welding equipment has been designed and fabricated. Also, fabrication technology of simulated dry process products was established and property models were developed based on reproducible property measurement data. In the development of head-end technology for dry refabrication of spent nuclear fuel and key technologies for volume reduction of head-end process waste which are essential in back-end fuel cycle field including pyro-processing, advanced head-end unit process technology development includes the establishment of experimental conditions for synthesis of porous fuel particles using a granulating furnace and for preparation of UO2 pellets, and fabrication and performance demonstration of engineering scale equipment for off-gas treatment of semi-volatile nuclides, and development of phosphate ceramic technology for immobilization of used filters. Radioactivation characterization and treatment equipment design of metal wastes from pretreatment process was conducted, and preliminary experiments of chlorination/electrorefining techniques for the treatment of hull wastes were performed. Based on the verification of the key technologies for head-end process via the hot-cell tests using spent nuclear fuel, pre-conceptual design for the head-end equipments was performed.

Use of curium neutron flux from head-end pyroprocessing subsystems for the High Reliability Safeguards methodology

Energy Technology Data Exchange (ETDEWEB)

Borrelli, R.A., E-mail: r.angelo.borrelli@gmail.com

2014-10-01

The deployment of nuclear energy systems (NESs) is expanding around the world. Nations are investing in NESs as a means to establish energy independence, grow national economies, and address climate change. Transitioning to the advanced nuclear fuel cycle can meet growing energy demands and ensure resource sustainability. However, nuclear facilities in all phases of the advanced fuel cycle must be ‘safeguardable,’ where safety, safeguards, and security are integrated into a practical design strategy. To this end, the High Reliability Safeguards (HRS) approach is a continually developing safeguardability methodology that applies intrinsic design features and employs a risk-informed approach for systems assessment that is safeguards-motivated. Currently, a commercial pyroprocessing facility is used as the example system. This paper presents a modeling study that investigates the neutron flux associated with processed materials. The intent of these studies is to determine if the neutron flux will affect facility design, and subsequently, safeguardability. The results presented in this paper are for the head-end subsystems in a pyroprocessing facility. The collective results from these studies will then be used to further develop the HRS methodology.

Development of IFR pyroprocessing technology

International Nuclear Information System (INIS)

Laidler, J.J.; Battles, J.E.; Miller, W.E.; Gay, E.C.

1993-01-01

A metallic fuel alloy, nominally U-20Pu-10Zr, is the key element of the IFR fuel cycle. This metallic fuel permits the use of an innovative reprocessing method, known as ''pyoprocessing,'' featuring fused-salt electrorefining of the spent fuel. Electrorefining separates the actinide elements from fission products, without producing a separate stream of plutonium. The fuel product is contaminated with the higher actinides and with a minor amount of rare earth fission products, making it self-protecting and thus diversion-resistant while still perfectly suitable as a fuel material in the fast spectrum of the IFR core

Development of High Temperature Transport System for Molten Salt

International Nuclear Information System (INIS)

Lee, S. H.; Lee, H. S.; Kim, J. G.

2011-01-01

Pyroprocessing technology is one of the the most promising technologies for the advanced fuel cycle with favorable economic potential and intrinsic proliferation-resistance. The electrorefining process, one of main processes which is composed of pyroprocess to recover the useful elements from spent fuel, is under development at the Korea Atomic Energy Research Institute as a sub process of the pyrochemical treatment of spent PWR fuel. High-temperature molten salt transport technologies are required because a molten salt should be transported from the electrorefiner to electrowiner after the electrorefining process. Therefore, in pyrometallurgical processing, the development of high-temperature molten salt transport technologies is a crucial prerequisite. However, there have been a few transport studies on high-temperature molten salt. In this study, an apparatus for suction transport experiments was designed and constructed for the development of high temperature transport technology for molten salt, and the performance test of the apparatus was performed. And also, predissolution test of the salt was carried out using the reactor with furnace in experimental apparatus

Development of advanced treatment technologies of radio-aqueous waste by an environmental friendly decomposition

Energy Technology Data Exchange (ETDEWEB)

Kim, Kwang Wook; Lee, E. H.; Moon, J. K. and others

2006-01-15

This project was aimed at the technology developments of electrode fabrication, electrolytic reactor design and fabrication, electrolytic processes and the analyses of electroytic reaction mechanisms, which were essential elements for the development of electrolytic systems to decompose or teat environmentally- friendly the several salts contained in waste solutions which are to be generated in the fields of nuclear/non-nuclear industries. Major research items carried our in this project were as follows; - Development of technologies to choose and fabricate the anodes and cathodes for the treatments of waste solutions containing nitrogen compounds and organics. - Development of a membrane electrolyzer stacked by mono-polar unit cells with independent series flow path of electrolytes - Development of an electrolyzer with a self-pH adjustment and an electrolytic process for ammonia decomposition by using the electrolyzer - Analysis of electrolytic reaction mechanism of ammonia - Development of an ion exchange membrane electrolyzer with only one discharge of pH-controlled electrolyte solution - Development of electrolytic dechlorination technology for the treatment of chloride molten salt waste salt from pyroprocess. - Development of technologies for treatment of high concentration nitric acid and recovery of waste organic solvent.

Stability of yttria-stabilized zirconia during pyroprocessing tests

Energy Technology Data Exchange (ETDEWEB)

Choi, Eun-Young, E-mail: eychoi@kaeri.re.kr; Lee, Jeong; Lee, Sung-Jai; Kim, Sung-Wook; Jeon, Sang-Chae; Cho, Soo Haeng; Oh, Seung Chul; Jeon, Min Ku; Lee, Sang Kwon; Kang, Hyun Woo; Hur, Jin-Mok

2016-07-15

In this study, the feasibility of yttria-stabilized zirconia (YSZ) was investigated for use as a ceramic material, which can be commonly used for both electrolytic reduction and electrorefining. First, the stability of YSZ in salts for electrolytic reduction and electrorefining was examined. Then, its stability was demonstrated by a series of pyroprocessing tests, such as electrolytic reduction, LiCl distillation, electrorefining, and LiCl−KCl distillation, using a single stainless steel wire mesh basket containing fuel and YSZ. A single basket was used by its transportation from one test to subsequent tests without the requirements for unloading.

Burnup Measurement of Spent Fuel Assembly by CZT-based Gamma-ray Spectroscopy for Input Nuclear Material Accountancy of Pyroprocessing

International Nuclear Information System (INIS)

Seo, Hee; Oh, Jong-Myeong; Shin, Hee-Sung; Kim, Ho-Dong; Lee, Seung-Kyu; Park, Se-Hwan

2013-06-01

Input nuclear material accountancy is crucial for a pyroprocessing facility safeguards. Until a direct Pu measurement technique is established, an indirect method based on code calculations with burnup measurement and neutron counting for 244 Cm could be a practical option. Burnup can be determined by destructive analysis (DA) for final dispositive accuracy or by nondestructive assay (NDA) for near-real time accountancy. In the present study, an underwater burnup measurement system based on gamma-ray spectroscopy with the CZT detector was developed and tested on a spent fuel assembly. Burnup was determined according to the 134 Cs/ 137 Cs activity ratio with efficiency correction by Geant4 Monte Carlo simulations. The activity ratio as a function of burnup was obtained by ORIGEN calculations. The measured burnup error was 8.6%, which was within the measurement uncertainty. It is expected that the underwater burnup measurement system could fulfill an important role as a means of near-real time accountancy at a future pyroprocessing facility. (authors)

Performance evaluation of PRIDE UNDA system with feed material of pyroprocessing

Energy Technology Data Exchange (ETDEWEB)

An, Su Jung; Seo, Hee; Lee, Chae Hun; Ahn, Seong Kyu; Park, Se Hwan; Ku, Jeong Hoe [Nonproliferation System Research Division, KAERI, Daejeon (Korea, Republic of)

2016-12-15

The PRIDE (PyRoprocessing Integrated inactive DEmonstration facility) provides unique opportunities not only to develop process technologies but also to test various types of safeguards equipment for nuclear material accountancy (NMA), containment and surveillance (C/S), as well as process monitoring. In this regard, we developed a UNDA (Unified Non-Destructive Assay) system by incorporating three different non-destructive assay (NDA) techniques, i.e., neutron, gamma-ray, and mass measurements, for the testing of NMA of PRIDE. One of the main advantages of the UNDA is reducing measurement time and systematic error related to sample handling and placement by integrating the NDA techniques. The {sup 235}U mass can be determined from the {sup 238}U mass and uranium enrichment ({sup 235}U/{sup 238}U). The {sup 238}U mass is acquired from total neutron counting using neutron detection module of UNDA, with the information on the spontaneous fission neutron yield of {sup 238}U and neutron detection efficiency of the system. Total sample mass is measured by using the mass balance. In our previous studies, the UNDA was developed and characterized for a calibration source. In this study, the UNDA was installed in PRIDE facility, and the performance of the UNDA was evaluated with feed material of oxide reduction process. In this study, the performance of the UNDA was evaluated with feed material of oxide reduction process: UO2 porous pellets made of DU. The neutron net count rate was obtained as functions of 238U mass. The measured net count rate fitted by linear regression showed good linearity. In addition, the 238U mass of unknown source was determined using the information of the detection efficiency and count rate obtained from the UNDA.

Current status on development of P and T in Korea

International Nuclear Information System (INIS)

Eung Ho, Kim

2007-01-01

According to the long-term plan for nuclear technology development in Korea, KAERI is conducting an R and D project on transmutation with the objective of key technology development in the areas of partitioning based on a pyro-process and transmutation system. The R and D activities for the partitioning and transmutation of long-lived radionuclides are introduced in this work. The study on partitioning is focused on the development of a pyro-process. The major experimental items of the partitioning include an electroreduction for a reduction of oxide fuel into metal, an electrorefining for a uranium recovery from the obtained metal, an electrowinning for an investigation of the thermodynamic behaviour of actinide mixture on a liquid metal cathode and a molten salt waste treatment such as the removal of fission products from waste salts. In particular, KAERI is presently developing a new method to, in a consecutive manner, remove fission products resulting from pyro-processing units in order to minimise the amount of waste salt to be disposed of. As for the transmutation system, we have studied, up to now, an accelerator-driven transmutation system, which is a subcritical reactor connected to a proton accelerator. Details on the design and the transmutation performance of the ADS system being studied at KAERI are presented, and an experimental scale facility related to the corrosion loop is introduced. In addition, a development plan of Gen IV-SFR being recently considered as a burner for transmutation of long-lived nuclides is discussed in this work. (author)

Assessment of Process Monitoring Techniques for Pyro processing Safeguards

Energy Technology Data Exchange (ETDEWEB)

Jung, Y. E.; Kim, C. M.; Yim, M. S. [KAIST, Daejeon (Korea, Republic of)

2016-05-15

PM technologies can be used to inspect normal/off-normal operation with various data obtained from facility operations in real time to meet safeguards objectives. To support the use of PM technologies for the purpose of pyroprocessing safeguards, this study aims at identifying technologies that could be useful for PM purposes and evaluating their applicability to a pyroprocessing facility. This paper describes the development of the assessment criteria to evaluate the practicality of candidate technologies for PM based on a variety of requirements and considerations. By using the developed assessment criteria, application of technologies in the oxide reduction process was assessed as a test case example. Research is necessary to validate the criteria according to the needs of each unit process, perhaps based on expert elicitation and/or international collaboration with other expert organization(s). These advanced assessment criteria will serve a useful guideline for selecting appropriate candidate PM technologies for pyroprocessing safeguards. Based on the results of using these evaluation criteria, the optimum technologies can be successfully selected for use at a large scale pyroprocessing facility.

High-level Waste Long-term management technology development

International Nuclear Information System (INIS)

Choi, Jong Won; Kang, C. H.; Ko, Y. K.

2012-02-01

The purpose of this project is to develop a long-term management system(A-KRS) which deals with spent fuels from domestic nuclear power stations, HLW from advanced fuel cycle and other wastes that are not admitted to LILW disposal site. Also, this project demonstrate the feasibility and reliability of the key technologies applied in the A-KRS by evaluating them under in-situ condition such as underground research laboratory and provide important information to establish the safety assessment and long-term management plan. To develop the technologies for the high level radioactive wastes disposal, demonstrate their reliability under in-situ condition and establish safety assessment of disposal system, The major objects of this project are the following: Ο An advanced disposal system including waste containers for HLW from advanced fuel cycle and pyroprocess has been developed. Ο Quantitative assessment tools for long-term safety and performance assessment of a radwaste disposal system has been developed. Ο Hydrological and geochemical investigation and interpretation methods has been developed to evaluate deep geological environments. Ο The THMC characteristics of the engineered barrier system and near-field has been evaluated by in-situ experiments. Ο The migration and retardation of radionuclides and colloid materials in a deep geological environment has been investigated. The results from this project will provide important information to show HLW disposal plan safe and reliable. The knowledge from this project can also contribute to environmental conservation by applying them to the field of oil and gas industries to store their wastes safe

Progress and status of the integral fast reactor (IFR) development program

International Nuclear Information System (INIS)

Chang, Y.I.

1992-01-01

This paper discusses the Integral Fast Reactor (IFR) development program, in which the entire reactor system - reactor, fuel cycle, and waste process is being developed and optimized at the same time as a single integral entity. Detailed discussions on the present status of the IFR technology development activities in the areas of fuels, pyroprocessing, safety, core design, and fuel cycle demonstration are also presented

Preliminary Study on the High Temperature Transport System for Molten Salt

International Nuclear Information System (INIS)

Lee, S. H.; Lee, H. S.; Kim, J. G.

2012-01-01

Pyroprocessing technology is one of the the most promising technologies for the advanced fuel cycle with favorable economic potential and intrinsic proliferation-resistance. The electrorefining process, one of main processes is compos- ed of pyroprocess to recover the useful elements from spent fuel, is under development at the Korea Atomic Energy Research Institute as a sub process of the pyrochemical treatment of spent PWR fuel. High-temperature molten salt transport technologies are required because a molten salt should be transported from the electrorefiner to electrowiner after the electrorefining process. Therefore, in pyroprocessing technology, the development of high-temperature transport technologies for molten salt is a crucial prerequisite. However, there have been a few transport studies on high-temperature molten salt. In this study, an apparatus for suction transport experiments was designed and constructed for the development of high temperature molten salt transport technology. Suction transport experiments were performed using LiC-KCl eutectic salt

Development of metallic uranium recovery technology from uranium oxide by Li reduction and electrorefining

International Nuclear Information System (INIS)

Tokiwai, Moriyasu; Kawabe, Akihiro; Yuda, Ryouichi; Usami, Tsuyoshi; Fujita, Reiko; Nakamura, Hitoshi; Yahata, Hidetsugu

2002-01-01

The purpose of the study is to develop technology for pre-treatment of oxide fuel reprocessing through pyroprocess. In the pre-treatment process, it is necessary to reduce actinide oxide to metallic form. This paper outlines some experimental results of uranium oxide reduction and recovery of refined metallic uranium in electrorefining. Both uranium oxide granules and pellets were used for the experiments. Uranium oxide granules was completely reduced by lithium in several hours at 650degC. Reduced uranium pellets by about 70% provided a simulation of partial reduction for the process flow design. Almost all adherent residues of Li and Li 2 O were successfully washed out with fresh LiCl salt. During electrorefining, metallic uranium deposited on the iron cathode as expected. The recovery efficiencies of metallic uranium from reduced uranium oxide granules and from pellets were about 90% and 50%, respectively. The mass balance data provided the technical bases of Li reduction and refining process flow for design. (author)

Research and development of pyro-reprocessing and its world status

International Nuclear Information System (INIS)

Inoue, Tadashi

2005-01-01

The next generation fuel cycle requires a strong resistance of nuclear proliferation and lightening the environmental burden as well as safety and economic advantage. The pyro-reprocessing technology satisfies such kinds of requirements. Central Research Institute of Electric Power Industry, CRIEPI, has been involving the development of metal fuel cycle integrated pyro-reprocessing with metal-electrorefining and metal fuel fast reactor since 1986. The study on pyro-processing technology of spent MOX fuel from LWR has been also started. Based on the fast that metal-electrorefining does not produce pure plutonium but transuranium elements, irradiation experiment of metal fuel with minor actinides is carried out by use of Phenix Fast Reactor in France. This article reports an overview of pyro-reprocessing and the present status of its research and development. The R and D activity proceeds to the process verification by use of genuine material and the development of engineering model of the process after finishing the verification of elemental technology. Irradiation study of metal fuel will be started by use of JOYO Fast Reactor as well as Phenix Fast Reactor. The target at 2015 is to finish the irradiation programs by both reactors and to demonstrate the pyro-process flow and related technologies by use of irradiated material. After finishing this stage, we expect to be technically feasible to design a pyro-process facility with a throughput of several tones of spent fuels. While R and D on pyro-technology has started initially in the U.S. and followed by CRIEPI, the several activities, currently, are followed in European and Asian nations. The engineering installation of electrochemical reduction successfully achieved by uranium test with 20 kg/batch and the construction of hot cell for handling a 20 kg/batch spent fuel finished in the Korean Atomic Energy Research Institute, KAERI. China has started R and D on metal fuel fast reactor and pyro-reprocessing as a

A analysis of molten salt separation system for nuclear wastes transmutation

Energy Technology Data Exchange (ETDEWEB)

Hwang, In Soon; Park, Byung Gi [Seoul National University, Seoul (Korea, Republic of); Kim, Kwang Bum; Kwon, Ou Sung [Yonsei University, Seoul (Korea, Republic of)

1997-07-01

Typical molten salt separation is ANL-IFR pyroprocessing and ORNL-MSRE pyroprocessing. IFR pyroprocessing is based on Chloride chemistry and electrorefining. MSRE pyroprocessing is base on fluoride chemistry and reductive extraction. Major technologies of molten salt separation are electrorefining, electrowining, reductive extraction, and oxide reduction. Common characteristics of this technologies is to utilize reduction-oxidation phenomena in molten salt. Electrorefining process is modeled on the basis of diffusion layer theory and Butler-Volmor relation. This model is numerically solved by LSODA package. To acquire the technology of electrorefining process, 3-electrode electrochemical cell is developed where electrolyte is 500 degree C LiCl-KCl eutectic molten salt, working electrodes are Ni and Au, and reference electrode is Ag/AgCl. We have investigated the stable potential range using cyclic voltammogram of Ni electrode. We have measured steady state polarization curve of Ni electrode. Then corrosion potential of Ni electrode is -0.38V{sub Ag/AgCl} and corrosion current is 1.23 x 10{sup -4} A/cm{sup 2}. 12 refs., 6 tabs., 24 figs. (author)

Progress and status of the Integral Fast Reactor (IFR) development program

International Nuclear Information System (INIS)

Chang, Yoon I.

1992-01-01

In the Integral Fast Reactor (IFR) development program, the entire reactor system -- reactor, fuel cycle, and waste process is being developed and optimized at the same time as a single integral entity. The ALMR reactor plant design is being developed by an industrial team headed by General Electric and is presented in a companion paper. Detailed discussions on the present status of the IFR technology development activities in the areas of fuels, pyroprocessing, safety, core design, and fuel cycle demonstration are presented in the other two companion papers that follows this

Progress and status of the Integral Fast Reactor (IFR) development program

Energy Technology Data Exchange (ETDEWEB)

Chang, Yoon I.

1992-04-01

In the Integral Fast Reactor (IFR) development program, the entire reactor system -- reactor, fuel cycle, and waste process is being developed and optimized at the same time as a single integral entity. The ALMR reactor plant design is being developed by an industrial team headed by General Electric and is presented in a companion paper. Detailed discussions on the present status of the IFR technology development activities in the areas of fuels, pyroprocessing, safety, core design, and fuel cycle demonstration are presented in the other two companion papers that follows this.

Progress and status of the Integral Fast Reactor (IFR) development program

Energy Technology Data Exchange (ETDEWEB)

Chang, Yoon I.

1992-01-01

In the Integral Fast Reactor (IFR) development program, the entire reactor system -- reactor, fuel cycle, and waste process is being developed and optimized at the same time as a single integral entity. The ALMR reactor plant design is being developed by an industrial team headed by General Electric and is presented in a companion paper. Detailed discussions on the present status of the IFR technology development activities in the areas of fuels, pyroprocessing, safety, core design, and fuel cycle demonstration are presented in the other two companion papers that follows this.

Actinide recycle potential in the IFR [Integral Fast Reactor

International Nuclear Information System (INIS)

Chang, Y.I.

1989-01-01

Rising concern about the greenhouse effect reinforces the need to reexamine the question of a next-generation reactor concept that can contribute significantly toward substitution for fossil-based energy generation. Even with only the nuclear capacity on-line today, world-wide reasonably assured uranium resources would last for only about 50 years. If nuclear is to make a significant contribution, breeding is a fundamental requirement. Uranium resources can then be extended by two orders of magnitude, making nuclear essentially a renewable energy source. The key technical elements of the IFR concept are metallic fuel and fuel cycle technology based on pyroprocessing. Pyroprocessing is radically different from the conventional PUREX reprocessing developed for the LWR oxide fuel. Chemical feasibility of pyroprocessing has been demonstrated. The next major step in the IFR development program will be the full-scale pyroprocessing demonstration to be carried out in conjunction with EBR-II. IFR fuel cycle closure based on pyroprocessing can also have a dramatic impact on the waste management options, and in particular on the actinide recycling. 6 figs

A Strategic Study for the enhancement of nuclear research and development transparency through the extra-contribution to IAEA

International Nuclear Information System (INIS)

Lee, Byung Wook; Lee, H. M.; Ko, H. S.; Ryu, J. S.; Kim, H. R.; Kim, H. D.; Song, K. S.

2008-12-01

To devote efforts to international nuclear technology cooperation, the research team of this study surveyed the IAEA activities to find ones suitable for extra-contributions by Korea. Based on the survey, the team made inputs to the IAEA MSSP (Member State Support Program). After consultation with the IAEA secretariat, it was decided to hold a technical meeting for the Asia Pacific region in Korea during 2009. The Korean government contributed 93,000 dollars to the IAEA for this purpose. Also a workshop on the safeguards for a pyroprocessing was held in Korea during 2008. The financial contribution to the IAEA technical meeting is one of the efforts from Korea to increase its understanding on the transparency in domestic nuclear activities. The contribution to the workshop on the safeguards of a pyroprocessing is expected to be a seed for implementing a future domestic nuclear R and D plan. Also such a contribution will enhance its transparency in developing domestic nuclear fuel cycle technology. Further efforts are necessary to lead to safeguards technology development by contributing to future MSSPs on advanced fuel cycle facilities. It is recommended to continue these financial contributions including in-kind contributions to the IAEA by elaborating the accumulated experiences on nuclear transparency

The Integral Fast Reactor: A practical approach to waste management

International Nuclear Information System (INIS)

Laidler, J.J.

1993-01-01

This report discusses development of the method for pyroprocessing of spent fuel from the Integral Fast Reactor (or Advanced Liquid Metal Reactor). The technology demonstration phase, in which recycle will be demonstrated with irradiated fuel from the EBR-II reactor has been reached. Methods for recovering actinides from spent LWR fuel are at an earlier stage of development but appear to be technically feasible at this time, and a large-scale demonstration of this process has begun. The utilization of fully compatible processes for recycling valuable spent fuel materials promises to provide substantial economic incentives for future applications of the pyroprocessing technology

Nuclear Criticality Calculation for Determining the Bach Size in a Pyroprocessing Facility

International Nuclear Information System (INIS)

Ko, Won Il; Lee, Ho Hee; Chang, Hong Rae; Song, Dae Yong; Kwon, Eun Ha; Jung, Chang Jun; Yoon, Suk Kyun

2009-01-01

The criticality analysis in a pyroprocessing facility is very important element for the R and D and the facility design in terms of the determination of batch size of the sub-processes as well as facility safety. Particularly, the determining the batch size is essential at the beginning stage of the R and D. In this report, the criticality analysis was carried out for the subprocesses such as voloxidation, electrolytic reduction, electrorefining and electrowinning process in order to estimate the maximum batch size of each process by using Monte Carlo code (MCNP4/C2). On the whole, the criticality problem could not give a big effect on the batch sizes in the voloxidation, electrolytic reduction and electrorefining. However, it was resulted that permissible amount of nuclear material to prevent the criticality accident in the electrowinning process was about 10kgHM

Nuclear Criticality Calculation for Determining the Bach Size in a Pyroprocessing Facility

Energy Technology Data Exchange (ETDEWEB)

Ko, Won Il; Lee, Ho Hee; Chang, Hong Rae; Song, Dae Yong; Kwon, Eun Ha; Jung, Chang Jun; Yoon, Suk Kyun [KAERI, Daejeon (Korea, Republic of)

2009-01-15

The criticality analysis in a pyroprocessing facility is very important element for the R and D and the facility design in terms of the determination of batch size of the sub-processes as well as facility safety. Particularly, the determining the batch size is essential at the beginning stage of the R and D. In this report, the criticality analysis was carried out for the subprocesses such as voloxidation, electrolytic reduction, electrorefining and electrowinning process in order to estimate the maximum batch size of each process by using Monte Carlo code (MCNP4/C2). On the whole, the criticality problem could not give a big effect on the batch sizes in the voloxidation, electrolytic reduction and electrorefining. However, it was resulted that permissible amount of nuclear material to prevent the criticality accident in the electrowinning process was about 10kgHM

A Study on the Fabrication of Uranium-Cadmium Alloy and its Distillation Behavior

International Nuclear Information System (INIS)

Kim, Ji Yong; Ahn, Do Hee; Kim, Kwang Rag; Paek, Seung Woo; Kim, Si Hyung

2010-01-01

The pyrometallurgical nuclear fuel recycle process, called pyroprocessing, has been known as a promising nuclear fuel recycling technology. Pyroprocessing technology is crucial to advanced nuclear systems due to increased nuclear proliferation resistance and economic efficiency. The basic concept of pyroprocessing is group actinide recovery, which enhances the nuclear proliferation resistance significantly. One of the key steps in pyroprocessing is 'electrowinning' which recovers group actinides with lanthanide from the spent nuclear fuels. In this study, a vertical cadmium distiller was manufactured. The evaporation rate of pure cadmium in vertical cadmium distiller varied from 12.3 to 40.8 g/cm 2 /h within a temperature range of 773 ∼ 923 K and pressure below 0.01 torr. Uranium - cadmium alloy was fabricated by electrolysis using liquid cadmium cathode in a high purity argon atmosphere glove box. The distillation behavior of pure cadmium and cadmium in uranium - cadmium alloy was investigated. The distillation behavior of cadmium from this study could be used to develop an actinide recovery process from a liquid cadmium cathode in a cadmium distiller

A Study on the Fabrication of Uranium-Cadmium Alloy and its Distillation Behavior

Energy Technology Data Exchange (ETDEWEB)

Kim, Ji Yong [University of Science and Technology, Daejeon (Korea, Republic of); Ahn, Do Hee; Kim, Kwang Rag; Paek, Seung Woo; Kim, Si Hyung [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2010-12-15

The pyrometallurgical nuclear fuel recycle process, called pyroprocessing, has been known as a promising nuclear fuel recycling technology. Pyroprocessing technology is crucial to advanced nuclear systems due to increased nuclear proliferation resistance and economic efficiency. The basic concept of pyroprocessing is group actinide recovery, which enhances the nuclear proliferation resistance significantly. One of the key steps in pyroprocessing is 'electrowinning' which recovers group actinides with lanthanide from the spent nuclear fuels. In this study, a vertical cadmium distiller was manufactured. The evaporation rate of pure cadmium in vertical cadmium distiller varied from 12.3 to 40.8 g/cm{sup 2}/h within a temperature range of 773 {approx} 923 K and pressure below 0.01 torr. Uranium - cadmium alloy was fabricated by electrolysis using liquid cadmium cathode in a high purity argon atmosphere glove box. The distillation behavior of pure cadmium and cadmium in uranium - cadmium alloy was investigated. The distillation behavior of cadmium from this study could be used to develop an actinide recovery process from a liquid cadmium cathode in a cadmium distiller.

Performance assessment modeling of high level nuclear wasteforms from the pyroprocess fuel cycle

International Nuclear Information System (INIS)

Nutt, W.M.; Hill, R.N.; Bullen, D.B.

1995-01-01

Several performance assessment (PA) analyses have been completed to estimate the release to the accessible environment of radionuclides from spent light water reactor (LWR) fuel emplaced in the proposed Yucca Mountain repository. Probabilistic methods were utilized based on the complexity of the repository system. Recent investigations have been conducted to identify the merits of a pyroprocess fuel cycle. This cycle utilizes high temperature molten salts and metals to partially separate actinides and fission products. In a closed liquid metal reactor (LMR) fuel cycle, this allows recycling of nearly all of the actinides. In a once-through cycle, this isolates the actinides for storage into a wasteform which can be specifically tailored for their retention. With appropriate front-end treatment, this Process can also be used to treat LWR spent fuel

A Glass-Ceramic Waste Forms for the Immobilization of Rare Earth Oxides from the Pyroprocessing Waste salt

International Nuclear Information System (INIS)

Ahn, Byung-Gil; Park, Hwan-Seo; Kim, Hwan-Young; Kim, In-Tae

2008-01-01

The fission product of rare earth (RE) oxide wastes are generates during the pyroprocess . Borosilicate glass or some ceramic materials such as monazite, apatite or sodium zirconium phosphate (NZP) have been a prospective host matrix through lots of experimental results. Silicate glasses have long been the preferred waste form for the immobilization of HLW. In immobilization of the RE oxides, the developed process on an industrial scale involves their incorporation into a glass matrix, by melting under 1200 ∼ 1300 .deg. C. Instead of the melting process, glass powder sintering is lower temperature (∼ 900 .deg. C) required for the process which implies less demanding conditions for the equipment and a less evaporation of volatile radionuclides. This study reports the behaviors, direct vitrification of RE oxides with glass frit, glass powder sintering of REceramic with glass frit, formation of RE-apatite (or REmonazite) ceramic according to reaction temperature, and the leach resistance of the solidified waste forms

Evaluation of Spent Fuel Recycling Scenario using Pyro-SFR related System

International Nuclear Information System (INIS)

Lee, Yong Kyo; Kim, Sang Ji; Kim, Young Jin

2014-01-01

It is needed to validate whether the recycling scenario connecting pyro-processing and sodium-cooled fast reactor(SFR) is promising or not. The latest technologies of pyro-processing are applied to SFR and the recycling scenario is evaluated through the SFR's performance analysis. The analyzed SFR is KALIMER-600 TRU burner which purpose is to transmute transuranics (TRU). National policy of CANDU SF management has not been decided yet. However, the stored quantity of this SF is large enough not to be neglected. So this study includes additionally the recycling scenario of CANDU SF. Adopting the mass ratio of TRU and RE recovered in pyro-processing is 4 to 1 on PWR SF recycling, the sodium void reactivity is higher than design basis of metal fuel. So the current pyro-processing technology is may not be acceptable. If pyro-processing technology of CANDU SF is assumed to be the same as PWR's case, CANDU recycling scenario is acceptable. Transmutation performance is worse than PWR's, while the sodium void reactivity is within design limit

Optimization of hybrid-type instrumentation for Pu accountancy of U/TRU ingot in pyroprocessing.

Science.gov (United States)

Seo, Hee; Won, Byung-Hee; Ahn, Seong-Kyu; Lee, Seung Kyu; Park, Se-Hwan; Park, Geun-Il; Menlove, Spencer H

2016-02-01

One of the final products of pyroprocessing for spent nuclear fuel recycling is a U/TRU ingot consisting of rare earth (RE), uranium (U), and transuranic (TRU) elements. The amounts of nuclear materials in a U/TRU ingot must be measured as precisely as possible in order to secure the safeguardability of a pyroprocessing facility, as it contains the most amount of Pu among spent nuclear fuels. In this paper, we propose a new nuclear material accountancy method for measurement of Pu mass in a U/TRU ingot. This is a hybrid system combining two techniques, based on measurement of neutrons from both (1) fast- and (2) thermal-neutron-induced fission events. In technique #1, the change in the average neutron energy is a signature that is determined using the so-called ring ratio method, according to which two detector rings are positioned close to and far from the sample, respectively, to measure the increase of the average neutron energy due to the increased number of fast-neutron-induced fission events and, in turn, the Pu mass in the ingot. We call this technique, fast-neutron energy multiplication (FNEM). In technique #2, which is well known as Passive Neutron Albedo Reactivity (PNAR), a neutron population's changes resulting from thermal-neutron-induced fission events due to the presence or absence of a cadmium (Cd) liner in the sample's cavity wall, and reflected in the Cd ratio, is the signature that is measured. In the present study, it was considered that the use of a hybrid, FNEM×PNAR technique would significantly enhance the signature of a Pu mass. Therefore, the performance of such a system was investigated for different detector parameters in order to determine the optimal geometry. The performance was additionally evaluated by MCNP6 Monte Carlo simulations for different U/TRU compositions reflecting different burnups (BU), initial enrichments (IE), and cooling times (CT) to estimate its performance in real situations. Copyright © 2015 Elsevier Ltd. All

Chemical stability of conductive ceramic anodes in LiCl–Li{sub 2}O molten salt for electrolytic reduction in pyroprocessing

Energy Technology Data Exchange (ETDEWEB)

Kim, Sung Wook; Kang, Hyun Woo; Jeon, Min Ku; Lee, Sang Kwon; Choi, Eun Young; Park, Woo Shin; Hong, Sun Seok; Oh, Seung Chul; Hur, Jin Mok [Nuclear Fuel Cycle Process Development Group, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-08-15

Conductive ceramics are being developed to replace current Pt anodes in the electrolytic reduction of spent oxide fuels in pyroprocessing. While several conductive ceramics have shown promising electrochemical properties in small-scale experiments, their long-term stabilities have not yet been investigated. In this study, the chemical stability of conductive La{sub 0.33}Sr{sub 0.67}MnO{sub 3} in LiCl–Li{sub 2}O molten salt at 650°C was investigated to examine its feasibility as an anode material. Dissolution of Sr at the anode surface led to structural collapse, thereby indicating that the lifetime of the La{sub 0.33}Sr{sub 0.67}MnO{sub 3} anode is limited. The dissolution rate of Sr is likely to be influenced by the local environment around Sr in the perovskite framework.

Development of Spent Fuel Examination Technology

Energy Technology Data Exchange (ETDEWEB)

Kim, Ho Dong; Park, K. J.; Shin, H. S. (and others)

2007-04-15

For the official operation of ACPF Facility Attachment based on facility declared DIQ was issued by IAEA and officialized upon ROK government approval. This procedure gives an essential ground to negotiate Joint Determination between governments of ROK and US. For ACPF process material accountability a neutron coincidence counting system was developed and calibrated with Cf-252 source. Its performance test demonstrated that over-all counting efficiency was about 21% with random error, 1.5% against calibration source, which found to be satisfactory to the expected design specification. A calibration curve derived by MCNP code with relationship between ASNC doublet counts vs. neutron activity of Cm-244 showed calibration constant to be 2.78x10E5 counts/s.g which would be used for initial ACP hot operation test. Nuclear material transportation and temporary storage system was established for active demonstration of advanced spent fuel management process line and would be directly applied to the effective management of wastes arising from active demonstration and would later contribute as a base data to development of inter hot-cell movement system in pyro-processing line. In addition, an optimal spent fuel for the ACP demonstration was selected and a computer code was developed as a tool to estimate the expected source term at each key measurement point of ACP.

Development of Spent Fuel Examination Technology

International Nuclear Information System (INIS)

Kim, Ho Dong; Park, K. J.; Shin, H. S.

2007-04-01

For the official operation of ACPF Facility Attachment based on facility declared DIQ was issued by IAEA and officialized upon ROK government approval. This procedure gives an essential ground to negotiate Joint Determination between governments of ROK and US. For ACPF process material accountability a neutron coincidence counting system was developed and calibrated with Cf-252 source. Its performance test demonstrated that over-all counting efficiency was about 21% with random error, 1.5% against calibration source, which found to be satisfactory to the expected design specification. A calibration curve derived by MCNP code with relationship between ASNC doublet counts vs. neutron activity of Cm-244 showed calibration constant to be 2.78x10E5 counts/s.g which would be used for initial ACP hot operation test. Nuclear material transportation and temporary storage system was established for active demonstration of advanced spent fuel management process line and would be directly applied to the effective management of wastes arising from active demonstration and would later contribute as a base data to development of inter hot-cell movement system in pyro-processing line. In addition, an optimal spent fuel for the ACP demonstration was selected and a computer code was developed as a tool to estimate the expected source term at each key measurement point of ACP

Development of Head-end Pyrochemical Reduction Process for Advanced Oxide Fuels

International Nuclear Information System (INIS)

Park, B. H.; Seo, C. S.; Hur, J. M.; Jeong, S. M.; Hong, S. S.; Choi, I. K.; Choung, W. M.; Kwon, K. C.; Lee, I. W.

2008-12-01

The development of an electrolytic reduction technology for spent fuels in the form of oxide is of essence to introduce LWR SFs to a pyroprocessing. In this research, the technology was investigated to scale a reactor up, the electrochemical behaviors of FPs were studied to understand the process and a reaction rate data by using U 3 O 8 was obtained with a bench scale reactor. In a scale of 20 kgHM/batch reactor, U 3 O 8 and Simfuel were successfully reduced into metals. Electrochemical characteristics of LiBr, LiI and Li 2 Se were measured in a bench scale reactor and an electrolytic reduction cell was modeled by a computational tool

Study on Oxidation or Reduction Behavior of Cs-Te-O System with Gas Conditions of Voloxidation Process

International Nuclear Information System (INIS)

Park, Byung Heung

2013-01-01

Pyroprocessing has been developed for the purpose of resolving the current spent nuclear fuel management issue and enhancing the recycle of valuable resources. Pyroprocessing has been developed with the dry technologies which are performed under high temperature conditions excluding any aqueous processes. Pyro-processes which are based on the electrochemical principles require pretreatment processes and a voloxidation process is considered as a pretreatment step for an electrolytic reduction process. Various kinds of gas conditions are applicable to the voloxidation process and the understanding of Cs behavior during the process is of importance for the analyses of waste characteristics and heat load on the overall pyroprocessing. In this study, the changes of chemical compounds with the gas conditions were calculated by analyzing gas-solid reaction behavior based on the chemical equilibria on a Cs-Te-O system. Cs 2 TeO 3 and Cs 2 TeO 4 were selected after a Tpp diagram analysis and it was confirmed that they are relatively stable under oxidizing atmospheres while it was shown that Cs and Te would be removed by volatilization under reducing atmosphere at a high temperature. This work provided basic data for predicting Cs behavior during the voloxidation process at which compounds are chemically distributed as the first stage in the pyroprocessing and it is expected that the results would be used for setting up material balances and related purposes

Integral Fast Reactor Program annual progress report, FY 1994

International Nuclear Information System (INIS)

Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, J.J.

1994-12-01

This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1994. Technical accomplishments are presented in the following areas of the IFR technology development activities: metal fuel performance; pyroprocess development; safety experiments and analyses; core design development; fuel cycle demonstration; and LMR technology R ampersand D

Integral Fast Reactor Program. Annual progress report, FY 1992

Energy Technology Data Exchange (ETDEWEB)

Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

1993-06-01

This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1992. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R&D.

Development of Computational Models for Pyrochemical Electrorefiners of Nuclear Waste Transmutation Systems

International Nuclear Information System (INIS)

Kim, K. R.; Lee, H. S.; Hwang, I. S.

2010-12-01

The objective of this project is to develop multi-dimensional computational models in order to improve the operation of uranium electrorefiners currently used in pyroprocessing technology. These 2-D (US) and 3-D (ROK) mathematical models are based on the fundamental physical and chemical properties of the electrorefiner processes. The validated models by compiled and evaluated experimental data could provide better information for developing advanced electrorefiners for uranium recovery. The research results in this period are as follows: - Successfully assessed a common computational platform for the modeling work and identify spatial characterization requirements. - Successfully developed a 3-D electro-fluid dynamic electrorefiner model. - Successfully validated and benchmarked the two multi-dimensional models with compiled experimental data sets

Development of Head-end Pyrochemical Reduction Process for Advanced Oxide Fuels

Energy Technology Data Exchange (ETDEWEB)

Park, B. H.; Seo, C. S.; Hur, J. M.; Jeong, S. M.; Hong, S. S.; Choi, I. K.; Choung, W. M.; Kwon, K. C.; Lee, I. W. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-12-15

The development of an electrolytic reduction technology for spent fuels in the form of oxide is of essence to introduce LWR SFs to a pyroprocessing. In this research, the technology was investigated to scale a reactor up, the electrochemical behaviors of FPs were studied to understand the process and a reaction rate data by using U{sub 3}O{sub 8} was obtained with a bench scale reactor. In a scale of 20 kgHM/batch reactor, U{sub 3}O{sub 8} and Simfuel were successfully reduced into metals. Electrochemical characteristics of LiBr, LiI and Li{sub 2}Se were measured in a bench scale reactor and an electrolytic reduction cell was modeled by a computational tool.

A Preliminary Study on the Reuse of the Recovered Uranium from the Spent CANDU Fuel Using Pyroprocessing

International Nuclear Information System (INIS)

Park, C. J.; Na, S. H.; Yang, J. H.; Kang, K. H.; Lee, J. W.

2009-01-01

During the pyroprocessing, most of the uranium is gathered in metallic form around a solid cathode during an electro-refining process, which is composed of about 94 weight percent of the spent fuel. In the previous study, a feasibility study has been done to reuse the recovered uranium for the CANDU reactor fuel following the traditional DUPIC (direct use of spent pressurized water reactor fuel into CANDU reactor) fuel fabrication process. However, the weight percent of U-235 in the recovered uranium is about 1 wt% and it is sufficiently re-utilized in a heavy water reactor which uses a natural uranium fuel. The reuse of recovered uranium will bring not only a huge economic profit and saving of uranium resources but also an alleviation of the burden on the management and the disposal of the spent fuel. The research on recycling of recovered uranium was carried out 10 years ago and most of the recovered uranium was assumed to be imported from abroad at that time. The preliminary results showed there is the sufficient possibility to recycle recovered uranium in terms of a reactor's characteristics as well as the fuel performance. However, the spent CANDU fuel is another issue in the storage and disposal problem. At present, most countries are considering that the spent CANDU fuel is disposed directly due to the low enrichment (∼0.5 wt%) of the discharge fissile content and lots of fission products. If mixing the spent CANDU fuel and the spent PWR fuel, the estimated uranium fissile enrichment will be about 0.6 wt% ∼ 1.0 wt% depending on the mixing ratio, which is sufficiently reusable in a CANDU reactor. Therefore, this paper deals with a feasibility study on the recovered uranium of the mixed spent fuel from the pyroprocessing. With the various mixing ratios between the PWR spent fuel and the CANDU spent fuel, a reactor characteristics including the safety parameters of the CANDU reactor was evaluated

Integral Fast Reactor Program annual progress report, FY 1991

International Nuclear Information System (INIS)

1992-06-01

This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1991. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R ampersand D

Integral Fast Reactor Program

International Nuclear Information System (INIS)

Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

1993-06-01

This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1992. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R ampersand D

Integral Fast Reactor Program. Annual progress report, FY 1993

Energy Technology Data Exchange (ETDEWEB)

Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

1994-10-01

This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1993. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R and D.

Integral Fast Reactor Program. Annual progress report, FY 1993

International Nuclear Information System (INIS)

Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

1994-10-01

This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1993. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R and D

Study on the System Requirements and Structures of Mailbox Declaration System for Reference Pyroprocessing Facility in the ROK

International Nuclear Information System (INIS)

Jeon, Jong Kyu

2011-01-01

The mailbox declaration system applied for the implementation of Safeguards at the Reference Pyroprocessing Facility (REPF) plays important role to support the declared information provided from Near-Real Time Accountancy (NRTA) and provides reference data to confirm the measurement results generated from the Unattended Monitoring System (UMS) for the purposes of verification and real-time monitoring of the movements and changes of nuclear materials (NM) at the processes in the REPF. In order to install and operate the mailbox declaration system at the REPF, this study focused on the operation, security, transmission of confidential information, procedure for transmission of mailbox declaration system as system requirements, and structure of mailbox declaration system to review the declared information through the mailbox by the national authority and to transmit the revised information to the IAEA

Fabrication, characterization and simulation of 4H-SiC Schottky diode alpha particle detectors for pyroprocessing actinide monitoring

Science.gov (United States)

Garcia, Timothy Richard

Pyroprocessing is a method of using high-temperature molten salts and electric fields to separate and collect fuel isotopes of used nuclear fuel. It has been has been tested in the U.S. at Idaho National Laboratory as a key step in closing the nuclear fuel cycle. One technical problem with the pyroprocessing method is a lack of knowledge regarding the actinide concentrations in the salt bath during operation, since on-line techniques for measuring these concentrations are not presently available. 4H-SiC Schottky diode detectors can potentially fulfill this need. Such detectors would operate in contact with the molten salt, and measure concentrations via alpha-particle spectroscopy. This work seeks to fabricate and characterize 4H-SiC Schottky diode detectors at high temperature, model the alpha particle spectrum expected in a molten salt, and model the operation of the detectors to confirm the physics of operation is as expected. In this work, 4H-SiC Schottky diode detectors were fabricated at OSU Nanotech West. After fabrication, these detectors were characterized using both I-V curves and Am-241 alpha-particle energy spectra. All measurements were made as a function of temperature, from room temperature up to 500°C. The average energy required to create an electron-hole pair was observed to decrease with an increase of temperature, due to a decrease of both the 4H-SiC bandgap and non-linear energy loss terms. Furthermore, the FWHM of the spectra was observed to be dependent on the leakage current at a certain temperature, and not dependent on the temperature itself. Secondly, the alpha particle energy spectrum in the pyroprocessing environment was modeled using SRIM. The molten salt was modeled in 3 different geometries, with or without a protective cover material on top of the detector. Due to the loss of alpha-particle energy in the molten salt itself, a high-energy alpha emitter may completely cover the spectrum from a lower-energy alpha emitter. Each of the

Considerations Regarding ROK Spent Nuclear Fuel Management Options

International Nuclear Information System (INIS)

Braun, Chaim; Forrest, Robert

2013-01-01

In this paper we discuss spent fuel management options in the Republic of Korea (ROK) from two interrelated perspectives: Centralized dry cask storage and spent fuel pyroprocessing and burning in sodium fast reactors (SFRs). We argue that the ROK will run out of space for at-reactors spent fuel storage by about the year 2030 and will thus need to transition centralized dry cask storage. Pyroprocessing plant capacity, even if approved and successfully licensed and constructed by that time, will not suffice to handle all the spent fuel discharged annually. Hence centralized dry cask storage will be required even if the pyroprocessing option is successfully developed by 2030. Pyroprocessing is but an enabling technology on the path leading to fissile material recycling and burning in future SFRs. In this regard we discuss two SFR options under development in the U. S.: the Super Prism and the Travelling Wave Reactor (TWR). We note that the U. S. is further along in reactor development than the ROK. The ROK though has acquired more experience, recently in investigating fuel recycling options for SFRs. We thus call for two complementary joint R and D project to be conducted by U. S. and ROK scientists. One leading to the development of a demonstration centralized away-from-reactors spent fuel storage facility. The other involve further R and D on a combined SFR-fuel cycle complex based on the reactor and fuel cycle options discussed in the paper

Development of lead slowing down spectrometer for isotopic fissile assay

International Nuclear Information System (INIS)

Lee, Yong Deok; Park, Chang Je; Ahn, Sang Joon; Kim, Ho Dong

2014-01-01

A lead slowing down spectrometer (LSDS) is under development for analysis of isotopic fissile material contents in pyro-processed material, or spent fuel. Many current commercial fissile assay technologies have a limitation in accurate and direct assay of fissile content. However, LSDS is very sensitive in distinguishing fissile fission signals from each isotope. A neutron spectrum analysis was conducted in the spectrometer and the energy resolution was investigated from 0.1eV to 100keV. The spectrum was well shaped in the slowing down energy. The resolution was enough to obtain each fissile from 0.2eV to 1keV. The detector existence in the lead will disturb the source neutron spectrum. It causes a change in resolution and peak amplitude. The intense source neutron production was designed for ∼E12 n's/sec to overcome spent fuel background. The detection sensitivity of U238 and Th232 fission chamber was investigated. The first and second layer detectors increase detection efficiency. Thorium also has a threshold property to detect the fast fission neutrons from fissile fission. However, the detection of Th232 is about 76% of that of U238. A linear detection model was set up over the slowing down neutron energy to obtain each fissile material content. The isotopic fissile assay using LSDS is applicable for the optimum design of spent fuel storage to maximize burnup credit and quality assurance of the recycled nuclear material for safety and economics. LSDS technology will contribute to the transparency and credibility of pyro-process using spent fuel, as internationally demanded.

A Post Closure Safety Assessment for Radioactive Wastes from Advanced nuclear fuel Cycle

International Nuclear Information System (INIS)

Kang, Chul Hyung; Hwang, Yong Soo

2010-01-01

KAERI has developed the KIEP-21 (Korean, Innovative, Environmentally Friendly, and Proliferation Resistant System for the 21st Century). It is an advanced nuclear fuel cycle option with a pyro-process and a GEN-IV SFR. A pyro-process consists of two distinctive processes, an electrolytic reduction process and an electro-refining and winning process. When the pyro-process is applied, it generates five streams of wastes. To compare pyro-process advantage over the direct disposal of Spent Nuclear Fuel (SNF), the PWR SNF of the 45,000 MWD burn-up has been assumed. A safety assessment model for pyro-process wastes and representative results are presented in this report

Carbonate Looping for De-Carbonization of Cement Plants

DEFF Research Database (Denmark)

Pathi, Sharat Kumar; Andersen, Maria Friberg; Lin, Weigang

2011-01-01

Cement industry is one of the largest emitter of CO2 other than power generation plants, which includes the emissions from combustion of fuel and also from calcination of limestone for clinker production. In order to reduce CO2 emissions from the cement industry an effective an economically...... feasible technology is to be developed. The carbonate looping process is a promising technology, which is particularly suitable for the cement industry as limestone could be used for capture and release of CO2. Integration of carbonate looping process into cement pyroprocess has two advantages: 1...... integrated into cement pyro-process. The energy required for regeneration in the calciner increases with increase in average conversion of calcined limestone and energy that can be extracted from carbonator decreases with increasing average conversion. Further the influence of type of limestone...

Update on development of the IFR pyroprocess

International Nuclear Information System (INIS)

Burris, L.; Miller, W.E.; Gay, E.C.; Ackerman, J.P.; Tomczuk, Z.; Herceg, J.E.; Kann, W.J.

1988-01-01

A pyrochemical process is under development for recovering and recycling fuel discharged from the integral fast reactor (IFR). In the past year, two major changes have been made in this process. First, the halide slagging step previously used for concentrating plutonium bred in the blanket has been eliminated, not because it did not work but because the same purpose can be achieved by electrorefining. The current flow sheet is shown. Now, all of the necessary separations are achieved by electrorefining alone. Second, to make the electrorefining operations sufficiently flexible to provide the necessary separations while accommodating a range of feed compositions, two types of cathodes are employed. One is used for selective removal of uranium for recycle as blanket material, and the other is used for removal of a uranium-plutonium product for recycle as core material. Computer codes based on thermodynamic models have been developed to predict the fate of product elements (uranium and plutonium) and fission products. These show that high recovery of uranium and plutonium and adequate removal of fission products are achievable

Energy audit and conservation opportunities for pyroprocessing unit of a typical dry process cement plant

International Nuclear Information System (INIS)

Kabir, G.; Abubakar, A.I.; El-Nafaty, U.A.

2010-01-01

Cement production process has been highly energy and cost intensive. The cement plant requires 8784 h per year of the total operating hours to produce 640,809 tonnes of clinker. To achieve effective and efficient energy management scheme, thermal energy audit analysis was employed on the pyroprocessing unit of the cement plant. Fuel combustion generates the bulk of the thermal energy for the process, amounting to 95.48% (4164.02 kJ/kg cl ) of the total thermal energy input. Thermal efficiency of the unit stands at 41%, below 50-54% achieved in modern plants. The exhaust gases and kiln shell heat energy losses are in significant quantity, amounting to 27.9% and 11.97% of the total heat input respectively. To enhance the energy performance of the unit, heat losses conservation systems are considered. Waste heat recovery steam generator (WHRSG) and Secondary kiln shell were studied. Power and thermal energy savings of 42.88 MWh/year and 5.30 MW can be achieved respectively. Financial benefits for use of the conservation methods are substantial. Environmental benefit of 14.10% reduction in Greenhouse gases (GHG) emissions could be achieved.

Energy audit and conservation opportunities for pyroprocessing unit of a typical dry process cement plant

Energy Technology Data Exchange (ETDEWEB)

Kabir, G.; Abubakar, A.I.; El-Nafaty, U.A. [Chemical Engineering Programme, Abubakar Tafawa Balewa University, P. M. B. 0248, Bauchi (Nigeria)

2010-03-15

Cement production process has been highly energy and cost intensive. The cement plant requires 8784 h per year of the total operating hours to produce 640,809 tonnes of clinker. To achieve effective and efficient energy management scheme, thermal energy audit analysis was employed on the pyroprocessing unit of the cement plant. Fuel combustion generates the bulk of the thermal energy for the process, amounting to 95.48% (4164.02 kJ/kg{sub cl}) of the total thermal energy input. Thermal efficiency of the unit stands at 41%, below 50-54% achieved in modern plants. The exhaust gases and kiln shell heat energy losses are in significant quantity, amounting to 27.9% and 11.97% of the total heat input respectively. To enhance the energy performance of the unit, heat losses conservation systems are considered. Waste heat recovery steam generator (WHRSG) and Secondary kiln shell were studied. Power and thermal energy savings of 42.88 MWh/year and 5.30 MW can be achieved respectively. Financial benefits for use of the conservation methods are substantial. Environmental benefit of 14.10% reduction in Greenhouse gases (GHG) emissions could be achieved. (author)

Characterization of Delayed-Particle Emission Signatures for Pyroprocessing. Part 1: ABTR Fuel Assembly.

Energy Technology Data Exchange (ETDEWEB)

Durkee, Jr., Joe W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-06-19

A three-part study is conducted using the MCNP6 Monte Carlo radiation-transport code to calculate delayed-neutron (DN) and delayed-gamma (DG) emission signatures for nondestructive assay (NDA) metal-fuel pyroprocessing. In Part 1, MCNP6 is used to produce irradiation-induced used nuclear fuel (UNF) isotopic inventories for an Argonne National Laboratory (ANL) Advanced Burner Test Reactor (ABTR) preconceptual design fuel assembly (FA) model. The initial fuel inventory consists of uranium mixed with light-water-reactor transuranic (TRU) waste and 10 wt% zirconium (U-LWR-SFTRU-10%Zr). To facilitate understanding, parametric evaluation is done using models for 3% and 5% initial ²³⁵U a% enrichments, burnups of 5, 10, 15, 20, 30, …, 120 GWd/MTIHM, and 3-, 5-, 10-, 20-, and 30- year cooling times. Detailed delayed-particle radioisotope source terms for the irradiate FA are created using BAMF-DRT and SOURCES3A. Using simulation tallies, DG activity ratios (DGARs) are developed for ¹³⁴Cs/¹³⁷Cs ¹³⁴Cs/¹⁵⁴Eu, and ¹⁵⁴Eu/¹³⁷Cs markers as a function of (1) burnup and (2) actinide mass, including elemental uranium, neptunium, plutonium, americium, and curium. Spectral-integrated DN emission is also tallied. The study reveals a rich assortment of DGAR behavior as a function of DGAR type, enrichment, burnup, and cooling time. Similarly, DN emission plots show variation as a function of burnup and of actinide mass. Sensitivity of DGAR and DN signatures to initial ²³⁵U enrichment, burnup, and cooling time is evident. Comparisons of the ABTR radiation signatures and radiation signatures previously reported for a generic Westinghouse oxide-fuel assembly indicate that there are pronounced differences in the ABTR and Westinghouse oxide-fuel DN and DG signatures. These differences are largely attributable to the initial TRU inventory in the ABTR fuel. The actinide and nonactinide inventories for the

Progress and status of the integral fast reactor (IFR) fuel cycle development

International Nuclear Information System (INIS)

Till, C.E.; Chang, Y.I.

1993-01-01

The Integral Fast Reactor (IFR) fuel cycle holds promise for substantial improvements in economics, diversion-resistance, and waste management. This paper discusses technical features of the IFR fuel cycle, its technical progress, the development status, and the future plans and directions. The Integral Fast Reactor (IFR) fuel cycle, is based on the use of a metallic fuel alloy (U-Pu-Zr) that permits use of an innovative method for processing of spent fuel. This method, a combination of pyrometallurgical and electrochemical processes, has been termed pyroprocessing. It offers the advantages of a simple, compact processing system and limited volumes of stabilized high-level wastes. This translates to an economically viable system that is likely to receive favorable public response, particularly when combined with the other attributes of the Integral Fast Reactor. Substantial progress has been made in the development of the IFR pyroprocessing method. A comprehensive demonstration of the process will soon begin at the Argonne National Laboratory Idaho site, using spent fuel from the EBR-II reactor. An important advantage of the IFR is its ability to recycle fuel in the process of power generation, extending fuel resources by a considerable amount and assuring the continued viability of nuclear power stations by reducing dependence on external fuel supplies. Pyroprocessing is the means whereby the recycle process is accomplished. It can also be applied to the recovery of fuel constituents from spent fuel generated in the process of operation of conventional light water reactor power plants, offering the means to recover the valuable fuel resources remaining in that material

The Development of Pyro Human Resource Information System

International Nuclear Information System (INIS)

Jung, M. S.; Kim, S. K.; Ko, W. I.

2012-01-01

This paper aims to provide the current status of the development of a human resource information system. Establishing an expert information system helps readily provide the personal information of international and local pyroprocess experts who are currently conducting research at institutes. The information system offers a data processing environment in which users can easily access the necessary information online for a prompt search. Setting up this online networking enables us to easily obtain the personal information of pyro-experts, if necessary, and to provide the basic materials to seek an efficient system of technical cooperation. As pyro-technology presently falls under a high-tech field in the area of back-end fuel cycle, the research is under way at some advanced nuclear nations such as the United States, Korea, and Japan: therefore, the cooperation of experts from home and abroad is critical, helping gain maximum achievements through minimum investments and personnel. Since many efforts should be preceded to secure original technology in the field of fair technology and pyrosystem engineering, we can attain the research goal efficiently if other advanced nuclear nations have already obtained advanced technology, by efficiently realizing the goal through the benchmarking of the necessary technology. To form a cooperative system for such experts, we should know, above all, what research experts are conducting in certain fields at certain laboratories of certain countries

Safeguard monitoring of direct electrolytic reduction

Science.gov (United States)

Jurovitzki, Abraham L.

Nuclear power is regaining global prominence as a sustainable energy source as the world faces the consequences of depending on limited fossil based, CO2 emitting fuels. A key component to achieving this sustainability is to implement a closed nuclear fuel cycle. Without achieving this goal, a relatively small fraction of the energy value in nuclear fuel is actually utilized. This involves recycling of spent nuclear fuel (SNF)---separating fissile actinides from waste products and using them to fabricate fresh fuel. Pyroprocessing is a viable option being developed for this purpose with a host of benefits compared to other recycling options, such as PUREX. Notably, pyroprocessing is ill suited to separate pure plutonium from spent fuel and thus has non-proliferation benefits. Pyroprocessing involves high temperature electrochemical and chemical processing of SNF in a molten salt electrolyte. During this batch process, several intermediate and final streams are produced that contain radioactive material. While pyroprocessing is ineffective at separating pure plutonium, there are various process misuse scenarios that could result in diversion of impure plutonium into one or more of these streams. This is a proliferation risk that should be addressed with innovative safeguards technology. One approach to meeting this challenge is to develop real time monitoring techniques that can be implemented in the hot cells and coupled with the various unit operations involved with pyroprocessing. Current state of the art monitoring techniques involve external chemical assaying which requires sample removal from these unit operations. These methods do not meet International Atomic Energy Agency's (IAEA) timeliness requirements. In this work, a number of monitoring techniques were assessed for their viability as online monitoring tools. A hypothetical diversion scenario for the direct electrolytic reduction process was experimentally verified (using Nd2O3 as a surrogate for PuO2

NASA's Exploration Technology Development Program Energy Storage Project Battery Technology Development

Science.gov (United States)

Reid, Concha M.; Miller, Thomas B.; Mercer, Carolyn R.; Jankovsky, Amy L.

2010-01-01

Technical Interchange Meeting was held at Saft America s Research and Development facility in Cockeysville, Maryland on Sept 28th-29th, 2010. The meeting was attended by Saft, contractors who are developing battery component materials under contracts awarded through a NASA Research Announcement (NRA), and NASA. This briefing presents an overview of the components being developed by the contractor attendees for the NASA s High Energy (HE) and Ultra High Energy (UHE) cells. The transition of the advanced lithium-ion cell development project at NASA from the Exploration Technology Development Program Energy Storage Project to the Enabling Technology Development and Demonstration High Efficiency Space Power Systems Project, changes to deliverable hardware and schedule due to a reduced budget, and our roadmap to develop cells and provide periodic off-ramps for cell technology for demonstrations are discussed. This meeting gave the materials and cell developers the opportunity to discuss the intricacies of their materials and determine strategies to address any particulars of the technology.

Development and Optimization of Voltammetric Methods for Real Time Analysis of Electrorefiner Salt with High Concentrations of Actinides and Fission Products

Energy Technology Data Exchange (ETDEWEB)

Simpson, Michael F.; Phongikaroon, Supathorn; Zhang, Jinsuo

2018-03-30

This project addresses the problem of achieving accurate material control and accountability (MC&A) around pyroprocessing electrorefiner systems. Spent nuclear fuel pyroprocessing poses a unique challenge with respect to reprocessing technology in that the fuel is never fully dissolved in the process fluid. In this case, the process fluid is molten, anhydrous LiCl-KCl salt. Therefore, there is no traditional input accountability tank. However, electrorefiners (ER) accumulate very large quantities of fissile nuclear material (including plutonium) and should be well safeguarded in a commercial facility. Idaho National Laboratory (INL) currently operates a pyroprocessing facility for treatment of spent fuel from Experimental Breeder Reactor-II with two such ER systems. INL implements MC&A via a mass tracking model in combination with periodic sampling of the salt and other materials followed by destructive analysis. This approach is projected to be insufficient to meet international safeguards timeliness requirements. A real time or near real time monitoring method is, thus, direly needed to support commercialization of pyroprocessing. A variety of approaches to achieving real time monitoring for ER salt have been proposed and studied to date—including a potentiometric actinide sensor for concentration measurements, a double bubbler for salt depth and density measurements, and laser induced breakdown spectroscopy (LIBS) for concentration measurements. While each of these methods shows some promise, each also involves substantial technical complexity that may ultimately limit their implementation. Yet another alternative is voltammetry—a very simple method in theory that has previously been tested for this application to a limited extent. The equipment for a voltammetry system consists of off-the-shelf components (three electrodes and a potentiostat), which results in substantial benefits relative to cost and robustness. Based on prior knowledge of electrochemical

International Nuclear Energy Research Initiative Development of Computational Models for Pyrochemical Electrorefiners of Nuclear Waste Transmutation Systems

International Nuclear Information System (INIS)

Simpson, M.F.; Kim, K.-R.

2010-01-01

In support of closing the nuclear fuel cycle using non-aqueous separations technology, this project aims to develop computational models of electrorefiners based on fundamental chemical and physical processes. Spent driver fuel from Experimental Breeder Reactor-II (EBR-II) is currently being electrorefined in the Fuel Conditioning Facility (FCF) at Idaho National Laboratory (INL). And Korea Atomic Energy Research Institute (KAERI) is developing electrorefining technology for future application to spent fuel treatment and management in the Republic of Korea (ROK). Electrorefining is a critical component of pyroprocessing, a non-aqueous chemical process which separates spent fuel into four streams: (1) uranium metal, (2) U/TRU metal, (3) metallic high-level waste containing cladding hulls and noble metal fission products, and (4) ceramic high-level waste containing sodium and active metal fission products. Having rigorous yet flexible electrorefiner models will facilitate process optimization and assist in trouble-shooting as necessary. To attain such models, INL/UI has focused on approaches to develop a computationally-light and portable two-dimensional (2D) model, while KAERI/SNU has investigated approaches to develop a computationally intensive three-dimensional (3D) model for detailed and fine-tuned simulation.

Nuclide Release Behavior from a Repository for a Pyro-process HLW and SF due to Variation of the MWCF Properties

International Nuclear Information System (INIS)

Lee, Youn Myoung; Hwang, Yong Soo

2009-01-01

An assessment program for an optional evaluation of a repository both for disposal of such high-level wastes (HLWs) from various steps of pyro-processes of PWR spent nuclear fuel (SF) and for direct disposal of PWR and CANDU SFs has been developed by utilizing general purpose GoldSim developing tool, by which nuclide transports in the near- and far-field of a repository as well as a transport through a biosphere under various natural and manmade disruptive events affecting a nuclide release could be modeled and evaluated. KAERI has been in charge of modeling and developing assessment tools by which the above mentioned repository system could be assessed in accordance with various features, events, and processes (FEPs) that could happen in and around the repository system. To cope with such various natural and manmade disruptive FEPs as well as normal release scenarios, all the possible cases in view of the Korean circumstances should be modeled and have been evaluated even though we have not yet have any repository. A possible case, among many others, with the variation of such physical properties as the fracture width and the rock matrix diffusion depth, associated with the natural fractures in the geological rock media, along which nuclide could be transported preferentially with the flow of groundwater is considered in the current study. Due to whatever the reason, such as e,g., the earthquake or human intrusion, it is assumed that the physical properties of the major water conducting fault (MWCF) is changed resulting in the size of fracture width and the matrix diffusion depth. For such case another illustration is made for probabilistic evaluation of a hypothetical Korean HLW repository, as similarly done in the previous studies

Purification of used eutectic (LiCl-KCl) salt electrolyte from pyroprocessing

Science.gov (United States)

Cho, Yung-Zun; Lee, Tae-Kyo; Eun, Hee-Chul; Choi, Jung-Hoon; Kim, In-Tae; Park, Geun-Il

2013-06-01

The separation characteristics of surrogate rare-earth fission products in a eutectic (LiCl-KCl) molten salt were investigated. This system is based on the eutectic salt used for the pyroprocessing treatment of used nuclear fuel (UNF). The investigation was performed using an integrated rare-earth separation apparatus comprising a precipitation reactor, a solid detachment device, and a layer separation device. To separate rare-earth fission products, a phosphate precipitation method using both Li3PO4 and K3PO4 as a precipitant was performed. The use of an equivalent phosphate precipitant composed of 0.408 molar ratio-K3PO4 and 0.592 molar ratio-Li3PO4 can preserve the original eutectic ratio, LiCl-0.592 molar ratio (or 45.2 wt%), as well as provide a high separation efficiency of over 99.5% under conditions of 550 °C and Ar sparging when using La, Nd, Ce, and Pr chlorides. The mixture of La, Nd, Ce, and Pr phosphate had a typical monoclinic (or monazite) structure, which has been proposed as a reliable host matrix for the permanent disposal of a high-level waste form. To maximize the reusability of purified eutectic waste salt after rare-earth separation, the successive rare-earth separation process, which uses both phosphate precipitation and an oxygen sparging method, were introduced and tested with eight rare-earth (Y, La, Ce, Pr, Nd, Sm, Eu and Gd) chlorides. In the successive rare-earth separation process, the phosphate reaction was terminated within 1 h at 550 °C, and a 4-8 h oxygen sparging time were required to obtain over a 99% separation efficiency at 700-750 °C. The mixture of rare-earth precipitates separated by the successive rare-earth separation process was found to be phosphate, oxychloride, and oxide. Through the successive rare-earth separation process, the eutectic ratio of purified salt maintained its original value, and impurity content including the residual precipitant of purified salt can be minimized.

Development Proliferation Resistance Assessment Methodology for Regulation Purposes

International Nuclear Information System (INIS)

Ham, Taekyu; Seo, Janghoon; Lee, Nayoung; Yoo, Hosik

2015-01-01

More than 45 countries are considering embarking on nuclear power programs. As a result, the world's nuclear power generating capacity is projected to continue to grow by 2030. The installed total nuclear capacity in 373 GWe in 2012 would reach 435 and 722 GWe by 2030 in low and high scenario predictions, respectively. In Korea, there are 23 nuclear power plants in operation. Thirteen more plants are either under construction or are being planned for completion by 2027. In addition, there are active researches is taking place into pyroprocessing technology for use in treating spent fuel and reducing storage. Measures for analyzing PR of a nuclear energy system were derived by collecting attributes that influence PR and then were categorized into groups. Three measures were then developed by a series of processes; legal and institutional framework, material characteristics, and safeguardability. Since, the extrinsic features are more practical to evaluate when a regulatory body evaluates a system

Advanced liquid metal reactor development at Argonne National Laboratory during the 1980s

International Nuclear Information System (INIS)

Wade, D.C.

1990-01-01

Argonne National Laboratory's (ANL'S) effort to pursue the exploitation of liquid metal cooled reactor (LMR) characteristics has given rise to the Integral Fast Reactor (IFR) concept, and has produced substantial technical advancement in concept implementation which includes demonstration of high burnup capability of metallic fuel, demonstration of injection casting fabrication, integral demonstration of passive safety response, and technical feasibility of pyroprocessing. The first half decade of the 90's will host demonstration of the IFR closed fuel cycle technology at the prototype scale. The EBR-II reactor will be fueled with ternary alloy fuel in HT-9 cladding and ducts, and pyroprocessing and injection casting refabrication of EBR-II fuel will be conducted using near-commercial sized equipment at the Fuel cycle Facility (FCF) which is co-located adjacent to EBR-II. Demonstration will start in 1992. The demonstration of passive safety response achievable with the IFR design concept, (already done in EBR-II in 1986) will be repeated in the mid 90's using the IFR prototype recycle fuel from the FCF. The demonstration of scrubbing of the reprocessing fission product waste stream, with recycle of the transuranics to the reactor for consumption, will also occur in the mid 90's. 30 refs

Development of Korea telecommunication technology

International Nuclear Information System (INIS)

1992-06-01

It concentrates on development of Korea telecommunication technology, which is made up seven chapters. It gives description of manual central telephone exchange or private automatic telephone exchange, transmission technology on wire line and cable line technology and optical transmission, radio communication technology on mobile and natural satellite communication, network technology with intelligent network, broadband ISDN and packet switched Data Network, terminal technology with telephone and data communication terminal and development of Information Technology in Korea. It has an appendix about development of military communication system.

Advanced PWR technology development -Development of advanced PWR system analysis technology-

Energy Technology Data Exchange (ETDEWEB)

Jang, Moon Heui; Hwang, Yung Dong; Kim, Sung Oh; Yoon, Joo Hyun; Jung, Bub Dong; Choi, Chul Jin; Lee, Yung Jin; Song, Jin Hoh [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-07-01

The primary scope of this study is to establish the analysis technology for the advanced reactor designed on the basis of the passive and inherent safety concepts. This study is extended to the application of these technology to the safety analysis of the passive reactor. The study was performed for the small and medium sized reactor and the large sized reactor by focusing on the development of the analysis technology for the passive components. Among the identified concepts the once-through steam generator, the natural circulation of the integral reactor, heat pipe for containment cooling, and hydraulic valve were selected as the high priority items to be developed and the related studies are being performed for these items. For the large sized passive reactor, the study plans to extend the applicability of the best estimate computer code RELAP5/MOD3 which is widely used for the safety analyses of the reactor system. The improvement and supplementation study of the analysis modeling and the methodology is planned to be carried out for these purpose. The newly developed technologies are expected to be applied to the domestic advanced reactor design and analysis and these technologies will play a key role in extending the domestic nuclear base technology and consolidating self-reliance in the essential nuclear technology. 72 figs, 15 tabs, 124 refs. (Author).

Cooperative technology development: An approach to advancing energy technology

International Nuclear Information System (INIS)

Stern, T.

1989-09-01

Technology development requires an enormous financial investment over a long period of time. Scarce national and corporate resources, the result of highly competitive markets, decreased profit margins, wide currency fluctuations, and growing debt, often preclude continuous development of energy technology by single entities, i.e., corporations, institutions, or nations. Although the energy needs of the developed world are generally being met by existing institutions, it is becoming increasingly clear that existing capital formation and technology transfer structures have failed to aid developing nations in meeting their growing electricity needs. This paper will describe a method for meeting the electricity needs of the developing world through technology transfer and international cooperative technology development. The role of nuclear power and the advanced passive plant design will be discussed. (author)

Office of Technology Development integrated program for development of in situ remediation technologies

International Nuclear Information System (INIS)

Peterson, M.

1992-08-01

The Department of Energy's Office of Technology Development has instituted an integrated program focused on development of in situ remediation technologies. The development of in situ remediation technologies will focus on five problem groups: buried waste, contaminated soils, contaminated groundwater, containerized wastes and underground detonation sites. The contaminants that will be included in the development program are volatile and non volatile organics, radionuclides, inorganics and highly explosive materials as well as mixtures of these contaminants. The In Situ Remediation Integrated Program (ISR IP) has defined the fiscal year 1993 research and development technology areas for focusing activities, and they are described in this paper. These R ampersand D topical areas include: nonbiological in situ treatment, in situ bioremediation, electrokinetics, and in situ containment

Advanced Reactor Technologies - Regulatory Technology Development Plan (RTDP)

Energy Technology Data Exchange (ETDEWEB)

Moe, Wayne L. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2017-08-23

This DOE-NE Advanced Small Modular Reactor (AdvSMR) regulatory technology development plan (RTDP) will link critical DOE nuclear reactor technology development programs to important regulatory and policy-related issues likely to impact a “critical path” for establishing a viable commercial AdvSMR presence in the domestic energy market. Accordingly, the regulatory considerations that are set forth in the AdvSMR RTDP will not be limited to any one particular type or subset of advanced reactor technology(s) but rather broadly consider potential regulatory approaches and the licensing implications that accompany all DOE-sponsored research and technology development activity that deal with commercial non-light water reactors. However, it is also important to remember that certain “minimum” levels of design and safety approach knowledge concerning these technology(s) must be defined and available to an extent that supports appropriate pre-licensing regulatory analysis within the RTDP. Final resolution to advanced reactor licensing issues is most often predicated on the detailed design information and specific safety approach as documented in a facility license application and submitted for licensing review. Because the AdvSMR RTDP is focused on identifying and assessing the potential regulatory implications of DOE-sponsored reactor technology research very early in the pre-license application development phase, the information necessary to support a comprehensive regulatory analysis of a new reactor technology, and the resolution of resulting issues, will generally not be available. As such, the regulatory considerations documented in the RTDP should be considered an initial “first step” in the licensing process which will continue until a license is issued to build and operate the said nuclear facility. Because a facility license application relies heavily on the data and information generated by technology development studies, the anticipated regulatory

Advanced Reactor Technology -- Regulatory Technology Development Plan (RTDP)

Energy Technology Data Exchange (ETDEWEB)

Moe, Wayne Leland [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-05-01

This DOE-NE Advanced Small Modular Reactor (AdvSMR) regulatory technology development plan (RTDP) will link critical DOE nuclear reactor technology development programs to important regulatory and policy-related issues likely to impact a “critical path” for establishing a viable commercial AdvSMR presence in the domestic energy market. Accordingly, the regulatory considerations that are set forth in the AdvSMR RTDP will not be limited to any one particular type or subset of advanced reactor technology(s) but rather broadly consider potential regulatory approaches and the licensing implications that accompany all DOE-sponsored research and technology development activity that deal with commercial non-light water reactors. However, it is also important to remember that certain “minimum” levels of design and safety approach knowledge concerning these technology(s) must be defined and available to an extent that supports appropriate pre-licensing regulatory analysis within the RTDP. Final resolution to advanced reactor licensing issues is most often predicated on the detailed design information and specific safety approach as documented in a facility license application and submitted for licensing review. Because the AdvSMR RTDP is focused on identifying and assessing the potential regulatory implications of DOE-sponsored reactor technology research very early in the pre-license application development phase, the information necessary to support a comprehensive regulatory analysis of a new reactor technology, and the resolution of resulting issues, will generally not be available. As such, the regulatory considerations documented in the RTDP should be considered an initial “first step” in the licensing process which will continue until a license is issued to build and operate the said nuclear facility. Because a facility license application relies heavily on the data and information generated by technology development studies, the anticipated regulatory

New high-level waste management technology for IFR pyroprocessing wastes

International Nuclear Information System (INIS)

Ackerman, J.P.; Johnson, T.R.

1993-01-01

The pyrochemical electrorefining process for recovery of actinides in spent fuel from the Integral Fast Reactor accumulates fission product wastes as chlorides dissolved in molten LiCI-KCI and as metals, some of which are in molten cadmium. Pyrochemical processes are being developed to recover uranium and transuranium elements for return to the reactor, and to separate and immobilize fission products in suitable waste forms. Solvent cadmium is recycled within the process. Electrolyte salt is treated in a series of salt/cadmium extraction steps; it is also returned to the process. Salt-borne fission products are concentrated on a zeolite bed that is converted to a stable, leach-resistant mineral. Rare earth fission products from the salt, noble metal fission products, and cladding hulls are dispersed in a metal matrix

Technology Development and Innovation | Wind | NREL

Science.gov (United States)

Technology Development and Innovation Technology Development and Innovation Technology Development Technology Center (NWTC) supports efforts to reduce bird and bat fatalities at wind energy projects and photo of wind turbines at the National Wind Technology Center. Wildlife technology research and

Energy, technology, development

Energy Technology Data Exchange (ETDEWEB)

Goldemberg, J [Ministerio da Educacao, Brasilia (Brazil)

1992-02-01

Energy and technology are essential ingredients of development, it is only through their use that it became possible to sustain a population of almost 5 billion on Earth. The challenges to eradicate poverty and underdevelopment in developing countries in the face of strong population increases can only be successfully met with the use of advanced technology, leapfrogging the path followed in the past by today's industrialized countries. It is shown in the paper that energy consumption can be decoupled from economic development. Such possibility will contribute significantly in achieving sustainable development. 10 refs., 4 figs., 3 tabs.

Advanced Reactor Technology -- Regulatory Technology Development Plan (RTDP)

International Nuclear Information System (INIS)

Moe, Wayne Leland

2015-01-01

This DOE-NE Advanced Small Modular Reactor (AdvSMR) regulatory technology development plan (RTDP) will link critical DOE nuclear reactor technology development programs to important regulatory and policy-related issues likely to impact a ''critical path'' for establishing a viable commercial AdvSMR presence in the domestic energy market. Accordingly, the regulatory considerations that are set forth in the AdvSMR RTDP will not be limited to any one particular type or subset of advanced reactor technology(s) but rather broadly consider potential regulatory approaches and the licensing implications that accompany all DOE-sponsored research and technology development activity that deal with commercial non-light water reactors. However, it is also important to remember that certain ''minimum'' levels of design and safety approach knowledge concerning these technology(s) must be defined and available to an extent that supports appropriate pre-licensing regulatory analysis within the RTDP. Final resolution to advanced reactor licensing issues is most often predicated on the detailed design information and specific safety approach as documented in a facility license application and submitted for licensing review. Because the AdvSMR RTDP is focused on identifying and assessing the potential regulatory implications of DOE-sponsored reactor technology research very early in the pre-license application development phase, the information necessary to support a comprehensive regulatory analysis of a new reactor technology, and the resolution of resulting issues, will generally not be available. As such, the regulatory considerations documented in the RTDP should be considered an initial ''first step'' in the licensing process which will continue until a license is issued to build and operate the said nuclear facility. Because a facility license application relies heavily on the data and information generated by

Development of fabrication technology for CANDU advanced fuel -Development of the advanced CANDU technology-

Energy Technology Data Exchange (ETDEWEB)

Choi, Chang Beom; Kim, Hyeong Soo; Kim, Sang Won; Seok, Ho Cheon; Shim, Ki Seop; Byeon, Taek Sang; Jang, Ho Il; Kim, Sang Sik; Choi, Il Kwon; Cho, Dae Sik; Sheo, Seung Won; Lee, Soo Cheol; Kim, Yoon Hoi; Park, Choon Ho; Jeong, Seong Hoon; Kang, Myeong Soo; Park, Kwang Seok; Oh, Hee Kwan; Jang, Hong Seop; Kim, Yang Kon; Shin, Won Cheol; Lee, Do Yeon; Beon, Yeong Cheol; Lee, Sang Uh; Sho, Dal Yeong; Han, Eun Deok; Kim, Bong Soon; Park, Cheol Joo; Lee, Kyu Am; Yeon, Jin Yeong; Choi, Seok Mo; Shon, Jae Moon [Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)

1994-07-01

The present study is to develop the advanced CANDU fuel fabrication technologies by means of applying the R and D results and experiences gained from localization of mass production technologies of CANDU fuels. The annual portion of this year study includes following: 1. manufacturing of demo-fuel bundles for out-of-pile testing 2. development of technologies for the fabrication and inspection of advanced fuels 3. design and munufacturing of fuel fabrication facilities 4. performance of fundamental studies related to the development of advanced fuel fabrication technology.

High performance fuel technology development

Energy Technology Data Exchange (ETDEWEB)

Koon, Yang Hyun; Kim, Keon Sik; Park, Jeong Yong; Yang, Yong Sik; In, Wang Kee; Kim, Hyung Kyu [KAERI, Daejeon (Korea, Republic of)

2012-01-15

{omicron} Development of High Plasticity and Annular Pellet - Development of strong candidates of ultra high burn-up fuel pellets for a PCI remedy - Development of fabrication technology of annular fuel pellet {omicron} Development of High Performance Cladding Materials - Irradiation test of HANA claddings in Halden research reactor and the evaluation of the in-pile performance - Development of the final candidates for the next generation cladding materials. - Development of the manufacturing technology for the dual-cooled fuel cladding tubes. {omicron} Irradiated Fuel Performance Evaluation Technology Development - Development of performance analysis code system for the dual-cooled fuel - Development of fuel performance-proving technology {omicron} Feasibility Studies on Dual-Cooled Annular Fuel Core - Analysis on the property of a reactor core with dual-cooled fuel - Feasibility evaluation on the dual-cooled fuel core {omicron} Development of Design Technology for Dual-Cooled Fuel Structure - Definition of technical issues and invention of concept for dual-cooled fuel structure - Basic design and development of main structure components for dual- cooled fuel - Basic design of a dual-cooled fuel rod.

Mobilizing technology for developing countries

Energy Technology Data Exchange (ETDEWEB)

Weiss, C Jr

1979-10-01

Mr. Weiss says that the 15 years since the UN Conference on Science, Technology, and Development in Geneva have taught us that what seem at first to be technological obstacles to development frequently turn out on closer examination to have been policy failures; that introduction of technologies into developing countries must be accompanied by institutional and policy changes if the technologies are to benefit the countries. He points out that choice of alternative technology for a developing country should depend on careful overall assessment of local techno-economic, geographical, ecological, and social factors, as well as the desired balance between growth and equity. Such a technology assessment, a key element in the choice of appropriate (i.e., locally suitable) technology for particular investment projects, should be built into procedures for project preparation and appraisal in governments and development assistance agencies. Turning to technologists, Mr. Weiss says they face a double challenge: (1) to recognize potential for new efforts to harness science and technology for the benefit of the developing countries; and (2) by understanding the social, institutional, and economic framework into which an innovation is to operate, to ease its application and diffusion, and thus speed and increase its practical impact. 25 references.

Development of Coated Particle Fuel Technology

International Nuclear Information System (INIS)

Lee, Young Woo; Kim, B. G.; Kim, S. H.

2007-06-01

Uranium kernel fabrication technology using a wet chemical so-gel method, a key technology in the coated particle fuel area, is established up to the calcination step and the first sintering of UO2 kernel was attempted. Experiments on the parametric study of the coating process using the surrogate ZrO2 kernel give the optimum conditions for the PyC and SiC coating layer and ZrC coating conditions were obtained for the vaporization of the ZrCl4 precursor and coating condition from ZrC coating experiments using plate-type graphite substrate. In addition, by development of fuel performance analysis code a part of the code system is completed which enables the participation to the benchmark calculation and comparison in the IAEA collaborated research program. The technologies for irradiation and post irradiation examination, which are important in developing the HTGR fuel technology of its first kind in Korea was started to develop and, through a feasibility study and preliminary analysis, the technologies required to be developed are identified for further development as well as the QC-related basic technologies are reviewed, analyzed and identified for the own technology development. Development of kernel fabrication technology can be enhanced for the remaining sintering technology and completed based on the technologies developed in this phase. In the coating technology, the optimum conditions obtained using a surrogate ZrO2 kernel material can be applied for the uranium kernel coating process development. Also, after completion of the code development in the next phase, more extended participation to the international collaboration for benchmark calculation can be anticipated which will enable an improvement of the whole code system. Technology development started in this phase will be more extended and further focused on the detailed technology development to be required for the related technology establishment

Evaluation of Design Models of Process Equipment for Use in PRIDE: Remote Operability and Maintainability

International Nuclear Information System (INIS)

Kim, Ki Ho; Kim, Sung Hyun; Yu, Seung Nam; Lee, Jong Kwang; Park, Byung Suk; Han, Jong Hui; Cho, Il Je; Lee, Han Soo

2012-01-01

Process equipment for pyroprocessing are being developed at KAERI (Korea Atomic Energy Research Institute). Those equipment should be operated and maintained in a fully remote manner in the argon gas filled cell of PRIDE (PyRoprocess Integrated inactive DEmonstration facility) at KAERI because direct human access to the in-cell is not possible during an operation due to the high toxicity of the argon gas. To make such process equipment remotely operable and maintainable, their design developments have been tested and evaluated in a simulator before they are constructed. A simulator as a means of evaluating the remote operability and maintainability of the design models of process equipment for pyroprocessing is described, and results of the design models tested and evaluated in a simulator are presented

Mars Technology Program: Planetary Protection Technology Development

Science.gov (United States)

Lin, Ying

2006-01-01

This slide presentation reviews the development of Planetary Protection Technology in the Mars Technology Program. The goal of the program is to develop technologies that will enable NASA to build, launch, and operate a mission that has subsystems with different Planetary Protection (PP) classifications, specifically for operating a Category IVb-equivalent subsystem from a Category IVa platform. The IVa category of planetary protection requires bioburden reduction (i.e., no sterilization is required) The IVb category in addition to IVa requirements: (i.e., terminal sterilization of spacecraft is required). The differences between the categories are further reviewed.

FY-95 technology catalog. Technology development for buried waste remediation

International Nuclear Information System (INIS)

1995-01-01

The US Department of Energy's (DOE) Buried Waste Integrated Demonstration (BWID) program, which is now part of the Landfill Stabilization Focus Area (LSFA), supports applied research, development, demonstration, and evaluation of a multitude of advanced technologies dealing with underground radioactive and hazardous waste remediation. These innovative technologies are being developed as part of integrated comprehensive remediation systems for the effective and efficient remediation of buried waste sites throughout the DOE complex. These efforts are identified and coordinated in support of Environmental Restoration (EM-40) and Waste Management (EM-30) needs and objectives. Sponsored by the DOE Office of Technology Development (EM-50), BWID and LSFA work with universities and private industry to develop technologies that are being transferred to the private sector for use nationally and internationally. This report contains the details of the purpose, logic, and methodology used to develop and demonstrate DOE buried waste remediation technologies. It also provides a catalog of technologies and capabilities with development status for potential users. Past FY-92 through FY-94 technology testing, field trials, and demonstrations are summarized. Continuing and new FY-95 technology demonstrations also are described

FY-95 technology catalog. Technology development for buried waste remediation

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-01

The US Department of Energy`s (DOE) Buried Waste Integrated Demonstration (BWID) program, which is now part of the Landfill Stabilization Focus Area (LSFA), supports applied research, development, demonstration, and evaluation of a multitude of advanced technologies dealing with underground radioactive and hazardous waste remediation. These innovative technologies are being developed as part of integrated comprehensive remediation systems for the effective and efficient remediation of buried waste sites throughout the DOE complex. These efforts are identified and coordinated in support of Environmental Restoration (EM-40) and Waste Management (EM-30) needs and objectives. Sponsored by the DOE Office of Technology Development (EM-50), BWID and LSFA work with universities and private industry to develop technologies that are being transferred to the private sector for use nationally and internationally. This report contains the details of the purpose, logic, and methodology used to develop and demonstrate DOE buried waste remediation technologies. It also provides a catalog of technologies and capabilities with development status for potential users. Past FY-92 through FY-94 technology testing, field trials, and demonstrations are summarized. Continuing and new FY-95 technology demonstrations also are described.

Development of Cr Electroplated Cladding Tube for preventing Fuel-Cladding Chemical Interaction (FCCI)

Energy Technology Data Exchange (ETDEWEB)

Kim, Jun Hwan; Woo, Je Woong; Kim, Sung Ho; Cheon, Jin Sik; Lee, Byung Oon; Lee, Chan Bock [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-05-15

Metal fuel has been selected as a candidate fuel in the SFR because of its superior thermal conductivity as well as enhanced proliferation resistance in connection with the pyroprocessing. However, metal fuel suffers eutectic reaction (Fuel Cladding Chemical Interaction, FCCI) with the fuel cladding made of stainless steel at reactor operating temperature so that cladding thickness gradually reduces to endanger reactor safety. In order to mitigate FCCI, barrier concept has been proposed between the fuel and the cladding in designing fuel rod. Regarding this, KAERI has initiated barrier cladding development to prevent interdiffusion process as well as enhance the SFR fuel performance. Previous study revealed that Cr electroplating has been selected as one of the most promising options because of its technical and economic viability. This paper describes the development status of the Cr electroplating technology for the usage of fuel rod in SFR. This paper summarizes the status of Cr electroplating technology to prevent FCCI in metal fuel rod. It has been selected for the ease of practical application at the tube inner surface. Technical scoping, performance evaluation and optimization have been carried out. Application to the tube inner surface and in-pile test were conducted which revealed as effective.

Development of Radioisotope Tracer Technology

International Nuclear Information System (INIS)

Jung, Sung Hee; Jin, Joon Ha; Kim, Jong Bum; Kim, Jin Seop; Kim, Jae Jo; Park, Soon Chul; Lim, Don Soon; Choi, Byung Jong; Jang, Dong Soon; Kim, Hye Sook

2007-06-01

The project is aimed to develop the radiotracer technology for process optimization and trouble-shooting to establish the environmental and industrial application of radiation and radioisotopes. The advanced equipment and software such as high speed data acquisition system, RTD model and high pressure injection tool have developed. Based on the various field application to the refinery/petrochemical industries, the developed technology was transfer to NDT company for commercial service. For the environmental application of radiotracer technology, injector, detector sled, core sampler, RI and GPS data logging system are developed and field tests were implemented successfully at Wolsung and Haeundae beach. Additionally tracer technology were also used for the performance test of the clarifier in a wastewater treatment plant and for the leak detection in reservoirs. From the experience of case studies on radiotracer experiment in waste water treatment facilities, 'The New Excellent Technology' is granted from the ministry of environment. For future technology, preliminary research for industrial gamma transmission and emission tomography which are new technology combined with radioisotope and image reconstruction are carried out

Safety assessment for a potential SNF repository and its implication to the proliferation resistance nuclear fuel cycle

International Nuclear Information System (INIS)

Hwang, Y.; Jeong, M.S.; Seo, C.S.

2007-01-01

KAERI is developing the pyro-process technology to minimize the burden on permanent disposal of spent nuclear fuel. In addition, KAERI has developed the Korean Reference System for potential spent nuclear fuel disposal since 1997. The deep geologic disposal system is composed of a multi-barrier system in a crystalline rock to dispose of 36,000 MT of spent nuclear fuel (SNF) from a CANDU and a PWR. Quite recently, introduction of advanced nuclear fuel cycles such as pyro-processing is a big issue to solve the everlasting disposal problem and to assure the sustainable supply of fuel for reactors. To compare the effect of direct disposal of SNF with that of the high level waste disposal for waste generated from the advanced nuclear fuel cycles, the total system performance assessment for two different schemes is developed; one for direct disposal of SNF and the other for the introduction of the pyro-processing and direct disposal CANDU spent nuclear fuel. The safety indicators to assess the environmental friendliness of the disposal option are annual individual doses, toxicities and risks. Even though many scientists use the toxicity to understand the environmental friendliness of the disposal, scientifically the annual individual doses or risks are meaningful indicators for it. The major mechanisms to determine the doses and risks for direct disposal are as follows: (1) Dissolution mechanisms of uranium dioxides which control the dissolution of most nuclides such as TRU's and most parts of fission products. (2) Instant release fraction of highly soluble nuclides such as I-129, C-135, Tc-99, and others. (3) Retardation and dilution effect of natural and engineered barriers. (4) Dilution effect in the biosphere. The dominant nuclide is I-129 which follows both congruent and instantaneous release modes. Since its long half life associated with the instantaneous release I-129 is dominant well beyond one million. The impact of the TRU's is negligible until the significant

Technology transfer and international development: Materials and manufacturing technology

Science.gov (United States)

1982-01-01

Policy oriented studies on technological development in several relatively advanced developing countries were conducted. Priority sectors defined in terms of technological sophistication, capital intensity, value added, and export potential were studied in Brazil, Venezuela, Israel, and Korea. The development of technological policy alternatives for the sponsoring country is assessed. Much emphasis is placed on understanding the dynamics of the sectors through structured interviews with a large sample of firms in the leading manufacturing and materials processing sectors.

Sensitivity of Transmutation Capability to Recycling Scenarios in KALIMER-600 TRU Burner

International Nuclear Information System (INIS)

Lee, Yong Kyo; Kim, Myung Hyun

2013-01-01

The purpose of this study is to test transmutation and design feasibility of KALIMER burner caused from many limitations in recycling options; such as low recovery factors and external feed. Design impact from many recycling options will be tested as a sensitivity to various recycling process parameters under many recycling scenarios. Through this study, possibilities when Pyro-processing is realized with SFR can be expected in the recycling scenarios. For the development of sodium-cooled fast reactor(SFR) technology, prototype KALIMER plant is now under R and D stage in Korea. For the future application of SFR for waste transmutation, KALIMER core was designed for TRU burner by KAERI. Feasibility of TRU burner cannot be evaluated exactly because overall functional parameters in pyro-processing recycling process has not been verified yet. There is great possibility to accept undesirable process functions in pyro-processing. Only TRU nuclides composition a little differs between PWR SF and CANDU SF so first scenario has no problem operating SFR. In second scenario, the radiotoxicity of waste at 99% of TRU RF have to be confirmed whether it is proper level to reposit as Low and Intermediate Level Wastes or not. And the reactor safety at high RF of RE must be inspected. Not only third scenario but also several scenarios for good measure are being calculated and will be evaluated

A Study on Improvement of Algorithm for Source Term Evaluation

International Nuclear Information System (INIS)

Park, Jeong Ho; Park, Do Hyung; Lee, Jae Hee

2010-03-01

The program developed by KAERI for source term assessment of radwastes from the advanced nuclear fuel cycle consists of spent fuel database analysis module, spent fuel arising projection module, and automatic characterization module for radwastes from pyroprocess. To improve the algorithm adopted the developed program, following items were carried out: - development of an algorithm to decrease analysis time for spent fuel database - development of setup routine for a analysis procedure - improvement of interface for spent fuel arising projection module - optimization of data management algorithm needed for massive calculation to estimate source terms of radwastes from advanced fuel cycle The program developed through this study has a capability to perform source term estimation although several spent fuel assemblies with different fuel design, initial enrichment, irradiation history, discharge burnup, and cooling time are processed at the same time in the pyroprocess. It is expected that this program will be very useful for the design of unit process of pyroprocess and disposal system

Analysis of the Important Factors for the LSDTS System

Energy Technology Data Exchange (ETDEWEB)

Lee, Yong Deok; Song, Jae Hoon; Park, Chang Je; Song, Kee Chan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-11-15

It is confirmed that it is necessary to have domestic experience for measuring fissile material such as U-235, U-238, and Pu-239 in spent fuel or pyro-processed fuel containing TRU and to have technology related with measurement for fissile material. Understanding newly advanced measurement system for fissile material, it indicates the development directions. In this research, it is shown to the basic principle of LSDTS and it is investigated to commercial neutron source generator in order to use appropriated neutron source in the LSDTS. On the other hand, it is understood to the properties for fission chamber as induced neutron detector. It is confirmed to the relationship between slowing-down time and neutron energy in slowing-down medium. Understanding the application of SDTS, the efficiency is broaden, that is, it can help as equipment for real-time, direct, and quantitative measurement of fissile material from fuel assay such as spent fuel or pyro-processed fuel.

Coherent Architecture Development as a Basis for Technology Development

DEFF Research Database (Denmark)

Ravn, Poul Martin

coherent architectures in a technology context as a basis for identification of critical development areas, this research has been focused around the following three areas: 1. Product architecture instances for prototypes testing novel technology. 2. Product architecture definition for a sub-system based......The subject of this PhD thesis is architecture-centered design. It elaborates especially on two specific areas: the coherence in architectures in a technology development context and the identification of critical development areas via property-based reasoning, based on an understanding of cette...... coherence. Despite the acceptance and results presented in multiple studies from the application of architectures, the research on architecture work in a technology development context is limited. Technologies are often developed and represented in the form of product sub-systems that are made available...

Technology development and applications at Fernald

International Nuclear Information System (INIS)

Pettit, P.J.; Skriba, M.C.; Warner, R.D.

1995-01-01

At the Fernald Environmental Management Project (FEMP) northwest of Cincinnati, Ohio, the U.S. Department of Energy and contractor Fernald Environmental Restoration Management Corporation (FERMCO) are aggressively pursuing both the development and the application of improved, innovative technology to the environmental restoration task. Application of emerging technologies is particularly challenging in a regulatory environment that places pressure on operational managers to develop and meet tight schedules. The regulatory and operational needs make close communication essential between technology developers and technology users (CERCLA/RCRA Unit managers). At Fernald this cooperation and communication has led, not only to the development and demonstration of new technologies with applications at other sites, but also to application of new technologies directly to the Fernald clean up. New technologies have been applied to improve environmental safety and health, improve the effectiveness of restoration efforts, and to cut restoration costs. The paper will describe successful efforts to develop and apply new technologies at the FEMP and will emphasize those technologies that have been applied and are planned for use in the clean up of this former uranium production facility

National Nuclear Technology Map Development

International Nuclear Information System (INIS)

Shin, J. I.; Lee, T. J.; Yoon, S. W.

2005-03-01

The objective of NuTRM is to prepare a plan of nuclear R and D and technological innovations which is very likely to make nuclear technology a promising power source for future national developments. The NuTRM finds out systematically the nuclear R and D vision and the high-value-added strategic technologies to be developed by the efficient cooperation of actors including government, industry, academy and research institute by 2020. In other words, NuTRM aims at a long-term strategic planning of nuclear R and D and technological innovation in order to promote the socio-economic contributions of nuclear science and technology for the nation's future competitiveness and sustainable development and to raise the global status of the Korean nuclear R and D and Industry

Technological development in fisheries management

DEFF Research Database (Denmark)

Eigaard, Ole Ritzau; Marchal, Paul; Gislason, Henrik

2014-01-01

Many marine fish stocks are overexploited and considerable overcapacity exists in fishing fleets worldwide. One of the reasons for the imbalance between resource availability and fishing capacity is technological development, which continuously increases the efficiency of the vessels—a mechanism...... referred to as “technological creep.” We review how the introduction of new and more efficient electronic equipment, gear design, engines, deck equipment, and catch-handling procedures influences the capture efficiency (catchability) of commercial fishing vessels. On average, we estimate that catchability...... increases by 3.2% per year due to technological developments, an increase often ignored in fisheries management. The documentation and quantification of technological creep improves the basis for successfully integrating the effects of technological development (and catchability changes) in fisheries...

ABC Technology Development Program

International Nuclear Information System (INIS)

1994-01-01

The Accelerator-Based Conversion (ABC) facility will be designed to accomplish the following mission: 'Provide a weapon's grade plutonium disposition capability in a safe, economical, and environmentally sound manner on a prudent schedule for [50] tons of weapon's grade plutonium to be disposed on in [20] years.' This mission is supported by four major objectives: provide a reliable plutonium disposition capability within the next [15] years; provide a level of safety and of safety assurance that meets or exceeds that afforded to the public by modern commercial nuclear power plants; meet or exceed all applicable federal, state, and local regulations or standards for environmental compliance; manage the program in a cost effective manner. The ABC Technology Development Program defines the technology development activities that are required to accomplish this mission. The technology development tasks are related to the following topics: blanket system; vessel systems; reactivity control systems; heat transport system components; energy conversion systems; shutdown heat transport systems components; auxiliary systems; technology demonstrations - large scale experiments

The EM technology development strategy

International Nuclear Information System (INIS)

Frank, C.W.; Barainca, M.; Kubo, A.S.

1992-01-01

The Office of Technology Development (TD) supports research and development of technologies that will lower cost, reduce risk, improve safety, and accelerate cleanup of the Nuclear Weapons Complex and provide solutions to currently untractable environmental problems. The TD strategic plan outlines Applied Research, Development, Demonstration, Testing, and Evaluation (RDDT and E) that will provide needed technology products to be used by Environmental Restoration and Waste Management operations (i.e., our customers). The TD strategic plan is derived from EM Goals, Objectives, and Strategy and is incorporated into DOE'S Five-Year Plan for Environmental Restoration and Waste Management. The TD strategic plan is developed based on integrating customer requirements, and is complemented by a top-down, bottom-up analysis of Site Specific Technology Needs and environmental problems. The execution of TD's strategic plan is implemented largely through Integrated Programs (IP) and Integrated Demonstrations (ID). IDs have proven to be a cost-effective method of managing technology development, testing and evaluation, and implementation of successful technology systems into the DOE Environmental Restoration and Waste Management Programs. The Savannah River ID for Volatile Organic Compounds (VOCs) in Saturated Soils resulted in a 51 percent cost savings over stand-alone demonstrations, saving over $8 million. The IPs and IDs are selected based on customer needs, technical complexity, and complex-wide regulatory and compliance agreements. New technology systems are selected for incorporation into an IP or ID from offerings of the DOE laboratories, industry, and the universities. A major TD initiative was announced in August 1991, with the release of a Program Research and Development Announcement (PRDA) requesting industry and universities to propose innovative new technologies to clean up the Weapons Complex. (author)

Development of coal energy utilization technologies

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

Coal liquefaction produces new and clean energy by performing hydrogenation, decomposition and liquefaction on coal under high temperatures and pressures. NEDO has been developing bituminous coal liquefaction technologies by using a 150-t/d pilot plant. It has also developed quality improving and utilization technologies for liquefied coal, whose practical use is expected. For developing coal gasification technologies, construction is in progress for a 200-t/d pilot plant for spouted bed gasification power generation. NEDO intends to develop coal gasification composite cycle power generation with high efficiency and of environment harmonious type. This paper summarizes the results obtained during fiscal 1994. It also dwells on technologies to manufacture hydrogen from coal. It further describes development of technologies to manufacture methane and substituting natural gas (SNG) by hydrogenating and gasifying coal. The ARCH process can select three operation modes depending on which of SNG yield, thermal efficiency or BTX yield is targeted. With respect to promotion of coal utilization technologies, description is given on surveys on development of next generation technologies for coal utilization, and clean coal technology promotion projects. International coal utilization and application projects are also described. 9 figs., 3 tabs.

Consuming technologies - developing routines

DEFF Research Database (Denmark)

Gram-Hanssen, Kirsten

2008-01-01

technologies and in this article these processes will be investigated from three different perspectives: an historical perspective of how new technologies have entered homes, a consumer perspective of how both houses and new technologies are purchased and finally, as the primary part of the article, a user...... perspective of how routines develop while these technologies are being used. In the conclusion these insights are discussed in relation to possible ways of influencing routines....

HTGR technology development: status and direction

International Nuclear Information System (INIS)

Kasten, P.R.

1982-01-01

During the last two years there has been an extensive and comprehensive effort expended primarily by General Atomic (GA) in generating a revised technology development plan. Oak Ridge National Laboratory (ORNL) has assisted in this effort, primarily through its interactions over the past years in working together with GA in technology development, but also through detailed review of the initial versions of the technology development plan as prepared by GA. The plan covers Fuel Technology, Materials Technology (including metals, graphite, and ceramics), Plant Technology (including methods, safety, structures, systems, heat exchangers, control and electrical, and mechanical), and Component Design Verification and Support areas

Safeguards System for the Advanced Spent Fuel Conditioning Process Facility

International Nuclear Information System (INIS)

Kim, Ho-dong; Lee, T.H.; Yoon, J.S.; Park, S.W; Lee, S.Y.; Li, T.K.; Menlove, H.; Miller, M.C.; Tolba, A.; Zarucki, R.; Shawky, S.; Kamya, S.

2007-01-01

The advanced spent fuel conditioning process (ACP) which is a part of a pyro-processing has been under development at Korean Atomic Energy Research Institute (KAERI) since 1997 to tackle the problem of an accumulation of spent fuel. The concept is to convert spent oxide fuel into a metallic form in a high temperature molten salt in order to reduce the heat energy, volume, and radioactivity of a spent fuel. Since the inactive tests of the ACP have been successfully implemented to confirm the validity of the electrolytic reduction technology, a lab-scale hot test will be undertaken in a couple of years to validate the concept. For this purpose, the KAERI has built the ACP Facility (ACPF) at the basement of the Irradiated Material Examination Facility (IMEF) of KAERI, which already has a reserved hot-cell area. Through the bilateral arrangement between US Department of Energy (DOE) and Korean Ministry of Science and Technology (MOST) for safeguards R and D, the KAERI has developed elements of safeguards system for the ACPF in cooperation with the Los Alamos National Laboratory (LANL). The reference safeguards design conditions and equipment were established for the ACPF. The ACPF safeguards system has many unique design specifications because of the particular characteristics of the pyro-process materials and the restrictions during a facility operation. For the material accounting system, a set of remote operation and maintenance concepts has been introduced for a non-destructive assay (NDA) system. The IAEA has proposed a safeguards approach to the ACPF for the different operational phases. Safeguards measures at the ACPF will be implemented during all operational phases which include a 'Cold Test', a 'Hot Test' and at the end of a 'Hot test'. Optimization of the IAEA's inspection efforts was addressed by designing an effective safeguards approach that relies on, inter alia, remote monitoring using cameras, installed NDA instrumentation, gate monitors and seals

Construction and engineering report for advanced nuclear fuel development facility

International Nuclear Information System (INIS)

Cho, S. W.; Park, J. S.; Kwon, S.J.; Lee, K. W.; Kim, I. J.; Yu, C. H.

2003-09-01

The design and construction of the fuel technology development facility was aimed to accommodate general nuclear fuel research and development for the HANARO fuel fabrication and advanced fuel researches. 1. Building size and room function 1) Building total area : approx. 3,618m 2 , basement 1st floor, ground 3th floor 2) Room function : basement floor(machine room, electrical room, radioactive waste tank room), 1st floor(research reactor fuel fabrication facility, pyroprocess lab., metal fuel lab., nondestructive lab., pellet processing lab., access control room, sintering lab., etc), 2nd floor(thermal properties measurement lab., pellet characterization lab., powder analysis lab., microstructure analysis lab., etc), 3rd floor(AHU and ACU Room) 2. Special facility equipment 1) Environmental pollution protection equipment : ACU(2sets), 2) Emergency operating system : diesel generator(1set), 3) Nuclear material handle, storage and transport system : overhead crane(3sets), monorail hoist(1set), jib crane(2sets), tank(1set) 4) Air conditioning unit facility : AHU(3sets), packaged air conditioning unit(5sets), 5) Automatic control system and fire protection system : central control equipment(1set), lon device(1set), fire hose cabinet(3sets), fire pump(3sets) etc

Technology research and development

International Nuclear Information System (INIS)

Haas, G.M.; Abdov, M.A.; Baker, C.C.; Beuligmann, R.F.

1985-01-01

The U.S. Dept. of Energy discusses the new program plan, the parameters of which are a broad scientific and technology knowledge base, an attractive plasma configuration to be determined, and other issues concerning uncertainty as to what constitutes attractive fusion options to be determined in the future, and increased collaboration. Tables show changing directions in magnetic fusion energy, two examples of boundary condition impacts on long-term technology development, and priority classes of the latter. The Argonne National Laboratory comments on the relationship between science, technology and the engineering aspects of the fusion program. UCLA remarks on the role of fusion technology in the fusion program plan, particularly on results from the recent studies of FINESSE. General Dynamics offers commentary on the issues of a reduced budget, and new emphasis on science which creates an image of the program. A table illustrates technology research and development in the program plan from an industrial perspective

Forward-Looking Planning of Technology Development

Directory of Open Access Journals (Sweden)

Katarzyna Halicka

2015-12-01

Full Text Available The main aim of this article is to adapt the Future-Oriented Technology Analysis (FTA to prospective planning of technology development. Firstly, the article presents the assumptions, methods and idea, as well as the concept of the FTA method. Moreover, selected publications on the use of this method were analysed. Then, an original, base model of forward-looking planning of technology development was constructed and presented. The end result of this process will be the development of the localized in time, presented in graphic form, action plan referred to as the route of technology development. Basing on the literature review and the research projects a preliminary route of development of arbitrarily chosen technology was also built and presented.

Development of nuclear fuel cycle technology

International Nuclear Information System (INIS)

Kawahara, Akira; Sugimoto, Yoshikazu; Shibata, Satoshi; Ikeda, Takashi; Suzuki, Kazumichi; Miki, Atsushi.

1990-01-01

In order to establish the stable supply of nuclear fuel as an important energy source, Hitachi ltd. has advanced the technical development aiming at the heightening of reliability, the increase of capacity, upgrading and the heightening of performance of the facilities related to nuclear fuel cycle. As for fuel reprocessing, Japan Nuclear Fuel Service Ltd. is promoting the construction of a commercial fuel reprocessing plant which is the first in Japan. The verification of the process performance, the ensuring of high reliability accompanying large capacity and the technical development for recovering effective resources from spent fuel are advanced. Moreover, as for uranium enrichment, Laser Enrichment Technology Research Association was founded mainly by electric power companies, and the development of the next generation enrichment technology using laser is promoted. The development of spent fuel reprocessing technology, the development of the basic technology of atomic process laser enrichment and so on are reported. In addition to the above technologies recently developed by Hitachi Ltd., the technology of reducing harm and solidification of radioactive wastes, the molecular process laser enrichment and others are developed. (K.I.)

Development of National Technology Audit Policy

Directory of Open Access Journals (Sweden)

Subiyanto Subiyanto

2017-07-01

Full Text Available The Laws have mandated implementation of technology audit, nevertheless such implementation needs an additional policy that is more technical. The concept of national audit technology policy shall make technology audit as a tool to ensure the benefit of technology application for society and technology advance for nation independency. This article discusses on technology audit policy concept especially infrastructure requirement, with emphasis on regulation, implementation tools, and related institution. The development of technology audit policy for national interest requires provision of mandatory audit implementation, accompanied by tools for developing technology auditor’s competence and technology audit institutional’s mechanism. To guide technology auditor’s competence, concept of national audit technology policy shall classify object of technology audit into product technology, production technology, and management of technology, accompanied by related parameters of technology performance evaluation.

SBWR technology and development

International Nuclear Information System (INIS)

Rao, A.S.; McCandless, R.J.; Sawyer, C.D.

1991-01-01

The simplified boiling water reactor (SBWR) is based on utilizing to the maximum extent possible proven light water reactor (LWR) technology developed through 30 years of operating plant experience plus the advanced boiling water reactor (ABWR) technology development program. For the unique features, developmental programs have been put in place to qualify the design. Thus, the focus of technology development has been on the passive safety features - the gravity-driven ECCS (GDCS) and the containment heat removal (PCCS). General Electric constructed a full-height, scaled, integral facility to demonstrate the GDCS concept and provide data for methods qualification. For the PCCS, a three-pronged program was implemented. Basic heat transfer data were obtained via testing at the Massachusetts Institute of Technology and the University of California at Berkeley. A full-height scaled integral facility to demonstrate the PCCS concept and provide data for methods qualification was constructed in Japan in 1989. Initial testing is now complete. Design of a full-scale heat exchanger unit is underway and testing is planned for completion in early 1993

Development of the advanced CANDU technology -Development of basic technology for HWR design

International Nuclear Information System (INIS)

Seok, Ho Cheon; Seok, Soo Dong; Lee, Sang Yong

1996-07-01

It is believed that it is easier for Korea to become self-reliant in PHWR technology than in PWR technology, mainly because of the lower design pressure and temperature and because of the simplicity, economy, flexibility of the fuel cycle in comparison with PWR systems. Even though one has no doubt about the safety and the economics of the PHWR's that are now being operated or constructed in Korea. It is necessary to develop the advanced design technology for even safer and more economical PHWR systems to overcome the ever growing international resistance to sharing of nuclear technology and to meet the even more stringent requirements for the future public acceptance of nuclear power. This study is to develop the more advance design technology compared to the existing one, especially in the field of reactor physics, safety systems and safety evaluation to realize the above requirements. 71 tabs., 147 figs., 143 refs. (Author)

Development of the advanced CANDU technology -Development of basic technology for HWR design-

Energy Technology Data Exchange (ETDEWEB)

Suk, Hoh Chun; Lee, Sang Yong; Suk, Soo Dong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-07-01

It is believed that it is easier for Korea to become self-reliant in PHWR technology than in PWR technology, mainly because of the lower design pressure and temperature and because of the simplicity, economy, flexibility of the fuel cycle in comparison with PWR systems. Even though one has no doubt about the safety and the economics of the PHWR`s that are now being operated or constructed in Korea, it is necessary to develop the advanced design technology for even safer and more economical PHWR systems to overcome the ever growing international resistance to sharing of nuclear technology and to meet the even more stringent requirements for the future public acceptance of nuclear power. This study is to develop the more advance design technology compared to the existing one, by performing in-depth studies especially in the field of reactor physics, safety systems and safety evaluation to realize the above requirements. 90 figs, 50 tabs, 38 refs. (Author).

Development of the advanced CANDU technology -Development of basic technology for HWR design-

International Nuclear Information System (INIS)

Suk, Hoh Chun; Lee, Sang Yong; Suk, Soo Dong

1995-07-01

It is believed that it is easier for Korea to become self-reliant in PHWR technology than in PWR technology, mainly because of the lower design pressure and temperature and because of the simplicity, economy, flexibility of the fuel cycle in comparison with PWR systems. Even though one has no doubt about the safety and the economics of the PHWR's that are now being operated or constructed in Korea, it is necessary to develop the advanced design technology for even safer and more economical PHWR systems to overcome the ever growing international resistance to sharing of nuclear technology and to meet the even more stringent requirements for the future public acceptance of nuclear power. This study is to develop the more advance design technology compared to the existing one, by performing in-depth studies especially in the field of reactor physics, safety systems and safety evaluation to realize the above requirements. 90 figs, 50 tabs, 38 refs. (Author)

Development of Radiochemical Separation Technology

Energy Technology Data Exchange (ETDEWEB)

Lee, Eil Hee; Kim, K. W.; Yang, H. B. (and others)

2007-06-15

This project of the second phase was aimed at the development of basic unit technologies for advanced partitioning, and the application tests of pre-developed partitioning technologies for separation of actinides by using a simulated multi-component radioactive waste containing Am, Np, Tc, U and so on. The goals for recovery yield of TRU, and for purity of Tc are high than 99% and about 99%, respectively. The work scopes and contents were as follows. 1). For the development of basic unit technologies for advanced partitioning. 1. Development of technologies for co-removal of TRU and for mutual separation of U and TRU with a reduction-complexation reaction. 2. Development of extraction system for high-acidity co-separation of An(+3) and Ln(+3) and its radiolytic evaluation. 3. Synthesis of extractants for the selective separation of An(+3) and its relevant extraction system development. 4. Development of a hybrid system for the recovery of noble metals and its continuous separation tests. 5. Development of electrolytic system for the decompositions of N-NO3 and N-NH3 compounds to nitrogen gas. 2). For the application test of pre-developed partitioning technologies for the separation of actinide elements in a simulated multi-component solution equivalent to HLW level. 1. Co-separation of Tc, Np and U by a (TBP-TOA)/NDD system. 2. Mutual-separation of Am, Cm and RE elements by a (Zr-DEHPA)/NDD system. All results will be used as the fundamental data for the development of advanced partitioning process in the future.

Learning in renewable energy technology development

International Nuclear Information System (INIS)

Junginger, M.

2005-01-01

The main objectives of this thesis are: to investigate technological change and cost reduction for a number of renewable electricity technologies by means of the experience curve approach; to address related methodological issues in the experience curve approach, and, based on these insights; and to analyze the implications for achieving the Dutch renewable electricity targets for the year 2020 within a European context. In order to meet these objectives, a number of research questions have been formulated: What are the most promising renewable electricity technologies for the Netherlands until 2020 under different technological, economic and environmental conditions?; To what extent is the current use of the experience curve approach to investigate renewable energy technology development sound, what are differences in the utilization of this approach and what are possible pitfalls?; How can the experience curve approach be used to describe the potential development of partially new energy technologies, such as offshore wind energy? Is it possible to describe biomass fuel supply chains with experience curves? What are the possibilities and limits of the experience curve approach when describing non-modular technologies such as large (biomass) energy plants?; What are the main learning mechanisms behind the cost reduction of the investigated technologies?; and How can differences in the technological progress of renewable electricity options influence the market diffusion of renewable electricity technologies, and what implications can varying technological development and policy have on the implementation of renewable electricity technologies in the Netherlands? The development of different renewable energy technologies is investigated by means of some case studies. The possible effects of varying technological development in combination with different policy backgrounds are illustrated for the Netherlands. The thesis focuses mainly on the development of investment

Technology development for radiation shielding analysis

International Nuclear Information System (INIS)

Ha, Jung Woo; Lee, Jae Kee; Kim, Jong Kyung

1986-12-01

Radiation shielding analysis in nuclear engineering fields is an important technology which is needed for the calculation of reactor shielding as well as radiation related safety problems in nuclear facilities. Moreover, the design technology required in high level radioactive waste management and disposal facilities is faced on serious problems with rapidly glowing nuclear industry development, and more advanced technology has to be developed for tomorrow. The main purpose of this study is therefore to build up the self supporting ability of technology development for the radiation shielding analysis in order to achieve successive development of nuclear industry. It is concluded that basic shielding calculations are possible to handle and analyze by using our current technology, but more advanced technology is still needed and has to be learned for the degree of accuracy in two-dimensional shielding calculation. (Author)

Robotics Technology Development Program Cross Cutting and Advanced Technology

International Nuclear Information System (INIS)

Harrigan, R.W.; Horschel, D.S.

1994-01-01

Need-based cross cutting technology is being developed which is broadly applicable to the clean up of hazardous and radioactive waste within the US Department of Energy's complex. Highly modular, reusable technologies which plug into integrated system architectures to meet specific robotic needs result from this research. In addition, advanced technologies which significantly extend current capabilities such as automated planning and sensor-based control in unstructured environments for remote system operation are also being developed and rapidly integrated into operating systems

Advanced safeguards research and development plan with an emphasis on its impact on nuclear power-plant design

International Nuclear Information System (INIS)

Tobin, S.J.; Demuth, S.F.; Miller, M.C.; Swinhoe, M.T.; Thomas, K.E.

2007-01-01

One tool for reducing the concern of nuclear proliferation is enhanced safeguards. Present safeguards have evolved over the past 40 years, and future safeguards will grow from this strong base to implement new technologies for improving our ability to quantify nuclear material. This paper will give an overview of the advanced technology research and development plan for safeguarding. One of the research facilities planned by the Department of Energy is the Advanced Fuel Cycle Facility (AFCF), to develop a novel nuclear fuel recycling program. Since the Advanced Fuel Cycle Facility will receive and reprocess spent fuel and will fabricate fast-reactor fuel, a wide breadth of safeguards technologies is involved. A fundamental concept in safeguards is material control and accounting (MCA). 4 topics concerning MCA and requiring further research have been identified: 1) measuring spent fuel, 2) measuring the plutonium content in the electro-refiner with pyro-processing, 3) measuring plutonium in the presence of other actinides, and 4) measuring neptunium and americium in the presence of other actinides. As for the long-term research and development plan for the AFCF, it will include improving MCA techniques as well as introducing new techniques that are not related to MCA, for example, enhanced containment and surveillance, or enhanced process monitoring. The top priority will stay quantifying the plutonium as accurately as possible and to reach this purpose 4 relevant technologies have been identified: 1) the microcalorimeter, 2) the passive neutron-albedo reactivity, 3) list-mode data acquisition, and 4) a liquid-scintillator multiplicity counter. Incorporating safeguards into the initial design of AFCF (safeguards by design) is a central concept. As the technology research and development plan for the Advanced Fuel Cycle Facility is examined, particular attention will be given to safeguards technologies that may affect the physical design of nuclear power plants

Technology Development Roadmap: A Technology Development Roadmap for a Future Gravitational Wave Mission

Science.gov (United States)

Camp, Jordan; Conklin, John; Livas, Jeffrey; Klipstein, William; McKenzie, Kirk; Mueller, Guido; Mueller, Juergen; Thorpe, James Ira; Arsenovic, Peter; Baker, John;

Tailings technology. Decommissioning and rehabilitation remedial action technology development

International Nuclear Information System (INIS)

Ramsey, R.W. Jr.

1982-01-01

This paper is to provide an overview of technology requirements for long-term uranium mill tailings disposal and remedial actions for existing tailings to ensure their adequate disposal. The paper examines the scientific disciplines that are the basis for the technology of uranium mill tailings stabilization and the design of barriers to control radiological exposure or environmental degradation at the location of tailings disposal. The discussion is presented as a hypothetical course of instruction at a fictitious university. Features of six mechanisms of dispersal or intrusion are examined with brief discussion of the applicable technology development for each. The paper serves as an introduction to subsequent specific technology development papers in the session. (author)

How does technological regime affect performance of technology development projects?

NARCIS (Netherlands)

Song, Michael; Hooshangi, Soheil; Zhao, Y. Lisa; Halman, Johannes I.M.

2014-01-01

In this study, we examine how technological regime affects the performance of technology development projects (i.e., project quality, sales, and profit). Technological regime is defined as the set of attributes of a technological environment where the innovative activities of firms take place.

Development of Food Preservation and Processing Technologies by Radiation Technology

International Nuclear Information System (INIS)

Byun, Myung Woo; Lee, Ju Won; Kim, Jae Hun

2007-07-01

To secure national food resources, development of energy-saving food processing and preservation technologies, establishment of method on improvement of national health and safety by development of alternative techniques of chemicals and foundation of the production of hygienic food and public health related products by irradiation technology were studied. Results at current stage are following: As the first cooperative venture business technically invested by National Atomic Research Development Project, institute/company's [technology-invested technology foundation No. 1] cooperative venture, Sun-BioTech Ltd., was founded and stated its business. This suggested new model for commercialization and industrialization of the research product by nation-found institute. From the notice of newly approved product list about irradiated food, radiation health related legal approval on 7 food items was achieved from the Ministry of health and wellfare, the Korea Food and Drug Administration, and this contributed the foundation of enlargement of practical use of irradiated food. As one of the foundation project for activation of radiation application technology for the sanitation and secure preservation of special food, such as military meal service, food service for patient, and food for sports, and instant food, such as ready-to-eat/ready-to-cook food, the proposal for radiation application to the major military commander at the Ministry of National Defence and the Joint Chiefs of Staff was accepted for the direction of military supply development in mid-termed plan for the development of war supply. Especially, through the preliminary research and the development of foundation technology for the development of the Korean style space food and functional space food, space Kimch with very long shelf life was finally developed. The development of new item/products for food and life science by combining RT/BT, the development of technology for the elimination/reduction of

Development of Food Preservation and Processing Technologies by Radiation Technology

Energy Technology Data Exchange (ETDEWEB)

Byun, Myung Woo; Lee, Ju Won; Kim, Jae Hun [and others

2007-07-15

To secure national food resources, development of energy-saving food processing and preservation technologies, establishment of method on improvement of national health and safety by development of alternative techniques of chemicals and foundation of the production of hygienic food and public health related products by irradiation technology were studied. Results at current stage are following: As the first cooperative venture business technically invested by National Atomic Research Development Project, institute/company's [technology-invested technology foundation No. 1] cooperative venture, Sun-BioTech Ltd., was founded and stated its business. This suggested new model for commercialization and industrialization of the research product by nation-found institute. From the notice of newly approved product list about irradiated food, radiation health related legal approval on 7 food items was achieved from the Ministry of health and wellfare, the Korea Food and Drug Administration, and this contributed the foundation of enlargement of practical use of irradiated food. As one of the foundation project for activation of radiation application technology for the sanitation and secure preservation of special food, such as military meal service, food service for patient, and food for sports, and instant food, such as ready-to-eat/ready-to-cook food, the proposal for radiation application to the major military commander at the Ministry of National Defence and the Joint Chiefs of Staff was accepted for the direction of military supply development in mid-termed plan for the development of war supply. Especially, through the preliminary research and the development of foundation technology for the development of the Korean style space food and functional space food, space Kimch with very long shelf life was finally developed. The development of new item/products for food and life science by combining RT/BT, the development of technology for the elimination/reduction of

Development of Food Preservation and Processing Technologies by Radiation Technology

Energy Technology Data Exchange (ETDEWEB)

Byun, Myung Woo; Lee, Ju Won; Kim, Jae Hun (and others)

2007-07-15

To secure national food resources, development of energy-saving food processing and preservation technologies, establishment of method on improvement of national health and safety by development of alternative techniques of chemicals and foundation of the production of hygienic food and public health related products by irradiation technology were studied. Results at current stage are following: As the first cooperative venture business technically invested by National Atomic Research Development Project, institute/company's [technology-invested technology foundation No. 1] cooperative venture, Sun-BioTech Ltd., was founded and stated its business. This suggested new model for commercialization and industrialization of the research product by nation-found institute. From the notice of newly approved product list about irradiated food, radiation health related legal approval on 7 food items was achieved from the Ministry of health and wellfare, the Korea Food and Drug Administration, and this contributed the foundation of enlargement of practical use of irradiated food. As one of the foundation project for activation of radiation application technology for the sanitation and secure preservation of special food, such as military meal service, food service for patient, and food for sports, and instant food, such as ready-to-eat/ready-to-cook food, the proposal for radiation application to the major military commander at the Ministry of National Defence and the Joint Chiefs of Staff was accepted for the direction of military supply development in mid-termed plan for the development of war supply. Especially, through the preliminary research and the development of foundation technology for the development of the Korean style space food and functional space food, space Kimch with very long shelf life was finally developed. The development of new item/products for food and life science by combining RT/BT, the development of technology for the elimination/reduction of

Robotics Technology Development Program

International Nuclear Information System (INIS)

1994-02-01

The Robotics Technology Development Program (RTDP) is a ''needs-driven'' effort. A lengthy series of presentations and discussions at DOE sites considered critical to DOE's Environmental Restoration and Waste Management (EM) Programs resulted in a clear understanding of needed robotics applications toward resolving definitive problems at the sites. A detailed analysis of the Tank Waste Retrieval (TWR), Contaminant Analysis Automation (CAA), Mixed Waste Operations (MWO), and Decontamination ampersand Dismantlement (D ampersand D). The RTDP Group realized that much of the technology development was common (Cross Cutting-CC) to each of these robotics application areas, for example, computer control and sensor interface protocols. Further, the OTD approach to the Research, Development, Demonstration, Testing, and Evaluation (RDDT ampersand E) process urged an additional organizational break-out between short-term (1--3 years) and long-term (3--5 years) efforts (Advanced Technology-AT). The RDTP is thus organized around these application areas -- TWR, CAA, MWO, D ampersand D and CC ampersand AT -- with the first four developing short-term applied robotics. An RTDP Five-Year Plan was developed for organizing the Program to meet the needs in these application areas

ECH Technology Development

Energy Technology Data Exchange (ETDEWEB)

Temkin, Richard [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

2014-12-24

Electron Cyclotron Heating (ECH) is needed for plasma heating, current drive, plasma stability control, and other applications in fusion energy sciences research. The program of fusion energy sciences supported by U. S. DOE, Office of Science, Fusion Energy Sciences relies on the development of ECH technology to meet the needs of several plasma devices working at the frontier of fusion energy sciences research. The largest operating ECH system in the world is at DIII-D, consisting of six 1 MW, 110 GHz gyrotrons capable of ten second pulsed operation, plus two newer gyrotrons. The ECH Technology Development research program investigated the options for upgrading the DIII-D 110 GHz ECH system. Options included extending present-day 1 MW technology to 1.3 – 1.5 MW power levels or developing an entirely new approach to achieve up to 2 MW of power per gyrotron. The research consisted of theoretical research and designs conducted by Communication and Power Industries of Palo Alto, CA working with MIT. Results of the study would be validated in a later phase by research on short pulse length gyrotrons at MIT and long pulse / cw gyrotrons in industry. This research follows a highly successful program of development that has led to the highly reliable, six megawatt ECH system at the DIII-D tokamak. Eventually, gyrotrons at the 1.5 megawatt to multi-megawatt power level will be needed for heating and current drive in large scale plasmas including ITER and DEMO.

Policy issues inherent in advanced technology development

Energy Technology Data Exchange (ETDEWEB)

Baumann, P.D.

1994-12-31

In the development of advanced technologies, there are several forces which are involved in the success of the development of those technologies. In the overall development of new technologies, a sufficient number of these forces must be present and working in order to have a successful opportunity at developing, introducing and integrating into the marketplace a new technology. This paper discusses some of these forces and how they enter into the equation for success in advanced technology research, development, demonstration, commercialization and deployment. This paper limits itself to programs which are generally governmental funded, which in essence represent most of the technology development efforts that provide defense, energy and environmental technological products. Along with the identification of these forces are some suggestions as to how changes may be brought about to better ensure success in a long term to attempt to minimize time and financial losses.

Policy issues inherent in advanced technology development

International Nuclear Information System (INIS)

Baumann, P.D.

1994-01-01

In the development of advanced technologies, there are several forces which are involved in the success of the development of those technologies. In the overall development of new technologies, a sufficient number of these forces must be present and working in order to have a successful opportunity at developing, introducing and integrating into the marketplace a new technology. This paper discusses some of these forces and how they enter into the equation for success in advanced technology research, development, demonstration, commercialization and deployment. This paper limits itself to programs which are generally governmental funded, which in essence represent most of the technology development efforts that provide defense, energy and environmental technological products. Along with the identification of these forces are some suggestions as to how changes may be brought about to better ensure success in a long term to attempt to minimize time and financial losses

Calcium-borosilicate glass-ceramics wasteforms to immobilize rare-earth oxide wastes from pyro-processing

Energy Technology Data Exchange (ETDEWEB)

Kim, Miae [Department of Materials Science and Engineering and Division of Advanced Nuclear Engineering, Pohang University of Science and Technology (POSTECH), Pohang, Gyeongbuk, 790-784 (Korea, Republic of); Heo, Jong, E-mail: jheo@postech.ac.kr [Department of Materials Science and Engineering and Division of Advanced Nuclear Engineering, Pohang University of Science and Technology (POSTECH), Pohang, Gyeongbuk, 790-784 (Korea, Republic of); Department of Materials Engineering, Adama Science and Technology University (ASTU), PO Box 1888, Adama (Ethiopia)

2015-12-15

Glass-ceramics containing calcium neodymium(cerium) oxide silicate [Ca{sub 2}Nd{sub 8-x}Ce{sub x}(SiO{sub 4}){sub 6}O{sub 2}] crystals were fabricated for the immobilization of radioactive wastes that contain large portions of rare-earth ions. Controlled crystallization of alkali borosilicate glasses by heating at T ≥ 750 °C for 3 h formed hexagonal Ca–silicate crystals. Maximum lanthanide oxide waste loading was >26.8 wt.%. Ce and Nd ions were highly partitioned inside Ca–silicate crystals compared to the glass matrix; the rare-earth wastes are efficiently immobilized inside the crystalline phases. The concentrations of Ce and Nd ions released in a material characterization center-type 1 test were below the detection limit (0.1 ppb) of inductively coupled plasma mass spectroscopy. Normalized release values performed by a product consistency test were 2.64·10{sup −6} g m{sup −2} for Ce ion and 2.19·10{sup −6} g m{sup −2} for Nd ion. Results suggest that glass-ceramics containing calcium neodymium(cerium) silicate crystals are good candidate wasteforms for immobilization of lanthanide wastes generated by pyro-processing. - Highlights: • Glass-ceramic wasteforms containing Ca{sub 2}Nd{sub 8-x}Ce{sub x}(SiO{sub 4}){sub 6}O{sub 2} crystals were synthesized to immobilize lanthanide wastes. • Maximum lanthanide oxide waste loading was >26.8 wt.%. • Ce and Nd ions were highly partitioned inside Ca–Nd–silicate crystals compared to glass matrix. • Amounts of Ce and Nd ions released in the material characterization center-type 1 were below the detection limit (0.1 ppb). • Normalized release values performed by a PCT were 2.64• 10{sup −6} g m{sup −2} for Ce ions and 2.19• 10{sup −6} g m{sup −2} for Nd ions.

Working Environment and Technological Development

DEFF Research Database (Denmark)

Clausen, Christian; Nielsen, Klaus T.; Jensen, Per Langaa

1997-01-01

and their and their concept of working environment2) Technology renewal, which considers the role of the working environment in connection with the development and use of concrete technologies3) Working environment planning, which considers the existing efforts to place the working environment in a planning process.......The paper describes the purpose, themes, overarching research questions and specific projects of the programme: Working Environment and Technological Development. The major research themes are:1) Management concepts and the working environment, which considers the visions...

Engineering research, development and technology

International Nuclear Information System (INIS)

1994-05-01

The mission of the Engineering Research, Development, and Technology Program at Lawrence Livermore National Laboratory (LLNL) is to develop the technical staff, tools, and facilities needed to support current and future LLNL programs. The efforts are guided by a dual-benefit research and development strategy that supports Department of Energy missions, such as national security through nuclear deterrence and economic competitiveness through partnerships with U.S. industry. This annual report, organized by thrust area, describes the activities for the fiscal year 1993. The report provides timely summaries of objectives, methods, and results from nine thrust areas for this fiscal year: Computational Electronics and Electromagnetics; Computational Mechanics; Diagnostics and Microelectronics; Fabrication Technology; Materials Science and Engineering; Power Conversion Technologies; Nondestructive Evaluation; Remote Sensing, Imaging, and Signal Engineering; and Emerging Technologies. Separate abstracts were prepared for 47 papers in this report

Technology Development: From Idea to Implementation - 12131

Energy Technology Data Exchange (ETDEWEB)

Spires, Renee H. [Savannah River Remediation (United States)

2012-07-01

There are good ideas and new technologies proposed every day to solve problems within the DOE complex. A process to transition a new technology from inception to the decision to launch a project with baselines is described. Examples from active technology development projects within Savannah River Remediation (SRR) will be used to illustrate the points. The process includes decision points at key junctures leading to preliminary design. At that point, normal project management tools can be employed. The technology development steps include proof-of-principle testing, scaled testing and analysis, and conceptual design. Tools are used that define the scope necessary for each step of technology development. The tools include use of the DOE technology readiness guide, Consolidated Hazards Analysis (CHA) and internal checklists developed by Savannah River Remediation. Integration with operating or planned facilities is also included. The result is a roadmap and spreadsheet that identifies each open question and how it may be answered. Performance criteria are developed that enable simple decisions to be made after the completion of each step. Conceptual design tasks should begin as the technology development continues. The most important conceptual design tasks at this point in the process include process flow diagrams (PFDs), high level Process and Instrumentation Drawings (P and IDs), and general layout drawings. These should influence the design of the scaled simulant testing. Mechanical and electrical drawings that support cost and schedule development should also be developed. An early safety control strategy developed from the CHA will also influence the cost. The combination of test results, calculations and early design output with rough order of magnitude cost and schedule information provide input into the decisions to proceed with a project and data to establish the baseline. This process can be used to mature any new technology, especially those that must be

Development of clean environment conservation technology by radiation

International Nuclear Information System (INIS)

Lee, Myunjoo; Kim, Tak Hyun; Jung, In Ha

2012-04-01

This report is aim to develop the technology for environmental conservation by radiation. It is consisted of two research parts. One is development of wastewater disinfection technology by radiation and the other is development of livestock waste treatment technology by radiation. For the development of wastewater disinfection technology disinfect ion process, technology for treatment of toxic organic chemicals and assessment of ecological toxicity, technology for treatment of endocrine disrupting chemicals and assessment of genetic safety were developed. For the development of livestock waste treatment technology, process for simultaneous removal of nutrients, technology for disinfection and quality enhancement of livestock waste compost, technology for reduction of composting periods, monitoring of toxic organic compounds, pretreatment technology for organic toxic chemicals and enhancement of biological treatment efficiencies were developed. Based on basic research, advanced livestock wastewater treatment process using radiation was established

Science and Technology and Economic Development

OpenAIRE

Lamberte, Mario B.

1988-01-01

Dealing with science and technology and economic development, this paper describes the relationship between technological capability and the degree of economic development. It analyzes the structure of the Philippine economy and the structural changes that have taken place since the 1970. It also investigates the impact of economic developments and technological advances in other countries on the Philippine economy. A discussion on possible research collaboration among PIDS, DOST and regional...

Status of irradiation technology development in JMTR

International Nuclear Information System (INIS)

Inaba, Y.; Inoue, S.; Izumo, H.; Kitagishi, S.; Tsuchiya, K.; Saito, T.; Ishitsuka, E.

2008-01-01

Irradiation Engineering Section of the Neutron Irradiation and Testing Reactor Centre was organised to development the new irradiation technology for the application at JMTR re-operation. The new irradiation engineering building was remoulded from the old RI development building, and was started to use from the end of September, 2008. Advanced in-situ instrumentation technology(high temperature multi-paired thermocouple, ceramic sensor,application of optical measurement), 99 Mo production technology by new Mo solution irradiation method,recycling technology on used beryllium reflector, and so on are planned as the development of new irradiation technologies. The development will be also important for the education and training programs through the development of young generation in not only Japan but also Asian countries. In this report, as the status of the development the new irradiation technology, new irradiation engineering building, high temperature multi-paired thermocouple, experiences of optical measurement, recycling technology on used beryllium reflector are introduced

Status of Irradiation technology development in JMTR

International Nuclear Information System (INIS)

Inaba, Y.; Inoue, S.; Izumo, H.; Kitagishi, S.; Tsuchiya, K.; Saito, T.; Ishitsuka, E.

2008-01-01

Irradiation Engineering Section of the Neutron Irradiation and Testing Reactor Center was organized to development the new irradiation technology for the application at JMTR re operation. The new irradiation engineering building was remodeled from the old RI development building, and was started to use from the end of September, 2008. Advanced in situ instrumentation technology (high temperature multi paired thermocouple, ceramic sensor, application of optical measurement), 99M o production technology by new Mo solution irradiation method, recycling technology on used beryllium reflector, and so on are planned as the development of new irradiation technologies. The development will be also important for the education and training programs through the development of young generation in not only Japan but also Asian counties. In this report, as the status of the development the new irradiation technology, new irradiation engineering building, high temperature multi paired thermocouple, experiences of optical measurement, recycling technology on used beryllium reflector are introduced

Safety Parameters for the Recycled Uranium Loaded into a CANDU Reactor

International Nuclear Information System (INIS)

Park, Chang Je; Kang, Kweon Ho; Na, Sang Ho; Kim, Young Hee; Ryu, Ho Jin; Park, Geun Il; Song, Kee Chan

2008-01-01

In order to recover uranium and TRU from spent nuclear fuels, a pyroprocessing has been developed through a dry and metallurgical reprocess technology using a series of electrolyses such as an electro-reduction, an electro-refining, and an electro-winning. When the spent fuel is being fed into the pyroprocess, most of the uranium is gathered in metallic form around a solid cathode during an electro-refining process. It is expected that the recovered uranium will be sent to a spent fuel storage site after converting it into a metal ingot form to reduce its storage space and transportation burden. However, the weight percent of U-235 in the recovered uranium is about 0.9 wt% and it is sufficiently re-utilized in a heavy water reactor which uses a natural uranium fuel. The reuse of recovered uranium will bring not only a huge economical profit and save of uranium resources but also an alleviation of burden on the management and disposal of the spent fuel. A previous research on recycling of recovered uranium was carried out and most of the recovered uranium was assumed to be imported from abroad at that time. The preliminary results showed there is a sufficient possibility to recycle recovered uranium in terms of a reactor's characteristics as well as the fuel performance. And the DUPIC (direct use of spent pressurized water reactor fuel into CANDU reactor) program has also been performed and demonstrated the fundamental technologies. The recovered uranium from a pyroprocess contains some TRU as an impurity and it will exhibit a slightly different behavior from the previous recycling options. In this paper, the reactor's characteristics including safety parameters are investigated based on the lattice calculations which are performed for the CANFELX bundle

Lunar Surface Systems Supportability Technology Development Roadmap

Science.gov (United States)

Oeftering, Richard C.; Struk, Peter M.; Green, Jennifer L.; Chau, Savio N.; Curell, Philip C.; Dempsey, Cathy A.; Patterson, Linda P.; Robbins, William; Steele, Michael A.; DAnnunzio, Anthony;

Advanced Mirror & Modelling Technology Development

Science.gov (United States)

Effinger, Michael; Stahl, H. Philip; Abplanalp, Laura; Maffett, Steven; Egerman, Robert; Eng, Ron; Arnold, William; Mosier, Gary; Blaurock, Carl

2014-01-01

The 2020 Decadal technology survey is starting in 2018. Technology on the shelf at that time will help guide selection to future low risk and low cost missions. The Advanced Mirror Technology Development (AMTD) team has identified development priorities based on science goals and engineering requirements for Ultraviolet Optical near-Infrared (UVOIR) missions in order to contribute to the selection process. One key development identified was lightweight mirror fabrication and testing. A monolithic, stacked, deep core mirror was fused and replicated twice to achieve the desired radius of curvature. It was subsequently successfully polished and tested. A recently awarded second phase to the AMTD project will develop larger mirrors to demonstrate the lateral scaling of the deep core mirror technology. Another key development was rapid modeling for the mirror. One model focused on generating optical and structural model results in minutes instead of months. Many variables could be accounted for regarding the core, face plate and back structure details. A portion of a spacecraft model was also developed. The spacecraft model incorporated direct integration to transform optical path difference to Point Spread Function (PSF) and between PSF to modulation transfer function. The second phase to the project will take the results of the rapid mirror modeler and integrate them into the rapid spacecraft modeler.

Development of technologies for solar energy utilization

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

With relation to the development of photovoltaic power systems for practical use, studies were made on thin-substrate polycrystalline solar cells and thin-film solar cells as manufacturing technology for solar cells for practical use. The technological development for super-high efficiency solar cells was also being advanced. Besides, the research and development have been conducted of evaluation technology for photovoltaic power systems and systems to utilize the photovoltaic power generation and peripheral technologies. The demonstrative research on photovoltaic power systems was continued. The international cooperative research on photovoltaic power systems was also made. The development of a manufacturing system for compound semiconductors for solar cells was carried out. As to the development of solar energy system technologies for industrial use, a study of elemental technologies was first made, and next the development of an advanced heat process type solar energy system was commenced. In addition, the research on passive solar systems was made. An investigational study was carried out of technologies for solar cities and solar energy snow melting systems. As international joint projects, studies were made of solar heat timber/cacao drying plants, etc. The paper also commented on projects for international cooperation for the technological development of solar energy utilization systems. 26 figs., 15 tabs.

Development of decontamination, decommissioning and environmental restoration technology

Energy Technology Data Exchange (ETDEWEB)

Lee, Byung Jik; Kwon, H S; Kim, G N. and others

1999-03-01

Through the project of 'Development of decontamination, decommissioning and environmental restoration technology', the followings were studied. 1. Development of decontamination and repair technology for nuclear fuel cycle facilities 2. Development of dismantling technology 3. Development of environmental restoration technology. (author)

Fusion development and technology

International Nuclear Information System (INIS)

Montgomery, D.B.

1991-01-01

This report discusses the following topics: superconducting magnet technology high field superconductors; advanced magnetic system and divertor development; poloidal field coils; gyrotron development; commercial reactor studies -- Aries; ITER physics; ITER superconducting PF scenario and magnet analysis; and safety, environmental and economic factors in fusion development

Development of decontamination, decommissioning and environmental restoration technology

Energy Technology Data Exchange (ETDEWEB)

Lee, Byung Jik; Kwon, H. S.; Kim, G. N. and others

1999-03-01

Through the project of 'Development of decontamination, decommissioning and environmental restoration technology', the followings were studied. 1. Development of decontamination and repair technology for nuclear fuel cycle facilities 2. Development of dismantling technology 3. Development of environmental restoration technology. (author)

Technology development life cycle processes.

Energy Technology Data Exchange (ETDEWEB)

Beck, David Franklin

2013-05-01

This report and set of appendices are a collection of memoranda originally drafted in 2009 for the purpose of providing motivation and the necessary background material to support the definition and integration of engineering and management processes related to technology development. At the time there was interest and support to move from Capability Maturity Model Integration (CMMI) Level One (ad hoc processes) to Level Three. As presented herein, the material begins with a survey of open literature perspectives on technology development life cycles, including published data on %E2%80%9Cwhat went wrong.%E2%80%9D The main thrust of the material presents a rational expose%CC%81 of a structured technology development life cycle that uses the scientific method as a framework, with further rigor added from adapting relevant portions of the systems engineering process. The material concludes with a discussion on the use of multiple measures to assess technology maturity, including consideration of the viewpoint of potential users.

Development of fabrication technology for ceramic nuclear fuel

International Nuclear Information System (INIS)

Lee, Young Woo; Sohn, D. S.; Na, S. H.

2003-05-01

The purpose of the study is to develop the fabrication technology of MOX fuel. The researches carried out during the last stage(1997. 4.∼2003. 3.) mainly consisted of ; study of MOX pellet fabrication technology for application and development of characterization technology for the aim of confirming the development of powder treatment technology and sintering technology and of the optimization of the above technologies and fabrication of Pu-MOX pellet specimens through an international joint collaboration between KAERI and PSI based on the fundamental technologies developed in KAERI. Based on the studies carried out and the results obtained during the last stage, more extensive studies for the process technologies of the unit processes were performed, in this year, for the purpose of development of indigenous overall MOX pellet fabrication process technology, relating process parameters among the unit processes and integrating these unit process technologies. Furthermore, for the preparation of transfer of relevant technologies to the industries, a feasibility study was performed on the commercialization of the technology developed in KAERI with the relevant industry in close collaboration

Radioactive Dry Process Material Treatment Technology Development

Energy Technology Data Exchange (ETDEWEB)

Park, J. J.; Hung, I. H.; Kim, K. K. (and others)

2007-06-15

The project 'Radioactive Dry Process Material Treatment Technology Development' aims to be normal operation for the experiments at DUPIC fuel development facility (DFDF) and safe operation of the facility through the technology developments such as remote operation, maintenance and pair of the facility, treatment of various high level process wastes and trapping of volatile process gases. DUPIC Fuel Development Facility (DFDF) can accommodate highly active nuclear materials, and now it is for fabrication of the oxide fuel by dry process characterizing the proliferation resistance. During the second stage from march 2005 to February 2007, we carried out technology development of the remote maintenance and the DFDF's safe operation, development of treatment technology for process off-gas, and development of treatment technology for PWR cladding hull and the results was described in this report.

Clean Technology Evaluation & Workforce Development Program

Energy Technology Data Exchange (ETDEWEB)

Patricia Glaza

2012-12-01

The overall objective of the Clean Technology Evaluation portion of the award was to design a process to speed up the identification of new clean energy technologies and match organizations to testing and early adoption partners. The project was successful in identifying new technologies targeted to utilities and utility technology integrators, in developing a process to review and rank the new technologies, and in facilitating new partnerships for technology testing and adoption. The purpose of the Workforce Development portion of the award was to create an education outreach program for middle & high-school students focused on clean technology science and engineering. While originally targeting San Diego, California and Cambridge, Massachusetts, the scope of the program was expanded to include a major clean technology speaking series and expo as part of the USA Science & Engineering Festival on the National Mall in Washington, D.C.

Technology transfer and development: a preliminary look at Chinese technology in Guyana

Energy Technology Data Exchange (ETDEWEB)

Long, F

1982-05-01

Technology is regarded as a vital ingredient for development. Since developing countries can hardly fill their technological requirements indigenously, such countries tend to acquire the bulk of technology applied to their production systems from abroad. However, the transfer of technology tends to be associated with a series of problems: foreign exchange, inappropriateness, the generation of limited inter-sectorial linkages, limited use of raw materials, and other inputs associated with technology dependency. The study points to the fact that technology transfer need not necessarily be associated with the disadvantages identified in the literature. The study which essentially looks at the use of Chinese technology in clay-brick manufacturing in Guyana, shows that the country was able to reap several development benefits from the technology-transfer arrangement. At the same time, certain problems arising from the technology-transfer package such as the transfer of critical skills in key areas of production, and maintenance and servicing, are discussed. But these, the author argues, are not a function of restrictive conditions found in technology-transfer clauses, but rather of improper technology-transfer management. 2 tables.

Technology certification and technology acceptance: Promoting interstate cooperation and market development for innovative technologies

International Nuclear Information System (INIS)

Brockbank, B.R.

1995-03-01

In the past two years, public and private efforts to promote development and deployment of innovative environmental technologies have shifted from the analysis of barriers to the implementation of a variety of initiatives aimed at surmounting those barriers. Particular attention has been directed at (1) streamlining fragmented technology acceptance processes within and among the states, and (2) alleviating disincentives, created by inadequate or unverified technology cost and performance data, for users and regulators to choose innovative technologies. Market fragmentation currently imposes significant cost burdens on technology developers and inhibits the investment of private capital in environmental technology companies. Among the responses to these problems are state and federal technology certification/validation programs, efforts to standardize cost/performance data reporting, and initiatives aimed at promoting interstate cooperation in technology testing and evaluation. This paper reviews the current status of these initiatives, identifies critical challenges to their success, and recommends strategies for addressing those challenges

Mixed Waste Integrated Program emerging technology development

International Nuclear Information System (INIS)

Berry, J.B.; Hart, P.W.

1994-01-01

The US Department of Energy (DOE) is responsible for the management and treatment of its mixed low-level wastes (MLLW). MLLW are regulated under both the Resource Conservation and Recovery Act and various DOE orders. Over the next 5 years, DOE will manage over 1.2 m 3 of MLLW and mixed transuranic (MTRU) wastes. In order to successfully manage and treat these mixed wastes, DOE must adapt and develop characterization, treatment, and disposal technologies which will meet performance criteria, regulatory approvals, and public acceptance. Although technology to treat MLLW is not currently available without modification, DOE is committed to developing such treatment technologies and demonstrating them at the field scale by FY 1997. The Office of Research and Development's Mixed Waste Integrated Program (MWIP) within the DOE Office of Environmental Management (EM), OfFice of Technology Development, is responsible for the development and demonstration of such technologies for MLLW and MTRU wastes. MWIP advocates and sponsors expedited technology development and demonstrations for the treatment of MLLW

Development of ultrasensitive spectroscopic analysis technology

International Nuclear Information System (INIS)

Cha, Hyung Ki; Song, K. S.; Kim, D. H.; Yang, K. H.; Jung, E. C.; Jeong, D. Y.; Yi, Y. J.; Lee, S. M.; Hong, K. H.; Han, J. M.; Yoo, B. D.; Rho, S. P.; Yi, J. H.; Park, H. M.; Cha, B. H.; Nam, S. M.; Lee, J. M.

1997-09-01

For the development of the laser initiated high resolution, ultra sensitive analysis technology following field of researches have been performed. 1) Laser resonance ionization technology, 2) Laser-induced rare isotope detection technology, 3) Laser-induced plasma analysis technology, 4) Microparticle analysis technology by using ion trap, 5) Laser induced remote sensing technique. As a result a monitoring system for photoionized product is developed and the test of system is performed with Sm sample. The rare isotope detection system is designed and a few key elements of the system are developed. In addition a laser-induced plasma analysis system is developed and samples such as Zircaloy, Zinc-base alloy, rock samples are reasonably analyzed. The detection sensitivity is identified as good as a few ppm order. An ion trap is developed and microparticles such as SiC are trapped inside the trap by ac and dc fields. The fluorescence signals from the organic dyes as well as rare earth element which are absorbed on the microparticles are detected. Several calibration curves are also obtained. In the field of laser remote sensing a mobile Lidar system is designed and several key elements are developed. In addition the developed system is used for the detection of Ozone, NO 2 , SO 2 , etc. (author). 57 refs., 42 figs

Mixed Waste Integrated Program emerging technology development

Energy Technology Data Exchange (ETDEWEB)

Berry, J.B. [Oak Ridge National Lab., TN (United States); Hart, P.W. [USDOE, Washington, DC (United States)

1994-06-01

The US Department of Energy (DOE) is responsible for the management and treatment of its mixed low-level wastes (MLLW). MLLW are regulated under both the Resource Conservation and Recovery Act and various DOE orders. Over the next 5 years, DOE will manage over 1.2 m{sup 3} of MLLW and mixed transuranic (MTRU) wastes. In order to successfully manage and treat these mixed wastes, DOE must adapt and develop characterization, treatment, and disposal technologies which will meet performance criteria, regulatory approvals, and public acceptance. Although technology to treat MLLW is not currently available without modification, DOE is committed to developing such treatment technologies and demonstrating them at the field scale by FY 1997. The Office of Research and Development`s Mixed Waste Integrated Program (MWIP) within the DOE Office of Environmental Management (EM), OfFice of Technology Development, is responsible for the development and demonstration of such technologies for MLLW and MTRU wastes. MWIP advocates and sponsors expedited technology development and demonstrations for the treatment of MLLW.

Do Technological Developments and Financial Development Promote Economic Growth: Fresh Evidence from Romania

OpenAIRE

Ur Rehman, Ijaz; Shahbaz, Muhammad; Kyophilavong, Phouphet

2013-01-01

We study the relationship between financial development, technological development and economic growth in Romania. We construct aggregate indices of financial development and technological development using principal component analysis. The ARDL bounds testing approach shows the presence of cointegration between financial development, technological development and economic growth. Financial development and technological development contribute to economic growth. Moreover, financial developmen...

Ten Items of Integrated Technology Developed by CNPC

Institute of Scientific and Technical Information of China (English)

无

2006-01-01

@@ The technological work of China National Petroleum Corporation (CNPC) was based on the company's general development strategy to become a multinational giant with international competitiveness during the 10th FiveYear Plan Period (2001-2005). The technological efforts were focused on strengthening strategic management of technology to identify the technological development targets, optimizing allocation of technological resources and increasing technological investment to highlight creation of key technology. Aiming at the important and key technologies needed for main business development,CNPC launched 15 technological projects at the State level with a 100 percent completion rate and 379 other projects at the corporate level with a 92.8 percent completion rate. With a number of high-level results achieved, CNPC has developed 10 items of integrated technology.

KSC Education Technology Research and Development Plan

Science.gov (United States)

Odell, Michael R. L.

2003-01-01

Educational technology is facilitating new approaches to teaching and learning science, technology, engineering, and mathematics (STEM) education. Cognitive research is beginning to inform educators about how students learn providing a basis for design of more effective learning environments incorporating technology. At the same time, access to computers, the Internet and other technology tools are becoming common features in K-20 classrooms. Encouraged by these developments, STEM educators are transforming traditional STEM education into active learning environments that hold the promise of enhancing learning. This document illustrates the use of technology in STEM education today, identifies possible areas of development, links this development to the NASA Strategic Plan, and makes recommendations for the Kennedy Space Center (KSC) Education Office for consideration in the research, development, and design of new educational technologies and applications.

Safeguards and Security Technology Development Directory. FY 1993

Energy Technology Data Exchange (ETDEWEB)

1993-06-01

The Safeguards and Security Technology Development Directory is published annually by the Office of Safeguards and Security (OSS) of the US Department of Energy (DOE), and is Intended to inform recipients of the full scope of the OSS R&D program. It is distributed for use by DOE headquarters personnel, DOE program offices, DOE field offices, DOE operating contractors, national laboratories, other federal agencies, and foreign governments. Chapters 1 through 7 of the Directory provide general information regarding the Technology Development Program, including the mission, program description, organizational roles and responsibilities, technology development lifecycle, requirements analysis, program formulation, the task selection process, technology development infrastructure, technology transfer activities, and current research and development tasks. These chapters are followed by a series of appendices which contain more specific information on aspects of the Program. Appendix A is a summary of major technology development accomplishments made during FY 1992. Appendix B lists S&S technology development reports issued during FY 1992 which reflect work accomplished through the OSS Technology Development Program and other relevant activities outside the Program. Finally, Appendix C summarizes the individual task statements which comprise the FY 1993 Technology Development Program.

Development of alternative energy technologies. Entrepreneurs, new technologies, and social change

Energy Technology Data Exchange (ETDEWEB)

Burns, T R

1985-01-01

This paper discusses the introduction and development of several alternative energy technologies in countries where the innovation process has enjoyed some measure of success: solar water heating (California, Israel), windmills (Denmark), wood and peat for co-generation (Northern New England, Finland) and geo-thermal power (California) as well as heat pumps designed to save energy (West Germany). It is argued that the introduction and development of new technologies - and the socio-technical systems which utilize these technologies - depend on the initiatives of entrepreneurs and social change agents. They engage in adapting and matching technology and social structure (laws, institutions, norms, political and economic forces and social structure generally). Successful developments - as well as blocked or retarded developments - are discussed in terms of such ''compatibility analysis''. Policy implications are also discussed. (orig.).

Web Development Technology-PHP. How It Is Related To Web Development Technology ASP.NET

Directory of Open Access Journals (Sweden)

Manya Sharma

2015-01-01

Full Text Available ABSTRACT This paper tells about the technologies used in PHP and how they are related to ASP.NET. The paper begin with the introduction of PHP defining what and how technologies has been used in development of User Complaint Web Application. How thistechnology is related to ASP.NET in features such as implementation functionality validation and proactive behavior involved in validating user input from the browser providing users feedback overall time consumed in development and maintenance.

Development of decontamination, decommissioning and environmental restoration technology

International Nuclear Information System (INIS)

Lee, Byung Jik; Kwon, H. S.; Kim, G. N. and others

1999-03-01

Through the project of D evelopment of decontamination, decommissioning and environmental restoration technology , the followings were studied. 1. Development of decontamination and repair technology for nuclear fuel cycle facilities 2. Development of dismantling technology 3. Development of environmental restoration technology. (author)

Spent Nuclear Fuel Reprocessing Flowsheet. A Report by the WPFC Expert Group on Chemical Partitioning of the NEA Nuclear Science Committee

International Nuclear Information System (INIS)

Na, Chan; Yamagishi, Isao; Choi, Yong-Joon; Glatz, Jean-Paul; Hyland, Bronwyn; Uhlir, Jan; Baron, Pascal; Warin, Dominique; De Angelis, Giorgio; Luce, Alfredo; INOUE, Tadashi; Morita, Yasuji; Minato, Kazuo; Lee, Han Soo; Ignatiev, Victor V.; Kormilitsyn, Mikhail V.; Caravaca, Concepcion; Lewin, Robert G.; Taylor, Robin J.; Collins, Emory D.; Laidler, James J.

2012-06-01

Under the auspices of the NEA Nuclear Science Committee (NSC), the Working Party on Scientific Issues of the Fuel Cycle (WPFC) has been established to co-ordinate scientific activities regarding various existing and advanced nuclear fuel cycles, including advanced reactor systems, associated chemistry and flowsheets, development and performance of fuel and materials, and accelerators and spallation targets. The WPFC has different expert groups to cover a wide range of scientific fields in the nuclear fuel cycle. The Expert Group on Chemical Partitioning was created in 2001 to (1) perform a thorough technical assessment of separations processes in application to a broad set of partitioning and transmutation (P and T) operating scenarios and (2) identify important research, development and demonstration necessary to bring preferred technologies to a deployable stage and (3) recommend collaborative international efforts to further technological development. This report aims to collect spent nuclear fuel reprocessing flowsheet of various processes developed by member states: aqueous, pyro and fluoride volatility. Contents: 1 - Hydrometallurgy process: Standard PUREX, Extended PUREX, UREX+3, Grind/Leach; 2 - Pyrometallurgy process: pyro-process (CRIEPI - Japan), 4-group partitioning process, pyro-process (KAERI - Korea), Direct electrochemical processing of metallic fuel, PyroGreen (reduce radiotoxicity to the level of low and intermediate level waste - LILW); 3 - Fluoride volatility process: Fluoride volatility process, Uranium and protactinium removal from fuel salt compositions by fluorine bubbling, Flowsheet studies on non-aqueous reprocessing of LWR/FBR spent nuclear fuel; Appendix A: Flowsheet studies of RIAR (Russian Federation), List of contributors, Members of the expert group

Interactions of energy technology development and new energy exploitation with water technology development in China

International Nuclear Information System (INIS)

Liang, Sai; Zhang, Tianzhu

2011-01-01

Interactions of energy policies with water technology development in China are investigated using a hybrid input-output model and scenario analysis. The implementation of energy policies and water technology development can produce co-benefits for each other. Water saving potential of energy technology development is much larger than that of new energy exploitation. From the viewpoint of proportions of water saving co-benefits of energy policies, energy sectors benefit the most. From the viewpoint of proportions of energy saving and CO 2 mitigation co-benefits of water technology development, water sector benefits the most. Moreover, economic sectors are classified into four categories concerning co-benefits on water saving, energy saving and CO 2 mitigation. Sectors in categories 1 and 2 have big direct co-benefits. Thus, they can take additional responsibility for water and energy saving and CO 2 mitigation. If China implements life cycle materials management, sectors in category 3 can also take additional responsibility for water and energy saving and CO 2 mitigation. Sectors in category 4 have few co-benefits from both direct and accumulative perspectives. Thus, putting additional responsibility on sectors in category 4 might produce pressure for their economic development. -- Highlights: ► Energy policies and water technology development can produce co-benefits for each other. ► For proportions of water saving co-benefits of energy policies, energy sectors benefit the most. ► For proportions of energy saving and CO 2 mitigation co-benefits of water policy, water sector benefits the most. ► China’s economic sectors are classified into four categories for policy implementation at sector scale.

Innovative Technology Development Program. Final summary report

International Nuclear Information System (INIS)

Beller, J.

1995-08-01

Through the Office of Technology Development (OTD), the U.S. Department of Energy (DOE) has initiated a national applied research, development, demonstration, testing, and evaluation program, whose goal has been to resolve the major technical issues and rapidly advance technologies for environmental restoration and waste management. The Innovative Technology Development (ITD) Program was established as a part of the DOE, Research, Development, Demonstration, Testing, and Evaluation (RDDT ampersand E) Program. The plan is part of the DOE's program to restore sites impacted by weapons production and to upgrade future waste management operations. On July 10, 1990, DOE issued a Program Research and Development Announcement (PRDA) through the Idaho Operations Office to solicit private sector help in developing innovative technologies to support DOE's clean-up goals. This report presents summaries of each of the seven projects, which developed and tested the technologies proposed by the seven private contractors selected through the PRDA process

Development of ultrasensitive spectroscopic analysis technology

Energy Technology Data Exchange (ETDEWEB)

Cha, Hyung Ki; Song, K S; Kim, D H; Yang, K H; Jung, E C; Jeong, D Y; Yi, Y J; Lee, S M; Hong, K H; Han, J M; Yoo, B D; Rho, S P; Yi, J H; Park, H M; Cha, B H; Nam, S M; Lee, J M

1997-09-01

For the development of the laser initiated high resolution, ultra sensitive analysis technology following field of researches have been performed. (1) Laser resonance ionization technology, (2) Laser-induced rare isotope detection technology, (3) Laser-induced plasma analysis technology, (4) Microparticle analysis technology by using ion trap, (5) Laser induced remote sensing technique. As a result a monitoring system for photoionized product is developed and the test of system is performed with Sm sample. The rare isotope detection system is designed and a few key elements of the system are developed. In addition a laser-induced plasma analysis system is developed and samples such as Zircaloy, Zinc-base alloy, rock samples are reasonably analyzed. The detection sensitivity is identified as good as a few ppm order. An ion trap is developed and microparticles such as SiC are trapped inside the trap by ac and dc fields. The fluorescence signals from the organic dyes as well as rare earth element which are absorbed on the microparticles are detected. Several calibration curves are also obtained. In the field of laser remote sensing a mobile Lidar system is designed and several key elements are developed. In addition the developed system is used for the detection of Ozone, NO{sub 2}, SO{sub 2}, etc. (author). 57 refs., 42 figs.

X-43 Hypersonic Vehicle Technology Development

Science.gov (United States)

Voland, Randall T.; Huebner, Lawrence D.; McClinton, Charles R.

2005-01-01

NASA recently completed two major programs in Hypersonics: Hyper-X, with the record-breaking flights of the X-43A, and the Next Generation Launch Technology (NGLT) Program. The X-43A flights, the culmination of the Hyper-X Program, were the first-ever examples of a scramjet engine propelling a hypersonic vehicle and provided unique, convincing, detailed flight data required to validate the design tools needed for design and development of future operational hypersonic airbreathing vehicles. Concurrent with Hyper-X, NASA's NGLT Program focused on technologies needed for future revolutionary launch vehicles. The NGLT was "competed" by NASA in response to the President s redirection of the agency to space exploration, after making significant progress towards maturing technologies required to enable airbreathing hypersonic launch vehicles. NGLT quantified the benefits, identified technology needs, developed airframe and propulsion technology, chartered a broad University base, and developed detailed plans to mature and validate hypersonic airbreathing technology for space access. NASA is currently in the process of defining plans for a new Hypersonic Technology Program. Details of that plan are not currently available. This paper highlights results from the successful Mach 7 and 10 flights of the X-43A, and the current state of hypersonic technology.

Development of Industrial Process Diagnosis and Measurement Technology

International Nuclear Information System (INIS)

Jung, Sung Hee; Kim, Jong Bum; Moon, Jin Ho

2010-04-01

Section 1. Industrial Gamma CT Technology for Process Diagnosis: The project is aimed to develop industrial process gamma tomography system for investigation on structural and physical malfunctioning and process media distribution by means of sealed gamma source and radioactive materials. Section 2. Development of RI Hydraulic Detection Technology for Industrial Application: The objectives in this study are to develop the evaluation technology of the hydrological characteristics and the hydraulic detection technology using radioisotope, and to analyze the hydrodynamics and pollutant transport in water environment like surface and subsurface. Section 3. Development of RT-PAT System for Powder Process Diagnosis: The objective of this project is the development of a new radiation technology to improve the accuracy of the determination of moisture content in a powder sample by using radiation source through the so-called RT-PAT (Radiation Technology-Process Analytical Technology), which is a new concept of converging technology between the radiation technology and the process analytical technology

Development of industrial process diagnosis and measurement technology

International Nuclear Information System (INIS)

Jung, Sunghee; Kim, Jongbum; Moon, Jinho; Suh, Kyungsuk; Kim, Jongyun

2012-04-01

Section1. Industrial Gamma CT Technology for Process Diagnosis The project is aimed to develop industrial process gamma tomography system for investigation on structural and physical malfunctioning and process media distribution by means of sealed gamma source and radioactive materials. Section2. Development of RI Hydraulic Detection Technology for Industrial Application The objectives in this study are to develop the evaluation technology of the hydrological characteristics and the hydraulic detection technology using radioisotope, and to analyze the hydrodynamics and pollutant transport in water environment like surface and subsurface. Section3. Development of RT-PAT System for Powder Process Diagnosis The objective of this project is the development of a new radiation technology to improve the accuracy of the determination of moisture content in a powder sample by using radiation source through the so-called RT-PAT (Radiation Technology-Process Analytical Technology), which is a new concept of converging technology between the radiation technology and the process analytical technology

Nigerian Journal of Technological Development

African Journals Online (AJOL)

The Nigerian Journal of Technological Development is now a quarterly publication of the Faculty of Engineering & Technology, University of Ilorin, Ilorin, Nigeria. ... to the subject matter as a Research Paper, Review Paper or a Technical Note.

Technology development multidimensional review for engineering and technology managers

CERN Document Server

Neshati, Ramin; Watt, Russell; Eastham, James

2014-01-01

Developing new products, services, systems, and processes has become an imperative for any firm expecting to thrive in today’s fast-paced and hyper-competitive environment.  This volume integrates academic and practical insights to present fresh perspectives on new product development and innovation, showcasing lessons learned on the technological frontier.  The first part emphasizes decision making.  The second part focuses on technology evaluation, including cost-benefit analysis, material selection, and scenarios. The third part features in-depth case studies to present innovation management tools, such as customer needs identification, technology standardization, and risk management. The fourth part highlights important international trends, such as globalization and outsourcing. Finally the fifth part explores social and political aspects.

Decontamination Technology Development for Nuclear Research Facilities

International Nuclear Information System (INIS)

Oh, Won Zin; Jung, Chong Hun; Choi, Wang Kyu; Won, Hui Jun; Kim, Gye Nam

2004-02-01

Technology development of surface decontamination in the uranium conversion facility before decommissioning, technology development of component decontamination in the uranium conversion facility after decommissioning, uranium sludge treatment technology development, radioactive waste soil decontamination technology development at the aim of the temporary storage soil of KAERI, Optimum fixation methodology derivation on the soil and uranium waste, and safety assessment methodology development of self disposal of the soil and uranium waste after decontamination have been performed in this study. The unique decontamination technology applicable to the component of the nuclear facility at room temperature was developed. Low concentration chemical decontamination technology which is very powerful so as to decrease the radioactivity of specimen surface under the self disposal level was developed. The component decontamination technology applicable to the nuclear facility after decommissioning by neutral salt electro-polishing was also developed. The volume of the sludge waste could be decreased over 80% by the sludge waste separation method by water. The electrosorption method on selective removal of U(VI) to 1 ppm of unrestricted release level using the uranium-containing lagoon sludge waste was tested and identified. Soil decontamination process and equipment which can reduce the soil volume over 90% were developed. A pilot size of soil decontamination equipment which will be used to development of real scale soil decontamination equipment was designed, fabricated and demonstrated. Optimized fixation methodology on soil and uranium sludge was derived from tests and evaluation of the results. Safety scenario and safety evaluation model were development on soil and uranium sludge aiming at self disposal after decontamination

Mars Technology Program Planetary Protection Technology Development

Science.gov (United States)

Lin, Ying

2006-01-01

The objectives of the NASA Planetary Protection program are to preserve biological and organic conditions of solar-system bodies for future scientific exploration and to protect the Earth from potential hazardous extraterrestrial contamination. As the exploration of solar system continues, NASA remains committed to the implementation of planetary protection policy and regulations. To fulfill this commitment, the Mars Technology Program (MTP) has invested in a portfolio of tasks for developing necessary technologies to meet planetary protection requirements for the next decade missions.

Technologies for a sustainable development; Technologies pour un developpement durable

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

The European Event on Technology (EET), a recurrent annual event since 1992, is a major meeting opportunity for researchers and engineers as well as private and public decision-makers, on technologies, their evolution and their industrial and social implications. In less than a decade, sustainable development has become both an economic and a political priority. It was urgent and legitimate that those who are the mainsprings should take hold of the subject and give it technological content, estimate its costs and define clear timetables. The debates consist of: plenary sessions on environmental, social and economic stakes of sustainable development and the challenges for, and commitment of engineers, managers and politicians with respect to these goals; and workshops, which provide an overview of recently acquired or upcoming technologies developed by sector: energy, transports, new information technologies, new industrial manufacturing technologies (materials, products, services), waste management, global environment monitoring, water management, bio-technologies, and innovation management. This document brings together the different talks given by the participants. Among these, the following ones fall into the energy and environment scope: energy efficiency of buildings: towards energy autonomy; superconductors enable in new millennium for electric power industry; advanced gas micro-turbine-driven generator technology; environmental and technical challenges of an offshore wind farm; future nuclear energy systems; modelling combustion in engines: progress and prospects for reducing emissions; on-board computers: reduction in consumption and emissions of engine-transmission units for vehicles; polymer-lithium batteries: perspectives for zero-emission traction; hybrid vehicles and energy/environmental optimization: paths and opportunities; fuel cells and zero-emission: perspectives and developments; global change: causes, modeling and economic issues; the GMES

Social and Technological Development in Context

DEFF Research Database (Denmark)

Koch, Christian

1997-01-01

This papers studies the processes developing technology and its social "sorroundings", the social networks. Positions in the debate on technological change is discussed. A central topic is the enterprise external development and decision processes and their interplay with the enterprise internal...

IFR fuel cycle

International Nuclear Information System (INIS)

Battles, J.E.; Miller, W.E.; Lineberry, M.J.; Phipps, R.D.

1992-01-01

The next major milestone of the IFR program is engineering-scale demonstration of the pyroprocess fuel cycle. The EBR-II Fuel Cycle Facility has just entered a startup phase, which includes completion of facility modifications and installation and cold checkout of process equipment. This paper reviews the development of the electrorefining pyroprocess, the design and construction of the facility for the hot demonstration, the design and fabrication of the equipment, and the schedule and initial plan for its operation

Status of advanced nuclear reactor development in Korea

International Nuclear Information System (INIS)

Kim, H.R.; Kim, K.K.; Kim, Y.W.; Joo, H.K.

2014-01-01

The Korean nuclear industry is facing new challenges to solve the spent fuel storage problem and meet the needs to diversify the application areas of nuclear energy. In order to provide solutions to these challenges, the Korea Atomic Energy Research Institute (KAERI) has been developing advanced nuclear reactors including a Sodium-cooled Fast Reactor, Very High Temperature Gas cooled Reactor (VHTR), and System-integrated Modular Advanced Reactor (SMART) with substantially improved safety, economics, and environment-friendly features. A fast reactor system is one of the most promising options for a reduction of radioactive wastes. The long-term plan for Advanced SFR development in conjunction with the pyro-process was authorized by the Korean Atomic Energy Commission in 2008. The development milestone includes specific design approval of a prototype SFR by 2020, and the construction of a prototype SFR by 2028. KAERI has been carrying out the preliminary design of a 150MWe SFR prototype plant system since 2012. The development of advanced SFR technologies and the basic key technologies necessary for the prototype SFR are also being carried out. By virtue of high-temperature heat, a VHTR has diverse applications including hydrogen production. KAERI launched a nuclear hydrogen project using a VHTR in 2006, which focused on four basic technologies: the development of design tools, very high-temperature experimental technology, TRISO fuel fabrication, and Sulfur-iodine thermo-chemical hydrogen production technology. The technology development project will be continued until 2017. A conceptual reactor design study was started in 2012 as collaboration between industry and government to enhance the early-launching of the nuclear hydrogen development and demonstration (NHDD) project. The goal of the NHDD project is to design and build a nuclear hydrogen demonstration system by 2030. KAERI has developed SMART which is a small-sized advanced integral reactor with a rated

Technology transfer for development

International Nuclear Information System (INIS)

Abraham, D.

1990-07-01

The IAEA has developed a multifaceted approach to ensure that assistance to Member States results in assured technology transfer. Through advice and planning, the IAEA helps to assess the costs and benefits of a given technology, determine the basic requirements for its efficient use in conditions specific to the country, and prepare a plan for its introduction. This report describes in brief the Technical Co-operation Programmes

Development of Risk Management Technology/Development of Risk-Informed Application Technology

Energy Technology Data Exchange (ETDEWEB)

Yang, Joon Eon; Kim, K. Y.; Ahn, K. I.; Lee, Y. H.; Lim, H. G.; Jung, W. S.; Choi, S. Y.; Han, S. J.; Ha, J. J.; Hwang, M. J.; Park, S. Y.; Yoon, C

2007-06-15

This project aims at developing risk-informed application technologies to enhance the safety and economy of nuclear power plant altogether. For this, the Integrated Level 1 and 2 PSA model is developed. In addition, the fire and internal flooding PSA models are improved according to the PSA standard of U.S.A. To solve the issues of domestic PSA model, the best-estimate thermal hydraulic analyses are preformed for the ATWS and LSSB. In order to reduce the uncertainty of PSA, several new PSA technologies are developed: (1) more exact quantification of large fault tree, (2) importance measure including the effects of external PSA. As feasibility studies of Option 2 and 3, the class of 6 systems' SSC are re-classified based on the risk information and the sensitivity analyses is performed for the EDG starting time, respectively. It is also improved that the methodology to identify the vital area of NPP. The research results of this project can be used in the regulatory body and the industry projects for risk-informed applications.

Development of Risk Management Technology/Development of Risk-Informed Application Technology

International Nuclear Information System (INIS)

Yang, Joon Eon; Kim, K. Y.; Ahn, K. I.; Lee, Y. H.; Lim, H. G.; Jung, W. S.; Choi, S. Y.; Han, S. J.; Ha, J. J.; Hwang, M. J.; Park, S. Y.; Yoon, C.

2007-06-01

This project aims at developing risk-informed application technologies to enhance the safety and economy of nuclear power plant altogether. For this, the Integrated Level 1 and 2 PSA model is developed. In addition, the fire and internal flooding PSA models are improved according to the PSA standard of U.S.A. To solve the issues of domestic PSA model, the best-estimate thermal hydraulic analyses are preformed for the ATWS and LSSB. In order to reduce the uncertainty of PSA, several new PSA technologies are developed: (1) more exact quantification of large fault tree, (2) importance measure including the effects of external PSA. As feasibility studies of Option 2 and 3, the class of 6 systems' SSC are re-classified based on the risk information and the sensitivity analyses is performed for the EDG starting time, respectively. It is also improved that the methodology to identify the vital area of NPP. The research results of this project can be used in the regulatory body and the industry projects for risk-informed applications

New developments in PET detector technology

International Nuclear Information System (INIS)

Niu Lingxin; Zhao Shujun; Zhang Bin; Liu Haojia

2010-01-01

The researches on PET detector are always active and innovative area. The research direction of PET detector includes improving performances of scintillator-based detectors, investigating new detectors suitable for multi-modality imaging (e.g. PET/CT and PET/MRI), meeting requirements of TOF and DOI technologies and boosting the development of the technologies. In this paper, new developments in PET detector technology about scintillation crystal, photodetector and semiconductor detector is introduced. (authors)

Development of Technological Profiles for Transfer of Energy- and Resource Saving Technologies

Directory of Open Access Journals (Sweden)

Lysenko, V.S.

2015-01-01

Full Text Available The article deals with the methodological foundations for the development of technological profiles for «System of Transfer of Energy- and Resource Saving Technologies». It is determined that a compliance with the methodology and standards of the European network «Relay Centers» (Innovation Relay Centers — IRC network, since 2008 — EEN, the Russian Technology Transfer Network RTTN and Uk rainian Technology Transfer Network UTTN is the main pri nciple of the development process of technological requests and offers.

Advancing CANDU technology AECL's Development program

International Nuclear Information System (INIS)

Torgerson, D.F.

1997-01-01

AECL has a comprehensive product development program that is advancing all aspects of CANDU technology including fuel and fuel cycles, fuel channels, heavy water and tritium technology, safety technology, components and systems, constructability, health and environment, and control and instrumentation. The technology arising from these programs is being incorporated into the CANDU design through an evolutionary process. This evolutionary process is focused on improving economics, enhancing safety and ensuring fuel cycle flexibility to secure fuel supply for the foreseeable future. This strategic thrusts are being used by CANDU designers and researchers to set priorities and goals for AECL's development activities. The goals are part of a 25-year development program that culminates in the 'CANDU X'. The 'CANDU X' is not a specific design - it is a concept that articulates our best extrapolation of what is achievable with the CANDU design over the next 25 years, and includes the advanced features arising from the R and D and engineering to be done over that time. AECL's current product, the 700 MWe class CANDU 6 and the 900 MWe class CANDU 9, both incorporate output from the development programs as the technology become available. A brief description of each development areas is given below. The paper ends with the conclusion that AECL has a clear vision of how CANDU technology and products will evolve over the next several years, and has structured a comprehensive development program to take full advantage of the inherent characteristics of heavy water reactors. (author)

Integrating Product and Technology Development

DEFF Research Database (Denmark)

Meijer, Ellen Brilhuis; Pigosso, Daniela Cristina Antelmi; McAloone, Tim C.

2016-01-01

.g. managing dependencies) and opportunities (e.g. streamlining development). This paper presents five existing reference models for technology development (TD), which were identified via a systematic literature review, where their possible integration with product development (PD) reference models......Although dual innovation projects, defined in this article as the concurrent development of products and technologies, often occur in industry, these are only scarcely supported methodologically. Limited research has been done about dual innovation projects and their inherent challenges (e...... was investigated. Based on the specific characteristics desired for dual innovation projects, such as integrated product development and coverage of multiple development stages, a set of selection criteria was employed to select suitable PD and TD reference models. The integration and adaptation of the selected...

Development of high-level radioactive waste treatment and conversion technologies 'Dry decontamination technology development for highly radioactive contaminants'

International Nuclear Information System (INIS)

Oh, Won Zin; Lee, K. W.; Won, H. J.; Jung, C. J.; Choi, W. K.; Kim, G. N.; Moon, J. K.

2001-04-01

The followings were studied through the project entitled 'Dry Decontamination Technology Development for Highly Radioactive Contaminants'. 1.Contaminant Characteristics Analysis of Domestic Nuclear Fuel Cycle Projects(NFCP) and Applicability Study of the Unit Dry-Decontamination Techniques A. Classification of contaminated equipments and characteristics analysis of contaminants B. Applicability study of the unit dry-decontamination techniques 2.Performance Evaluation of Unit Dry Decontamination Technique A. PFC decontamination technique B. CO2 decontamination technique C. Plasma decontamination technique 3.Development of Residual Radiation Assessment Methodology for High Radioactive Facility Decontamination A. Development of radioactive nuclide diffusion model on highly radioactive facility structure B. Obtainment of the procedure for assessment of residual radiation dose 4.Establishment of the Design Concept of Dry Decontamination Process Equipment Applicable to Highly Radioactive Contaminants 5.TRIGA soil unit decontamination technology development A. Development of soil washing and flushing technologies B. Development of electrokinetic soil decontamination technology

Development of IT-based data communication network technology

International Nuclear Information System (INIS)

Hong, Seok Boong; Jeong, K. I.; Yoo, Y. R.

2010-10-01

- Developing broadband high-reliability real-time communications technology for NPP - Developing reliability and performance validation technology for communications network - Developing security technology for NPP communications network - Developing field communications network for harsh environment of NPP - International standard registration(Oct. 28, 2009, IEC 61500

Foreign cooperative technology development and transfer

International Nuclear Information System (INIS)

Schassburger, R.J.; Robinson, R.A.

1988-01-01

It is the policy of the US Department of Energy (DOE) that, in pursuing the development of mined geologic repositories in the United States, the waste isolation program will continue to actively support international cooperation and exchange activities that are judged to be in the best interest of the program and in compliance with the Nuclear Waste Policy Act of 1982, Sec. 223. Because there are common technical issues and because technology development often requires large expenditures of funds and dedication of significant capital resources, it is advantageous to cooperate with foreign organizations carrying out similar activities. The DOE's Office of Civilian Radioactive Waste Management is working on cooperative nuclear waste isolation technology development programs with the Organization for Economic Cooperation and Development/Nuclear Energy Agency (OECD/NEA), Canada's Atomic Energy of Canada, Limited (AECL), Sweden, Switzerland, and the Federal Republic of Germany. This paper describes recent technology results that have been obtained in DOE's foreign cooperative programs. Specific technology development studies are discussed for cooperative efforts with Canada, OECD/NEA, and a natural analog project in Brazil

Key technological challenges for JSFR development

International Nuclear Information System (INIS)

Morishita, Masaki; Nakai, Ryodai; Aoto, Kazumi

2008-01-01

JSFR is a sodium cooled loop type fast reactor on which a conceptual design study is now underway in the framework of 'Fast Reactor Cycle Technology Development Project (FaCT project)' of Japan. Achieving economic competitiveness with future light water reactors, along with assuring high level of safety and reliability, is among the most crucial development targets. A number of innovative technologies are pursued for these purposes. A two loop primary heat transfer system (PHTS) design, integration of a main circulation pump and an intermediate heat exchanger (IHX) into one single component, and adoption of high chrome ferritic steel as a structural material are typical technologies mainly for economic purposes. A passive shutdown system, decay heat removal by natural convection, and re-criticality free core configuration are those for mainly safety enhancement purposes. Technically challenging issues inevitably accompany these innovative technologies, and a systematic research and development program is undertaken for resolving these issues and realization of the plant design. An overall picture will be given in this paper on the design concept of JSFR that will be followed by descriptions on the major innovative technologies and their relevant research and development activities. (author)

Titanium Aluminide Casting Technology Development

Science.gov (United States)

Bünck, Matthias; Stoyanov, Todor; Schievenbusch, Jan; Michels, Heiner; Gußfeld, Alexander

2017-12-01

Titanium aluminide alloys have been successfully introduced into civil aircraft engine technology in recent years, and a significant order volume increase is expected in the near future. Due to its beneficial buy-to-fly ratio, investment casting bears the highest potential for cost reduction of all competing production technologies for TiAl-LPTB. However, highest mechanical properties can be achieved by TiAl forging. In view of this, Access e.V. has developed technologies for the production of TiAl investment cast parts and TiAl die cast billets for forging purposes. While these parts meet the highest requirements, establishing series production and further optimizing resource and economic efficiency are present challenges. In order to meet these goals, Access has recently been certified according to aircraft standards, aiming at qualifying parts for production on technology readiness level 6. The present work gives an overview of the phases of development and certification.

The DOE safeguards and security technology development program

International Nuclear Information System (INIS)

Cherry, R.C.; Wheelock, A.J.

1991-01-01

This paper reports that strategic planning for safeguards and security within the Department of Energy emphasizes the contributions of advanced technologies to the achievement of Departmental protection program goals. The Safeguards and Security Technology Development Program provides state-of-the-art technologies, systems and technical services in support of the policies and programmatic requirements for the protection of Departmental assets. The Program encompasses research and development in physical security, nuclear material control and accountability, information security and personnel security, and the integration of these disciplines in advanced applications. Technology development tasks serve goals that range from the maintenance of an effective technology base to the development, testing and evaluation of applications to meet field needs. A variety of factors, from the evolving threat to reconfiguration of the DOE complex and the technical requirements of new facilities, are expected to influence safeguards and security technology requirements and development efforts. Implementation of the Program is based on the systematic identification, prioritization and alignment of technology development tasks and needs. Initiatives currently underway are aimed at enhancing technology development project management. Increased management attention is also being placed on efforts to promote the benefits of the Program through technology transfer and interagency liaison

Energy consumption and technological developments

International Nuclear Information System (INIS)

Okorokov, V.R.

1990-02-01

The paper determines an outline of the world energy prospects based on principal trends of the development of energy consumption analysed over the long past period. According to the author's conclusion the development of energy systems will be determined in the nearest future (30 - 40 years) by contemporary energy technologies based on the exploitation of traditional energy resources but in the far future technologies based on the exploitation of thermonuclear and solar energy will play the decisive role. (author)

Technology-development needs for magnetic fusion

International Nuclear Information System (INIS)

Stacey, W.M. Jr.; Baker, C.C.; Conn, R.W.; Krakowski, R.A.; Steiner, D.; Thomassen, K.I.

1983-03-01

The technology-development needs for magnetic fusion have been identified from an assessment of the conceptual design studies which have been performed. A summary of worldwide conceptual design effort is presented. The relative maturity of the various confinement concepts and the intensity and continuity of the design efforts are taken into account in identifying technology development needs. A major conclusion of this study is that there is a high degree of commonality among the technology requirements identified for the various confinement concepts

Overcoming regulatory barriers: DOE environmental technology development program

International Nuclear Information System (INIS)

Kurtyka, B.M.; Clodfelter-Schumack, K.; Evans, T.T.

1995-01-01

The potential to improve environmental conditions via compliance or restoration is directly related to the ability to produce and apply innovative technological solutions. However, numerous organizations, including the US General Accounting Office (GAO), the EPA National Advisory Council for Environmental Policy and Technology (NACEPT), the DOE Environmental Management Advisory Board (EMAB), and the National Science and Technology Council (NSTC) have determined that significant regulatory barriers exist that inhibit the development and application of these technologies. They have noted the need for improved efforts in identifying and rectifying these barriers for the purpose of improving the technology development process, providing innovative alternatives, and enhancing the likelihood of technology acceptance by all. These barriers include, among others, regulator and user bias against ''unknown/unproven'' technologies; multi-level/multi-media permit disincentives; potential liability of developers and users for failed implementation; wrongly defined or inadequate data quality objectives: and lack of customer understanding and input. The ultimate goal of technology development is the utilization of technologies. This paper will present information on a number of regulatory barriers hindering DOE's environmental technology development program and describe DOE efforts to address these barriers

Development of environmental radiation control technology

International Nuclear Information System (INIS)

Kim, Ingyu; Kim, Enhan; Keum, Dongkwon

2012-04-01

To develop the comprehensive environmental radiation management technology, - An urban atmospheric dispersion model and decision-aiding model have been developed. - The technologies for assessing the radiation impact to non-human biota and the environmental medium contamination have developed. - The analytical techniques of the indicator radionuclides related to decommissioning of nuclear facilities and nuclear waste repository have been developed. - The national environmental radiation impact has been assessed, and the optimum management system of natural radiation has been established

Transfer of radiation technology to developing countries

Science.gov (United States)

Markovic, Vitomir; Ridwan, Mohammad

1993-10-01

Transfer of technology is a complex process with many facets, options and constraints. While the concept is an important step in bringing industrialization process to agricultural based countries, it is clear, however, that a country will only benefit from a new technology if it addresses a real need, and if it can be absorbed and adapted to suit the existing cultural and technological base. International Atomic Energy Agency, as UN body, has a mandate to promote nuclear applicationsand assist Member States in transfer of technology for peaceful applications. This mandate has been pursued by many different mechanisms developed in the past years: technical assistance, coordinated research programmes, scientific and technical meetings, publications, etc. In all these activities the Agency is the organizer and initiator, but main contributions come from expert services from developed countries and, increasingly, from developing countries themselves. The technical cooperation among developing coutries more and more becomes part of different programmes. In particular, regional cooperation has been demonstrated as an effective instrument for transfer of technology from developed and among developing countries. Some examples of actual programmes are given.

The development and technology transfer of software engineering technology at NASA. Johnson Space Center

Science.gov (United States)

Pitman, C. L.; Erb, D. M.; Izygon, M. E.; Fridge, E. M., III; Roush, G. B.; Braley, D. M.; Savely, R. T.

1992-01-01

The United State's big space projects of the next decades, such as Space Station and the Human Exploration Initiative, will need the development of many millions of lines of mission critical software. NASA-Johnson (JSC) is identifying and developing some of the Computer Aided Software Engineering (CASE) technology that NASA will need to build these future software systems. The goal is to improve the quality and the productivity of large software development projects. New trends are outlined in CASE technology and how the Software Technology Branch (STB) at JSC is endeavoring to provide some of these CASE solutions for NASA is described. Key software technology components include knowledge-based systems, software reusability, user interface technology, reengineering environments, management systems for the software development process, software cost models, repository technology, and open, integrated CASE environment frameworks. The paper presents the status and long-term expectations for CASE products. The STB's Reengineering Application Project (REAP), Advanced Software Development Workstation (ASDW) project, and software development cost model (COSTMODL) project are then discussed. Some of the general difficulties of technology transfer are introduced, and a process developed by STB for CASE technology insertion is described.

EMI Architecture and Technology Development Plan

CERN Document Server

Balazs, K.

2013-01-01

This document provides a brief overview of the EMI architecture and the technology development directions presented by the four EMI technology areas and by EMI partners. The report represents the final revision of EMI technology planning covering a time period beyond the project end.

Biofuel technologies. Recent developments

Energy Technology Data Exchange (ETDEWEB)

Gupta, Vijai Kumar [National Univ. of Ireland Galway (Ireland). Dept. of Biochemistry; MITS Univ., Rajasthan (India). Dept. of Science; Tuohy, Maria G. (eds.) [National Univ. of Ireland Galway (Ireland). Dept. of Biochemistry

2013-02-01

Written by experts. Richly illustrated. Of interest to both experienced researchers and beginners in the field. Biofuels are considered to be the main potential replacement for fossil fuels in the near future. In this book international experts present recent advances in biofuel research and related technologies. Topics include biomethane and biobutanol production, microbial fuel cells, feedstock production, biomass pre-treatment, enzyme hydrolysis, genetic manipulation of microbial cells and their application in the biofuels industry, bioreactor systems, and economical processing technologies for biofuel residues. The chapters provide concise information to help understand the technology-related implications of biofuels development. Moreover, recent updates on biofuel feedstocks, biofuel types, associated co- and byproducts and their applications are highlighted. The book addresses the needs of postgraduate researchers and scientists across diverse disciplines and industrial sectors in which biofuel technologies and related research and experimentation are pursued.

NATIONAL TECHNOLOGICAL INITIATIVE AS THE STRATEGIC DIRECTION OF THE TECHNOLOGICAL DEVELOPMENT OF RUSSIA

Directory of Open Access Journals (Sweden)

E. V. Sibirskaya

2018-01-01

Full Text Available Russia, having lost a significant part of a high-tech industrial complex during the reforms (1993–2000, sharply reducing the state support of scientific research and development, has turned into a power dependent on the conjuncture in the hydrocarbon energy market and from foreign sup-plies of technologies, consumption goods, including those necessary for life support, thus being on the "technological needle". The main factor of development was the resource-producing complex. This situation had a negative impact on the pace of the country's development, on its defense capability and created real prerequisites for the loss of technological, economic, and, in the long run, political sovereignty and disintegration of the state. Nevertheless, the availability of natural resources along with human capi-tal and geographic location is a global competitive advantage of theRussian Federation, and the task is to use this advantage maximally as one of the first echelon countries in the emerging world order. One of the most important tasks was the search for such a direction of technological devel-opment that allows, on the one hand, to preserve Russia's position in the world market of traditional products; on the other – to strengthen positions in the markets of products with a higher degree of processing of Russian raw materials (oil and gas complex and agro-industrial complex; and finally – to master new "growth points" (services, new markets, talents, technologies in the world market of high-tech products and services. The set tasks assume several solutions. First, scientific and technological development should be based on the strategy of scientific and technological development of theRussian Federationand the national technological initiative, as it sets both resource constraints and priorities in the needs of the economy in new products and new technological solutions. Secondly,Russiashould take into account existing and emerging trends in the

A Lunar Surface System Supportability Technology Development Roadmap

Science.gov (United States)

Oeftering, Richard C.; Struk, Peter M.; Taleghani, barmac K.

2011-01-01

This paper discusses the establishment of a Supportability Technology Development Roadmap as a guide for developing capabilities intended to allow NASA s Constellation program to enable a supportable, sustainable and affordable exploration of the Moon and Mars. Presented is a discussion of supportability, in terms of space facility maintenance, repair and related logistics and a comparison of how lunar outpost supportability differs from the International Space Station. Supportability lessons learned from NASA and Department of Defense experience and their impact on a future lunar outpost is discussed. A supportability concept for future missions to the Moon and Mars that involves a transition from a highly logistics dependent to a logistically independent operation is discussed. Lunar outpost supportability capability needs are summarized and a supportability technology development strategy is established. The resulting Lunar Surface Systems Supportability Strategy defines general criteria that will be used to select technologies that will enable future flight crews to act effectively to respond to problems and exploit opportunities in an environment of extreme resource scarcity and isolation. This strategy also introduces the concept of exploiting flight hardware as a supportability resource. The technology roadmap involves development of three mutually supporting technology categories, Diagnostics Test and Verification, Maintenance and Repair, and Scavenging and Recycling. The technology roadmap establishes two distinct technology types, "Embedded" and "Process" technologies, with different implementation and thus different criteria and development approaches. The supportability technology roadmap addresses the technology readiness level, and estimated development schedule for technology groups that includes down-selection decision gates that correlate with the lunar program milestones. The resulting supportability technology roadmap is intended to develop a set

NASA Astrophysics Funds Strategic Technology Development

Science.gov (United States)

Seery, Bernard D.; Ganel, Opher; Pham, Bruce

2016-01-01

The COR and PCOS Program Offices (POs) reside at the NASA Goddard Space Flight Center (GSFC), serving as the NASA Astrophysics Division's implementation arm for matters relating to the two programs. One aspect of the PO's activities is managing the COR and PCOS Strategic Astrophysics Technology (SAT) program, helping mature technologies to enable and enhance future astrophysics missions. For example, the SAT program is expected to fund key technology developments needed to close gaps identified by Science and Technology Definition Teams (STDTs) planned to study several large mission concept studies in preparation for the 2020 Decadal Survey.The POs are guided by the National Research Council's "New Worlds, New Horizons in Astronomy and Astrophysics" Decadal Survey report, NASA's Astrophysics Implementation Plan, and the visionary Astrophysics Roadmap, "Enduring Quests, Daring Visions." Strategic goals include dark energy, gravitational waves, and X-ray observatories. Future missions pursuing these goals include, e.g., US participation in ESA's Euclid, Athena, and L3 missions; Inflation probe; and a large UV/Optical/IR (LUVOIR) telescope.To date, 65 COR and 71 PCOS SAT proposals have been received, of which 15 COR and 22 PCOS projects were funded. Notable successes include maturation of a new far-IR detector, later adopted by the SOFIA HAWC instrument; maturation of the H4RG near-IR detector, adopted by WFIRST; development of an antenna-coupled transition-edge superconducting bolometer, a technology deployed by BICEP2/BICEP3/Keck to measure polarization in the CMB signal; advanced UV reflective coatings implemented on the optics of GOLD and ICON, two heliophysics Explorers; and finally, the REXIS instrument on OSIRIS-REx is incorporating CCDs with directly deposited optical blocking filters developed by another SAT-funded project.We discuss our technology development process, with community input and strategic prioritization informing calls for SAT proposals and

Enhancement of Nuclear Transparency of Pyroprocessing through Case Studies

International Nuclear Information System (INIS)

Lee, Han Soo; Park, S. W.; Kim, E. H.; Kim, D. H.; Hurh, J. M.; Kim, I. T.; Kim, H. D.; Lee, J. H.

2009-09-01

- Analysis of international spent nuclear fuel treatment technologies and future collaboration · Collection of recent technology information of US, Japan and Europe · Discuss on future collaboration with US · Collection of active test results of other countries and compare with domestic results - Establishment of network regarding nuclear spent fuel treatment technology thru IPRC - Information exchange through international conference (IPRC) - Discuss with experts on active test results

Mixed Waste Integrated Program -- Problem-oriented technology development

International Nuclear Information System (INIS)

Hart, P.W.; Wolf, S.W.; Berry, J.B.

1994-01-01

The Mixed Waste Integrated Program (MWIP) is responding to the need for DOE mixed waste treatment technologies that meet these dual regulatory requirements. MWIP is developing emerging and innovative treatment technologies to determine process feasibility. Technology demonstrations will be used to determine whether processes are superior to existing technologies in reducing risk, minimizing life-cycle cost, and improving process performance. Technology development is ongoing in technical areas required to process mixed waste: materials handling, chemical/physical treatment, waste destruction, off-gas treatment, final forms, and process monitoring/control. MWIP is currently developing a suite of technologies to process heterogeneous waste. One robust process is the fixed-hearth plasma-arc process that is being developed to treat a wide variety of contaminated materials with minimal characterization. Additional processes encompass steam reforming, including treatment of waste under the debris rule. Advanced off-gas systems are also being developed. Vitrification technologies are being demonstrated for the treatment of homogeneous wastes such as incinerator ash and sludge. An alternative to conventional evaporation for liquid removal--freeze crystallization--is being investigated. Since mercury is present in numerous waste streams, mercury removal technologies are being developed

Textile technology development

Science.gov (United States)

Shah, Bharat M.

1995-01-01

The objectives of this report were to evaluate and select resin systems for Resin Transfer Molding (RTM) and Powder Towpreg Material, to develop and evaluate advanced textile processes by comparing 2-D and 3-D braiding for fuselage frame applications and develop window belt and side panel structural design concepts, to evaluate textile material properties, and to develop low cost manufacturing and tooling processes for the automated manufacturing of fuselage primary structures. This research was in support of the NASA and Langley Research Center (LaRc) Advanced Composite Structural Concepts and Materials Technologies for Primary Aircraft Structures program.

A next-generation reactor concept: The Integral Fast Reactor (IFR)

Energy Technology Data Exchange (ETDEWEB)

Chang, Y.I.

1992-01-01

The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

A next-generation reactor concept: The Integral Fast Reactor (IFR)

Energy Technology Data Exchange (ETDEWEB)

Chang, Y.I.

1992-07-01

The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

A next-generation reactor concept: The Integral Fast Reactor (IFR)

International Nuclear Information System (INIS)

Chang, Y.I.

1992-01-01

The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing

Fusion development and technology

International Nuclear Information System (INIS)

Montgomery, D.B.

1992-01-01

This report discusses the following: superconducting magnet technology; high field superconductors; advanced magnetic system and divertor development; poloidal field coils; gyrotron development; commercial reactor studies--aries; ITER physics: alpha physics and alcator R ampersand D for ITER; lower hybrid current drive and heating in the ITER device; ITER superconducting PF scenario and magnet analysis; ITER systems studies; and safety, environmental and economic factors in fusion development

Information Communication Technology Planning in Developing Countries

Science.gov (United States)

Malapile, Sandy; Keengwe, Jared

2014-01-01

This article explores major issues related to Information Communication Technology (ICT) in education and technology planning. Using the diffusion of innovation theory, the authors examine technology planning opportunities and challenges in Developing countries (DCs), technology planning trends in schools, and existing technology planning models…

Development of advanced neutron beam technology

Energy Technology Data Exchange (ETDEWEB)

Seong, B S; Lee, J S; Sim, C M [and others

2007-06-15

The purpose of this work is to timely support the national science and technology policy through development of the advanced application techniques for neutron spectrometers, built in the previous project, in order to improve the neutron spectrometer techniques up to the world-class level in both quantity and quality and to reinforce industrial competitiveness. The importance of the research and development (R and D) is as follows: 1. Technological aspects - Development of a high value-added technology through performing the advanced R and D in the broad research areas from basic to applied science and from hard to soft condensed matter using neutron scattering technique. - Achievement of an important role in development of the new technology for the following industries aerospace, defense industry, atomic energy, hydrogen fuel cell etc. by the non-destructive inspection and analysis using neutron radiography. - Development of a system supporting the academic-industry users for the HANARO facility 2. Economical and Industrial Aspects - Essential technology in the industrial application of neutron spectrometer, in the basic and applied research of the diverse materials sciences, and in NT, BT, and IT areas - Broad impact on the economics and the domestic and international collaborative research by using the neutron instruments in the mega-scale research facility, HANARO, that is a unique source of neutron in Korea. 3. Social Aspects - Creating the scientific knowledge and contributing to the advanced industrial society through the neutron beam application - Improving quality of life and building a national consensus on the application of nuclear power by developing the RT fusion technology using the HANARO facility. - Widening the national research area and strengthening the national R and D capability by performing advanced R and D using the HANARO facility.

Development of advanced neutron beam technology

International Nuclear Information System (INIS)

Seong, B. S.; Lee, J. S.; Sim, C. M.

2007-06-01

The purpose of this work is to timely support the national science and technology policy through development of the advanced application techniques for neutron spectrometers, built in the previous project, in order to improve the neutron spectrometer techniques up to the world-class level in both quantity and quality and to reinforce industrial competitiveness. The importance of the research and development (R and D) is as follows: 1. Technological aspects - Development of a high value-added technology through performing the advanced R and D in the broad research areas from basic to applied science and from hard to soft condensed matter using neutron scattering technique. - Achievement of an important role in development of the new technology for the following industries aerospace, defense industry, atomic energy, hydrogen fuel cell etc. by the non-destructive inspection and analysis using neutron radiography. - Development of a system supporting the academic-industry users for the HANARO facility 2. Economical and Industrial Aspects - Essential technology in the industrial application of neutron spectrometer, in the basic and applied research of the diverse materials sciences, and in NT, BT, and IT areas - Broad impact on the economics and the domestic and international collaborative research by using the neutron instruments in the mega-scale research facility, HANARO, that is a unique source of neutron in Korea. 3. Social Aspects - Creating the scientific knowledge and contributing to the advanced industrial society through the neutron beam application - Improving quality of life and building a national consensus on the application of nuclear power by developing the RT fusion technology using the HANARO facility. - Widening the national research area and strengthening the national R and D capability by performing advanced R and D using the HANARO facility

Cyrogenic Life Support Technology Development Project

Science.gov (United States)

Bush, David R.

2015-01-01

KSC has used cryogenic life support (liquid air based) technology successfully for many years to support spaceflight operations. This technology has many benefits unique to cryogenics when compared to traditional compressed gas systems: passive cooling, lighter, longer duration, and lower operating pressure. However, there are also several limiting factors that have prevented the technology from being commercialized. The National Institute of Occupational Safety and Health, Office of Mine Safety and Health Research (NIOSH-OMSHR) has partnered with NASA to develop a complete liquid air based life support solution for emergency mine escape and rescue. The project will develop and demonstrate various prototype devices and incorporate new technological innovations that have to date prevented commercialization.

Advances in Robotic Servicing Technology Development

Science.gov (United States)

Gefke, Gardell G.; Janas, Alex; Pellegrino, Joseph; Sammons, Matthew; Reed, Benjamin

2015-01-01

NASA's Satellite Servicing Capabilities Office (SSCO) has matured robotic and automation technologies applicable to in-space robotic servicing and robotic exploration over the last six years. This paper presents the progress of technology development activities at the Goddard Space Flight Center Servicing Technology Center and on the ISS, with an emphasis on those occurring in the past year. Highlighted advancements are design reference mission analysis for servicing in low Earth orbit (LEO) and asteroid redirection; delivery of the engineering development unit of the NASA Servicing Arm; an update on International Space Station Robotic Refueling Mission; and status of a comprehensive ground-based space robot technology demonstration expanding in-space robotic servicing capabilities beginning fall 2015.

Development of high burnup nuclear fuel technology

International Nuclear Information System (INIS)

Suk, Ho Chun; Kang, Young Hwan; Jung, Jin Gone; Hwang, Won; Park, Zoo Hwan; Ryu, Woo Seog; Kim, Bong Goo; Kim, Il Gone

1987-04-01

The objectives of the project are mainly to develope both design and manufacturing technologies for 600 MWe-CANDU-PHWR-type high burnup nuclear fuel, and secondly to build up the foundation of PWR high burnup nuclear fuel technology on the basis of KAERI technology localized upon the standard 600 MWe-CANDU- PHWR nuclear fuel. So, as in the first stage, the goal of the program in the last one year was set up mainly to establish the concept of the nuclear fuel pellet design and manufacturing. The economic incentives for high burnup nuclear fuel technology development are improvement of fuel utilization, backend costs plant operation, etc. Forming the most important incentives of fuel cycle costs reduction and improvement of power operation, etc., the development of high burnup nuclear fuel technology and also the research on the incore fuel management and safety and technologies are necessary in this country

Transmutation Technology Development

Energy Technology Data Exchange (ETDEWEB)

Song, T. Y.; Park, W. S.; Kim, Y. H. (and others)

2007-06-15

The spent fuel coming from the PWR is one of the most difficult problems to be solved for the continuous use of nuclear power. It takes a few million years to be safe under the ground. Therefore, it is not easy to take care of the spent fuel for such a long time. Transmutation technology is the key technology which can solve the spent fuel problem basically. Transmutation is to transmute long-lived radioactive nuclides in the spent fuel into short-lived or stable nuclide through nuclear reactions. The long-lived radioactive nuclides can be TRU and fission products such as Tc-99 and I-129. Although the transmutation technology does not make the underground disposal totally unnecessary, the period to take care of the spent fuel can be reduced to the order of a few hundred years. In addition to the environmental benefit, transmutation can be considered to recycle the energy in the spent fuel since the transmutation is performed through nuclear fission reaction of the TRU in the spent fuel. Therefore, transmutation technology is worth being developed in economical aspect. The results of this work can be a basis for the next stage research. The objective of the third stage research was to complete the core conceptual design and verification of the key technologies. The final results will contribute to the establishment of Korean back end fuel cycle policy by providing technical guidelines.

History of nuclear technology development in Japan

Energy Technology Data Exchange (ETDEWEB)

Yamashita, Kiyonobu, E-mail: yamashita.kiyonobu@jaea.go.jp [Visiting Professor, at the Faculty of Petroleum and Renewable Energy Engineering, University Teknologi Malaysia Johor Bahru 81310 (Malaysia); General Advisor Nuclear HRD Centre, Japan Atomic Energy Agency, TOKAI-mura, NAKA-gun, IBARAKI-ken, 319-1195 (Japan)

2015-04-29

Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident.

History of nuclear technology development in Japan

Science.gov (United States)

Yamashita, Kiyonobu

2015-04-01

Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident.

History of nuclear technology development in Japan

International Nuclear Information System (INIS)

Yamashita, Kiyonobu

2015-01-01

Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident

Ocean Technology Development Tank

Data.gov (United States)

Federal Laboratory Consortium — The new SWFSC laboratory in La Jolla incorporates a large sea- and fresh-water Ocean Technology Development Tank. This world-class facility expands NOAA's ability to...

Technological capacity as an element of development strategy

Energy Technology Data Exchange (ETDEWEB)

Weiss, C; Kamenetzky, M; Ramesh, J

1980-03-01

The idea that science and technology transfers would result in the development of indigenous infrastructures able to cope with social problems overlooked the costs and uncertainties of applying science and technology to modernizing industry. A local capacity to deal with development is not emerging in developing countries and the role of small-scale technology has been largely ignored. A technological capacity needs to be built from within the public and private sectors, with adequate financial and technical support for small production units and adequate sheltering for long-term problems. Public policies are needed which can assess the fitness of technological institutions and policies to develop a capacity for making technological decisions that are compatible with local supply. 12 references. (DCK)

Developing countries: small technology with big effects

International Nuclear Information System (INIS)

McRobie, G.; Carr, M.

1978-01-01

As far the poor countries of the world are concerned, during the past twenty years they have had access only to the technologies developed by the rich to suit the rich. It is now beyond question that some of the most daunting problems confronting the majority of the worlds populations stem directly from the kind of technology transferred to them under current aid and development programs. That the technology of the rich is generally inappropriate to meet the needs and resources of the poor countries is becoming more widley recognized both by aid-givers and aid-receivers. Yet it is this technology that continues to be almost exclusively and most powerfully promoted in the developing countries. To meet their needs a new technology must be discovered or devised: one that lies between the sickle and the combine harvester and is small, simple and cheap enough to harmonise withlocal human and material resources and lends itself to widespread reproduction with the minimum of outside help. What we now need most urgently is a new set of technologies, designed, by people who are informed by the need to develop capital-saving technologies capable of being decentralized to the maximum extend. The technology gap is not only wide, but the knowledge an resources required to fill is, although they exist in the industrialized countries, have not been mobilized to provide the right kind of knowledge and to make it available to those who need it. It was to do this that the Intermediate Technology Development Group was set up ten years ago. (orig.) 891 HP 892 EKI [de

CROSSCUTTING TECHNOLOGY DEVELOPMENT AT THE CENTER FOR ADVANCED SEPARATION TECHNOLOGIES

Energy Technology Data Exchange (ETDEWEB)

Hugh W. Rimmer

2004-05-12

This Technical Progress Report describes progress made on the seventeen subprojects awarded in the first year of Cooperative Agreement DE-FC26-02NT41607: Crosscutting Technology Development at the Center for Advanced Separation Technologies. This work is summarized in the body of the main report: the individual sub-project Technical Progress Reports are attached as Appendices. Due to the time taken up by the solicitation/selection process, these cover the initial 6-month period of project activity only. The U.S. is the largest producer of mining products in the world. In 1999, U.S. mining operations produced $66.7 billion worth of raw materials that contributed a total of $533 billion to the nation's wealth. Despite these contributions, the mining industry has not been well supported with research and development funds as compared to mining industries in other countries. To overcome this problem, the Center for Advanced Separation Technologies (CAST) was established to develop technologies that can be used by the U.S. mining industry to create new products, reduce production costs, and meet environmental regulations. Originally set up by Virginia Tech and West Virginia University, this endeavor has been expanded into a seven-university consortium--Virginia Tech, West Virginia University, University of Kentucky, University of Utah, Montana Tech, New Mexico Tech and University of Nevada, Reno--that is supported through U.S. DOE Cooperative Agreement No. DE-FC26-02NT41607: Crosscutting Technology Development at the Center for Advanced Separation Technologies. Much of the research to be conducted with Cooperative Agreement funds will be longer-term, high-risk, basic research and will be carried out in five broad areas: (1) Solid-solid separation (2) Solid-liquid separation (3) Chemical/Biological Extraction (4) Modeling and Control, and (5) Environmental Control.

Hypersonic Inflatable Aerodynamic Decelerator (HIAD) Technology Development Overview

Science.gov (United States)

Hughes, Stephen J.; Cheatwood, F. McNeil; Calomino, Anthony M.; Wright, Henry S.; Wusk, Mary E.; Hughes, Monica F.

2013-01-01

The successful flight of the Inflatable Reentry Vehicle Experiment (IRVE)-3 has further demonstrated the potential value of Hypersonic Inflatable Aerodynamic Decelerator (HIAD) technology. This technology development effort is funded by NASA's Space Technology Mission Directorate (STMD) Game Changing Development Program (GCDP). This paper provides an overview of a multi-year HIAD technology development effort, detailing the projects completed to date and the additional testing planned for the future.

ISV technology development plan for buried waste

International Nuclear Information System (INIS)

Nickelson, D.F.; Callow, R.A.; Luey, J.K.

1992-07-01

This report identifies the main technical issues facing the in situ vitrification (ISV) application to buried waste, and presents a plan showing the top-level schedule and projected resources needed to develop and demonstrate the technology for meeting Environmental Restoration Department (ERD) needs. The plan also proposes a model strategy for the technology transfer from the Department of Energy's Office of Technology Development (DOE-OTD) to the Office of Environmental Restoration (DOE-ER) as the technology proceeds from issues resolution (development) to demonstration and remedial readiness. Implementation of the plan would require $34,91 1K in total funding to be spread in the years FY-93 through FY-98. Of this amount, $10,183K is planned to be funded by DOE-OTD through the ISV Integrated Program. The remaining amount, $24,728K, is recommended to be split between the Department of Energy (DOE) Office of Technology Development ($6,670K) and DOE Office of Environmental Restoration ($18,058K)

The development of information technologies

Directory of Open Access Journals (Sweden)

Kostúr Karol

2002-12-01

Full Text Available The contribution analyses the tasks information technologies in industry. At present time is the problem of connecting mutual variously levels of management. Therefore, first priority is an integration of information technologies. The information technologies for enterprise management are analysed. The product SAP R/3 appears as suitable for top management. The SAP R/3 Enterprise has a new technology so call web-server. This server enables the integration with e-business. The development my SAP is based on application of Business information warehouse (BW and Strategic enterprise management (SEM. The cheaper products (SPIN + EVIS are characterized too. Whitness Miner is very interesting system. The contribution this technology is programming realization of method KDD – knowledge discovery in databases.

The Clean Development Mechanism and neglected environmental technologies

International Nuclear Information System (INIS)

Kim, Jung Eun; Popp, David; Prag, Andrew

2013-01-01

The Clean Development Mechanism (CDM) provides an institutional framework for developed countries to support projects that reduce greenhouse gas emissions in developing countries. Are the technologies promoted those most needed by the recipient countries? We address this question by first reviewing Technology Needs Assessments prepared by developing countries, and then comparing the stated needs to the technologies most frequently promoted via CDM. While there appears to be a good match between requested technologies and those used in CDM, desired technologies such as solar energy for remote locations, biofuels, improved cooking stoves, and efficient lighting appear “neglected” by CDM. Nonetheless, a review of costs for these technologies suggests that many could be cost effective for developing countries. For projects requiring wide dispersal of household items, such as cooking stoves or lighting, the administrative burdens of CDM provide a hurdle. In other cases, difficulties quantifying the ancillary benefits of these projects hinder the promotion of these technologies. We conclude with possible explanations for why these technologies are neglected and suggestions for future research. - Highlights: ► We identify technologies desired by developing countries but not provided via CDM. ► Solar PV is neglected due to high costs. ► The CDM process provides a hurdle for improved cooking stoves and efficient lighting. ► Implications for CDM and climate policy are discussed

Incorporating regulatory considerations into waste treatment technology development

International Nuclear Information System (INIS)

Siegel, M.R.; Powell, J.A.; Williams, T.A.; Kuusinen, T.L.; Lesperance, A.M.

1991-02-01

It is generally recognized that the development of new and innovative waste treatment technologies can significantly benefit the US Department of Energy's (DOE) environmental restoration and waste management program. DOE has established a research, development, demonstration, testing, and evaluation (RDDT ampersand E) program, managed by its Office of Technology Development, to encourage and direct the development of new waste treatment and management technologies. The treatment, storage, and disposal of hazardous and radioactive waste is heavily regulated both at the federal and state levels. In order to achieve the goals of applying the best new technologies in the fastest and most cost-effective manner possible, it is essential that regulatory factors be considered early and often during the development process. This paper presents a number of regulatory issues that are relevant to any program intended to encourage the development of new waste treatment and management technologies. It will also address how the use of these basic regulatory considerations can help ensure that technologies that are developed are acceptable to regulators and can therefore be deployed in the field. 2 refs

Technology as a factor of identity transformation: development of HOMO TECHNOLOGIES

Directory of Open Access Journals (Sweden)

Vadim A. Emelin

2016-03-01

Full Text Available Based on the understanding of identity as an individual’s identity with the self within the cultural historical chronotope, and experienced as the feeling of belonging/ non-belonging to some communities, controllability/uncontrollability of situations and predictability/non-predictability of events, the paper describes the processes of identity transformation in the course of a technological development. Taken as the initial point, the idea of organ-extension (K. Marx, E. Kapp and technological extension of man (S. Freud, M. McLuhan means that technologies are the extension of a human body and its organs. The processes of technological extension assume a particular scale under condition of information society development, within which computer-, telecommunication-, transport-, bio-, nano- and other high technologies have become an actual cultural historical force that has a power to transform a human. Special attention is paid to the fact that unlike the precedent technologies that have just facilitated some or other human performance, modern technologies of information society do not only change the human topology, widen and expand human natural abilities but also really transform higher mental functions and mediate mental processes and relations between human individuals. Man becomes not only a biological and social creature but also a technological one, i.e. so called HOMO TECHNOLOGICUS. The scale and speed of cultural historical changes make the study of the technological extensions role in the transformation of identity a key point for developing ways of comprehending their role in the life of a modern person, and also for forecasting the evolution of relationship between man and machines in the future.

Technology developments for improved tritium management

International Nuclear Information System (INIS)

Miller, J.M.; Spagnolo, D.A.

1994-06-01

Tritium technology developments have been an integral part of the advancement of CANDU reactor technology. An understanding of tritium behaviour within the heavy-water systems has led to improvements in tritium recovery processes, tritium measurement techniques and overall tritium control. Detritiation technology has been put in place as part of heavy water and tritium management practices. The advances made in these technologies are summarized. (author). 20 refs., 5 figs

SRS environmental technology development field test platform

International Nuclear Information System (INIS)

Riha, B.D.; Rossabi, J.; Eddy-Dilek, C.A.

1995-01-01

A critical and difficult step in the development and implementation of new technologies for environmental monitoring and characterization is successfully transferring these technologies to industry and government users for routine assessment and compliance activities. The Environmental Sciences Section of the DOE Savannah River Technology Center provides a forum for developers, potential users, and regulatory organizations to evaluate new technologies in comparison with baseline technologies in a well characterized field test bed. The principal objective of this project is to conduct comprehensive, objective field tests of monitoring and characterization technologies that are not currently used in EPA standard methods and evaluate their performance during actual operating conditions against baseline methods. This paper provides an overview of the field test site and a description of some of the technologies demonstrated at the site including their field applications

Design of LSDS for Isotopic Fissile Assay in Spent Fuel

International Nuclear Information System (INIS)

Lee, Yongdeok; Park, Changje; Kim, Hodong; Song, Kee Chan

2013-01-01

A future nuclear energy system is being developed at Korea Atomic Energy Research Institute (KAERI), the system involves a Sodium Fast Reactor (SFR) linked with the pyro-process. The pyro-process produces a source material to fabricate a SFR fuel rod. Therefore, an isotopic fissile content assay is very important for fuel rod safety and SFR economics. A new technology for an analysis of isotopic fissile content has been proposed using a lead slowing down spectrometer (LSDS). The new technology has several features for a fissile analysis from spent fuel: direct isotopic fissile assay, no background interference, and no requirement from burnup history information. Several calculations were done on the designed spectrometer geometry: detection sensitivity, neutron energy spectrum analysis, neutron fission characteristics, self shielding analysis, and neutron production mechanism. The spectrum was well organized even at low neutron energy and the threshold fission chamber was a proper choice to get prompt fast fission neutrons. The characteristic fission signature was obtained in slowing down neutron energy from each fissile isotope. Another application of LSDS is for an optimum design of the spent fuel storage, maximization of the burnup credit and provision of the burnup code correction factor. Additionally, an isotopic fissile content assay will contribute to an increase in transparency and credibility for the utilization of spent fuel nuclear material, as internationally demanded

DESIGN OF LSDS FOR ISOTOPIC FISSILE ASSAY IN SPENT FUEL

Directory of Open Access Journals (Sweden)

YONGDEOK LEE

2013-12-01

Full Text Available A future nuclear energy system is being developed at Korea Atomic Energy Research Institute (KAERI, the system involves a Sodium Fast Reactor (SFR linked with the pyro-process. The pyro-process produces a source material to fabricate a SFR fuel rod. Therefore, an isotopic fissile content assay is very important for fuel rod safety and SFR economics. A new technology for an analysis of isotopic fissile content has been proposed using a lead slowing down spectrometer (LSDS. The new technology has several features for a fissile analysis from spent fuel: direct isotopic fissile assay, no background interference, and no requirement from burnup history information. Several calculations were done on the designed spectrometer geometry: detection sensitivity, neutron energy spectrum analysis, neutron fission characteristics, self shielding analysis, and neutron production mechanism. The spectrum was well organized even at low neutron energy and the threshold fission chamber was a proper choice to get prompt fast fission neutrons. The characteristic fission signature was obtained in slowing down neutron energy from each fissile isotope. Another application of LSDS is for an optimum design of the spent fuel storage, maximization of the burnup credit and provision of the burnup code correction factor. Additionally, an isotopic fissile content assay will contribute to an increase in transparency and credibility for the utilization of spent fuel nuclear material, as internationally demanded.

A study on artificial rare earth (RE2O3) based neutron absorber

International Nuclear Information System (INIS)

KIM, Kyung-O; Kyung KIM, Jong

2015-01-01

A new concept of a neutron absorption material (i.e., an artificial rare earth compound) was introduced for criticality control in a spent fuel storage system. In particular, spent nuclear fuels were considered as a potential source of rare earth elements because the nuclear fission of uranium produces a full range of nuclides. It was also found that an artificial rare earth compound (RE 2 O 3 ) as a High-Level Waste (HLW) was naturally extracted from pyroprocessing technology developed for recovering uranium and transuranic elements (TRU) from spent fuels. In this study, various characteristics (e.g., activity, neutron absorption cross-section) were analyzed for validating the application possibility of this waste compound as a neutron absorption material. As a result, the artificial rare earth compound had a higher neutron absorption probability in the entire energy range, and it can be used for maintaining sub-criticality for more than 40 years on the basis of the neutron absorption capability of Boral™. Therefore, this approach is expected to vastly improve the efficiency of radioactive waste management by simultaneously keeping HLW and spent nuclear fuel in a restricted space. - Highlights: • Quantitative analysis of rare earth elements in PWR spent fuels. • Extraction of artificial rare earth compound using pyroprocessing technology. • Characteristic analysis of artificial rare earth elements. • Performance evaluation of artificial rare earth for criticality control.

Development of isotope hydrology technology in China

International Nuclear Information System (INIS)

Li Zhangsu

1988-01-01

The development of isotope hydrology technology in China is described. The isotope technology provides an independent approach for solving hydrological problems. Isotope hydrology is applied in three ways: the use of change in environmental isotopic composition of water (especially used in water resources exploitation), the use of artificial radioactive tracers and the use of redioisotope instruments. Many important achievements have been obtained in application of isotopic hydrology technology. For the sake of promoting rapid development of isotope hydrology the topics on management, technology and others are commented

Fire Safety Consideration in the Pre-conceptual Design State of Pyro-Facillity

Energy Technology Data Exchange (ETDEWEB)

Jeon, Hong Rae; Seo, Seok Jun; Lee, Hyo Jik [KAERI, Daejeon (Korea, Republic of)

2016-05-15

The government, in order to solve this problem, has organized a public engagement committee and is searching for a solution. To use sustainable nuclear energy, our country is also pursuing research and development of fast breeder reactor and pyroprocessing technology in accordance with the international movement of spent fuel recycling and efforts towards nuclear non-proliferation which is centered on the development and demonstration of recycling spent fuel and fast breeder reactors. Pyro-facility has different features with nuclear power plant. In the pyroprocess, chemical and electrochemical separation were took place in the hot cells and material at risk (MAR) is distributed in many working areas. In this paper, we conducted the fire modeling of hot cells to see the stability of pyrophoric materials which is considered as one of the potential hazardous materials in the main process cell. Based on modeling results, consideration of fire safety pyrofacility will be discussed. We performed preliminary hazard analysis for pyrofacility and summarized potential fire hazard. Pyrophoric material fire is the dominant hazard in the main process hot cell and fire modeling of cable tray in the cell was analyzed to see the stability of pyrophoric materials. Analysis results clearly shows that pyrophoric materials are prone to be affected.

competitive technologies for sustainable development

International Nuclear Information System (INIS)

Chriqui, Vincent; Bergougnoux, Jean; Hossie, Gaelle; Beeker, Etienne; Buba, Johanne; Delanoe, Julien; Ducos, Geraldine; Hilt, Etienne; Rigard-Cerison, Aude; Teillant, Aude; Auverlot, Dominique; Martinez, Elise; Dambrine, Fabrice; Roure, Francoise

2012-08-01

By letter dated 27 April 2011, the Director General of the Centre for Strategic Analysis, Vincent Chriqui, confided to Jean Bergougnoux, honorary president of the SNCF, Honorary General Director of EDF, the task of animating a reflection Prospective Technological Studies of the sectors of energy, transport and construction. This synthesis report, prepared with the assistance of rapporteurs Centre for Strategic Analysis, attempts to summarize and put into perspective all the work which show these specific reports. Admittedly some very complex issues still need supplements. It may therefore be useful to extend this work in a number of areas. Beyond its role in the competitiveness of a country, technological innovation is essential to provide appropriate responses to the challenges of our commitment to sustainable development in terms of economic growth, preservation of the environmental and social progress. Mission for Prospective Technological conducted by the Centre for Strategic Analysis has sought to clarify this dual problem by proposing a long-term vision for the energy, transport and construction. For each technology studied, it has attempted to assess both the possible contribution to sustainable development and the competitive potential of our country on the international scene. His work, chaired by Jean Bergougnoux have reviewed the technological advances that may occur in the coming decades in the sectors concerned. They examined the conditions for integration of these advances in systems and subsystems existing (or create) and the conditions of a mature technical, economic but also social. Wherever possible, two time horizons were identified: a medium-term horizon, 2030, for which we have a fairly clear vision of future developments and long-term horizon, 2050, which allows to consider jumps Scientists are still uncertain. Finally, the mission is interested in four transverse technologies involved consistently in the three study areas, which are likely to

Technologies for destruction of long-lived radionuclides in high-level nuclear waste: Overview and requirements

International Nuclear Information System (INIS)

Arthur, E.D.

1993-01-01

This paper, and this topical session on Nuclear Waste Minimization, Management and Remediation, focuses on two nuclear systems, and their associated technologies, that have the potential to address concerns surrounding long-lived radionuclides in high-level waste. Both systems offer technology applicable to HLW from present light-water reactors (LWR). Additionally these systems represent advanced nuclear power concepts that have important features associated with integrated management of wastes, long-term fuel supplies, and enhanced safety. The first system is the Integral Fast Reactor (IFR) concept. This system incorporates a metal-fueled fast reactor coupled with chemical separations based on pyroprocessing to produce power while simultaneously burning long-lived actinide waste. IFR applications include burning of actinides from current LWR spent fuel and energy production in a breeder environment. The second concept, Accelerator Transmutation of Waste (ATW), is based upon an accelerator-induced intense source of thermal neutrons and is aimed at destruction of long-lived actinides and fission products. This concept can be applied to long-lived radionuclides in spent fuel HLW as well as a future fission power source built around use of natural thorium or uranium as fuels coupled with concurrent waste destruction

Development of MMIS design technology for integral reactor

Energy Technology Data Exchange (ETDEWEB)

Koo, In Soo; Park, H. Y.; Lee, C. K. and others

1999-03-01

The objective of this study is to establish the concept design of the SMART MMIS through the setup of a structure and design concept of MMIS, the development of design methodology, and essential technologies for MMIS considering computer based digital technologies and human factors. Main activities of this study divided into three categories such as the development of conceptual design and requirement of the SMART I and C, the development of conceptual design and requirement of the SMART MMI, and essential technology for the MMIS. The results of main activities that have been performed during the study are as follows; 1) The review of licensing requirements and operating experience of existing plants. 2) The establishment of a system design concept about development strategy, basic functions and requirements, and applicable technology through the adoption of digital technology and human factorsengineering. 3) The accomplishment of function, structure, and design requirement of each MMIS through the performance of conceptual design on system structure and actuation logic using function analysis. It is necessary to develop and apply new technologies for the MMIS design compatible with the design basis of SMART. Considered essential technologies for the MMIS in this study are 1) the development of a signal validation algorithm and sensor diagnosis technique 2) the development of a soft controller for operator's action 3) the establishment of a data communication structure for MMIS architecture 4) the development of an information optimization basis and automatic start-up algorithm 5) the development of sensor reduction requirements 6) the development of a qualification method of digital equipment for applied digital technology and commercial grade items. (author)

Development of MMIS design technology for integral reactor

International Nuclear Information System (INIS)

Koo, In Soo; Park, H. Y.; Lee, C. K. and others

1999-03-01

The objective of this study is to establish the concept design of the SMART MMIS through the setup of a structure and design concept of MMIS, the development of design methodology, and essential technologies for MMIS considering computer based digital technologies and human factors. Main activities of this study divided into three categories such as the development of conceptual design and requirement of the SMART I and C, the development of conceptual design and requirement of the SMART MMI, and essential technology for the MMIS. The results of main activities that have been performed during the study are as follows; 1) The review of licensing requirements and operating experience of existing plants. 2) The establishment of a system design concept about development strategy, basic functions and requirements, and applicable technology through the adoption of digital technology and human factors engineering. 3) The accomplishment of function, structure, and design requirement of each MMIS through the performance of conceptual design on system structure and actuation logic using function analysis. It is necessary to develop and apply new technologies for the MMIS design compatible with the design basis of SMART. Considered essential technologies for the MMIS in this study are 1) the development of a signal validation algorithm and sensor diagnosis technique 2) the development of a soft controller for operator's action 3) the establishment of a data communication structure for MMIS architecture 4) the development of an information optimization basis and automatic start-up algorithm 5) the development of sensor reduction requirements 6) the development of a qualification method of digital equipment for applied digital technology and commercial grade items. (author)

China's High-technology Standards Development

Institute of Scientific and Technical Information of China (English)

无

2007-01-01

There are several major technology standards, including audio video coding (AVS), automotive electronics, third generation (3G) mobile phones, mobile television, wireless networks and digital terrestrial television broadcasting, that have been released or are currently under development in China. This article offers a detailed analysis of each standard and studies their impact on China's high-technology industry.

Technologies in support of CANDU development

International Nuclear Information System (INIS)

Turner, C.; Tapping, B.

2005-01-01

Atomic Energy of Canada, Ltd. (AECL) has significant research and development (R and D) programs designed to meet the needs of both existing CANDU reactors and new and evolving CANDU plant designs. These R and D programs cover a wide range of technology, from chemistry and materials support through to inspection and life management tools. Emphasis is placed on effective technology development programs for fuel channels, feeders and steam generators to ensure their operation through design life, and beyond. This paper specifically addresses how the R and D has been applied in the production of longer-lived pressure tubes for the most recent CANDU 6 reactors, and how this technology forms the basis for the pressure tubes of the Advanced CANDU Reactor (ACR). Similarly, AECL has developed solutions for other critical components such as calandria tubes, feeder pipe and steam generators. The paper also discusses how the R and D knowledge has been integrated into aging management databases and health monitoring tools. Since 1997, AECL has been working with CANDU utilities on comprehensive and integrated CANDU Plant Life Management (PLiM) programs for successful and reliable plant operation through design life and beyond. AECL has developed and implemented an advanced chemistry monitoring and diagnostic system, called ChemAND which allows on-line access by the operators to current and past chemistry conditions enabling appropriate responses and facilitating planning of shutdown maintenance actions. An equivalent tool for monitoring, trending and diagnosing thermal and mechanical data has also been developed; this tool is called ThermAND. AECL is developing the Maintenance Information, Monitoring, and Control (MIMC) system, which provide information to the user for condition-based decision-making in maintenance. To enable more effective inspections, surveillance and data collection, AECL has developed unique one-off tooling to carry out unanticipated inspection and repair

AFCI Safeguards Enhancement Study: Technology Development Roadmap

Energy Technology Data Exchange (ETDEWEB)

Smith, Leon E.; Dougan, A.; Tobin, Stephen; Cipiti, B.; Ehinger, Michael H.; Bakel, A. J.; Bean, Robert; Grate, Jay W.; Santi, P.; Bryan, Steven; Kinlaw, M. T.; Schwantes, Jon M.; Burr, Tom; Lehn, Scott A.; Tolk, K.; Chichester, David; Menlove, H.; Vo, D.; Duckworth, Douglas C.; Merkle, P.; Wang, T. F.; Duran, F.; Nakae, L.; Warren, Glen A.; Friedrich, S.; Rabin, M.

2008-12-31

The Advanced Fuel Cycle Initiative (AFCI) Safeguards Campaign aims to develop safeguards technologies and processes that will significantly reduce the risk of proliferation in the U.S. nuclear fuel cycle of tomorrow. The Safeguards Enhancement Study was chartered with identifying promising research and development (R&D) directions over timescales both near-term and long-term, and under safeguards oversight both domestic and international. This technology development roadmap documents recognized gaps and needs in the safeguarding of nuclear fuel cycles, and outlines corresponding performance targets for each of those needs. Drawing on the collective expertise of technologists and user-representatives, a list of over 30 technologies that have the potential to meet those needs was developed, along with brief summaries of each candidate technology. Each summary describes the potential impact of that technology, key research questions to be addressed, and prospective development milestones that could lead to a definitive viability or performance assessment. Important programmatic linkages between U.S. agencies and offices are also described, reflecting the emergence of several safeguards R&D programs in the U.S. and the reinvigoration of nuclear fuel cycles across the globe.

Development of NDT technology of the welds

International Nuclear Information System (INIS)

Li Jianwen; Xu Yansen; Wang Zengyong

2002-01-01

Non-destructive testing (NDT) and its up-to-date development are summarized, including the advantages and disadvantages and the development of NDT technology. The up-to-date development of X-ray imaging and industrial CT is emphasised on, and the fundamental theory of ultrasonic imaging and related signal processing technology is introduced

Development of NDT technology of the welds

Energy Technology Data Exchange (ETDEWEB)

Jianwen, Li; Yansen, Xu; Zengyong, Wang [China Academy of Engineering Physics, Mianyang (China). Inst. of Mechanical Engineering

2002-07-01

Non-destructive testing (NDT) and its up-to-date development are summarized, including the advantages and disadvantages and the development of NDT technology. The up-to-date development of X-ray imaging and industrial CT is emphasised on, and the fundamental theory of ultrasonic imaging and related signal processing technology is introduced.

Development of liquid type TBM technology for ITER

International Nuclear Information System (INIS)

Lee, Dong Won; Kim, S. K.; Yoon, J. S.

2012-03-01

The final objectives of this project are as follows; Development of the key techniques for the liquid type TBM for ITER: Developing plan for leading and participating liquid TBM concepts; Estimating cost and schedule according to development schedule and managing technologies; Developing integrated design system and completing the engineering design for liquid TBM; Developing the key technologies for the liquid TBM; Construction of performance test systems for liquid TBM and verification of the performance. We are technically surveying the ITER system design data, the insufficient part of ITER design, and required R and D items and so on. In Korea, HCML TBM, liquid type breeder with lithium or lead lithium, has been studied during the past years to develop a tritium breeding technology for tritium self-sufficiency of nuclear fusion reactor and the TBM was proposed to be tested in ITER. In this study, we can obtain the key technology of nuclear fusion reactor especially on the TBM design, analysis and manufacturing technology through the present project and these technologies will help the construction of Korea fusion DEMO reactor and the development of commercial nuclear fusion reactor in Korea

Technological opportunities and paths of development

DEFF Research Database (Denmark)

Plichta, Kirsten

1993-01-01

the outcome of different firms development effort may also help shape a path at the industry level. This may be because the criteria by which the market selects between the different product may to some extent be anticipated by the developing firms or because the criteria by which the market select betwee...... technological knowledge, their production, development and other routines as well prior investments in products and production equipment play an important role with regard to the technological opportunities that firms' identify and select for development. 3) Because history matters and because firms are bounded...... in the industry. 6) It is argued that such paths of incremental improvement at the industry level may be an outcome of a) the dynamics that produce the technological opportunities; b) the institutions that govern decisions and expectations and c) the criteria by which the chooses between different firms...

Industrial Arts Test Development, Book III. Resource Items for Graphics Technology, Power Technology, Production Technology.

Science.gov (United States)

New York State Education Dept., Albany.

This booklet is designed to assist teachers in developing examinations for classroom use. It is a collection of 955 objective test questions, mostly multiple choice, for industrial arts students in the three areas of graphics technology, power technology, and production technology. Scoring keys are provided. There are no copyright restrictions,…

Definition of Technology Readiness Levels for Transmutation Fuel Development

International Nuclear Information System (INIS)

Jon Carmack; Kemal O. Pasamehmetoglu

2008-01-01

To quantitatively assess the maturity of a given technology, the Technology Readiness Level (TRL) process is used. The TRL process has been developed and successfully used by the Department of Defense (DOD) for development and deployment of new technology and systems for defense applications. In addition, NASA has also successfully used the TRL process to develop and deploy new systems for space applications. Transmutation fuel development is a critical technology needed for closing the nuclear fuel cycle. Because the deployment of a new nuclear fuel forms requires a lengthy and expensive research, development, and demonstration program, applying the TRL concept to the transmutation fuel development program is very useful as a management and tracking tool. This report provides definition of the technology readiness level assessment process as defined for use in assessing nuclear fuel technology development for the Transuranic Fuel Development Campaign

Development of radioisotope tracer technology

International Nuclear Information System (INIS)

Jin, Joon Ha; Lee, Myun Joo; Jung, Sung Hee; Park, Soon Chul; Lim, Dong Soon; Kim, Jae Ho; Lee, Jae Choon; Lee, Doo Sung; Cho, Yong Suk; Shin, Sung Kuan

2000-04-01

The purpose of this study is to develop the radioisotope tracer technology, which can be used in solving industrial and environmental problems and to build a strong tracer group to support the local industries. In relation to the tracer technology in 1999, experiments to estimate the efficiencies of a sludge digester of a waste water treatment plant and a submerged biological reactor of a dye industry were conducted. As a result, the tracer technology for optimization of facilities related to wastewater treatment has been developed and is believed to contribute to improve their operation efficiency. The quantification of the experimental result was attempted to improve the confidence of tracer technology by ECRIN program which basically uses the MCNP simulation principle. Using thin layer activation technique, wear of tappet shim was estimated. Thin layer surface of a tappet shim was irradiated by proton beam and the correlation between the measured activity loss and the amount of wear was established. The equipment was developed to adjust the energy of proton which collides with the surface of tappet. The tracer project team has participated into the tracer test for estimating the efficiency of RFCC system in SK cooperation. From the experiment the tracer team has obtained the primary elements to be considered for judging the efficiency of RFCC unit. By developing the tracer techniques to test huge industrial units like RFCC, the tracer team will be able to support the local industries that require technical services to solve any urgent trouble. (author)

Atoms in industry: Radiation technology supports development [Foreword

International Nuclear Information System (INIS)

Amano, Yukiya

2015-01-01

Cutting-edge industrial technologies underpin the success of strong economies, in developed and developing countries alike. Nuclear science and technology, in particular, can make a major contribution to economic growth and competitiveness, and have an important role to play in support of sustainable development. The IAEA helps to make nuclear science and technology available to enable countries to pursue wider development objectives in areas including human health, agriculture, natural resource management and environmental protection. This edition of the IAEA Bulletin highlights some of the ways in which the technology is being put to effective use in industry.

Technological Developments in Networking, Education and Automation

CERN Document Server

Elleithy, Khaled; Iskander, Magued; Kapila, Vikram; Karim, Mohammad A; Mahmood, Ausif

2010-01-01

"Technological Developments in Networking, Education and Automation" includes a set of rigorously reviewed world-class manuscripts addressing and detailing state-of-the-art research projects in the following areas: Computer Networks: Access Technologies, Medium Access Control, Network architectures and Equipment, Optical Networks and Switching, Telecommunication Technology, and Ultra Wideband Communications. Engineering Education and Online Learning: including development of courses and systems for engineering, technical and liberal studies programs; online laboratories; intelligent

Dry Refabrication Technology Development of Spent Nuclear Fuel

International Nuclear Information System (INIS)

Lee, Jung Won; Park, G. I.; Park, C. J.

2010-04-01

Key technical data on advanced nuclear fuel cycle technology development for the spent fuel recycling have been produced in this study. In the frame work of DUPIC, dry process oxide products fabrication, hot cell experimental data for decladding, powdering and oxide product fabrication from low and high burnup spent fuel have been produced, basic technology for fabrication of spent fuel standard material has been developed, and remote modulated welding equipment has been designed and fabricated. In the area of advanced pre-treatment process development, a rotary-type oxidizer and spherical particle fabrication process were developed by using SIMFUEL and off-gas treatment technology and zircalloy tube treatment technology were studied. In the area of the property characteristics of dry process products, fabrication technology of simulated dry process products was established and property models were developed based on reproducible property measurement data

Development of Nuclear Fuel Remote Fabrication Technology

International Nuclear Information System (INIS)

Lee, Jung Won; Yang, M. S.; Kim, S. S. and others

2005-04-01

The aim of this study is to develop the essential technology of dry refabrication using spent fuel materials in a laboratory scale on the basis of proliferation resistance policy. The emphasis is placed on the assessment and the development of the essential technology of dry refabrication using spent fuel materials. In this study, the remote fuel fabrication technology to make a dry refabricated fuel with an enhanced quality was established. And the instrumented fuel pellets and mini-elements were manufactured for the irradiation testing in HANARO. The design and development technology of the remote fabrication equipment and the remote operating and maintenance technology of the equipment in hot cell were also achieved. These achievements will be used in and applied to the future back-end fuel cycle and GEN-IV fuel cycle and be a milestone for Korea to be an advanced nuclear country in the world

Development of improved technology for decommissioning operations

International Nuclear Information System (INIS)

Allen, R.P.

1982-07-01

This paper describes the technology development activities conducted at Pacific Northwest Laboratory under US Department of Energy sponsorship to help ensure the availability of safe, cost-effective and environmentally sound decommissioning technology for radioactively contaminated facilities. These improved decommissioning technologies include techniques for the removal of contaminated concrete surfaces and coatings, adaptation of electropolishing and vibratory finishing decontamination techniques for field decommissioning applications, development of sensitive field instrumentation and methods for the monitoring of large surface areas, techniques for the field sectioning of contaminated components, improved contamination-stabilizing coatings and application methods, and development of a small solidification system for the field solidification of liquid waste. The results of cost/benefit studies for some of these technologies are also reported

Status of molten carbonate fuel cell technology development

Science.gov (United States)

Parsons, E. L., Jr.; Williams, M. C.; George, T. J.

The MCFC technology has been identified by the DOE as a promising product for commercialization. Development of the MCFC technology supports the National Energy Strategy. Review of the status of the MCFC technology indicates that the MCFC technology developers are making rapid and significant progress. Manufacturing facility development and extensive testing is occurring. Improvements in performance (power density), lower costs, improved packaging, and scale up to full height are planned. MCFC developers need to continue to be responsive to end-users in potential markets. It will be market demands for the correct product definition which will ultimately determine the character of MCFC power plants. There is a need for continued MCFC product improvement and multiple product development tests.

Joining technology development summary, 189a OH024

International Nuclear Information System (INIS)

Edmonds, D.P.

1978-01-01

Joining technology is discussed for Breeder Reactor technology including welding development and mechanical properties of weldments for austenitic stainless steels, high-temperature structural design data for austenitic stainless steel weldments and advanced transition joints is discussed. Technology developed in this program is briefly reviewed

Transferable site remediation technologies developed by U.S. DOE Office of Science and Technology

International Nuclear Information System (INIS)

Anderson, T.D.

1996-01-01

To provide needed technologies for site remediation, the US Department of Energy's Office of Environmental Management, Office of Science and Technology (OST) is developing technologies to address environmental problems associated with hazardous and radioactive contaminants in soil and groundwater. The Technology Investment Decision model serves as a framework for technology management in OST. Seven technology maturation stages are used in the model. These stages run from basic research through implementation. The Innovative Technology Summary Reports (ITSRs) provide a technical synopsis of an individual technology that has been developed. An ITSR is prepared for each technology that is successfully demonstrated in the field. The information required to produce an ITSR is collected as the technology matures through the Technology Investment Decision Process. As of July 1996 there have been thirteen ITSRs completed. This paper describes those thirteen technologies

ADVANCED TECHNOLOGIES OF ELECTRONIC EDUCATIONAL SYSTEMS DEVELOPMENT

Directory of Open Access Journals (Sweden)

M. Shishkina

2011-11-01

Full Text Available Actual problems and contradictions of electronic educational systems development are described: availability of education, quality of educational services; individualization of education; exposures and advantages in using of computer technology; standardization of technologies and resources. Tendencies of their solution in the view of development of new advanced technologies of e-education are specified. The essence and advantages of using the cloud computing technologies as a new platform of distributed learning are specified. Advanced directions of cloud-based data usage in executive system of education are declared: access management, content management, asset management, communications management.

VLBI Technology Development at SHAO

Science.gov (United States)

Zhang, Xiuzhong; Shu, Fengchun; Xiang, Ying; Zhu, Renjie; Xu, Zhijun; Chen, Zhong; Zheng, Weimin; Luo, Jintao; Wu, Yajun

2010-01-01

VLBI technology development made significant progress at SHAO in the last few years. The development status of the Chinese DBBC, the software and FPGA-based correlators, and the new VLBI antenna, as well as VLBI applications are summarized in this paper.

Development of high-level radioactive waste treatment and conversion technologies 'Dry decontamination technology development for highly radioactive contaminants'

Energy Technology Data Exchange (ETDEWEB)

Oh, Won Zin; Lee, K. W.; Won, H. J.; Jung, C. J.; Choi, W. K.; Kim, G. N.; Moon, J. K

2001-04-01

The followings were studied through the project entitled 'Dry Decontamination Technology Development for Highly Radioactive Contaminants'. 1.Contaminant Characteristics Analysis of Domestic Nuclear Fuel Cycle Projects(NFCP) and Applicability Study of the Unit Dry-Decontamination Techniques A. Classification of contaminated equipments and characteristics analysis of contaminants B. Applicability study of the unit dry-decontamination techniques 2.Performance Evaluation of Unit Dry Decontamination Technique A. PFC decontamination technique B. CO2 decontamination technique C. Plasma decontamination technique 3.Development of Residual Radiation Assessment Methodology for High Radioactive Facility Decontamination A. Development of radioactive nuclide diffusion model on highly radioactive facility structure B. Obtainment of the procedure for assessment of residual radiation dose 4.Establishment of the Design Concept of Dry Decontamination Process Equipment Applicable to Highly Radioactive Contaminants 5.TRIGA soil unit decontamination technology development A. Development of soil washing and flushing technologies B. Development of electrokinetic soil decontamination technology.

Technology development and transfer in environmental management

International Nuclear Information System (INIS)

Katz, J.; Karnovitz, A.; Yarbrough, M.

1994-01-01

Federal efforts to develop and employ the innovative technologies needed to clean up contaminated facilities would greatly benefit from a greater degree of interaction and integration with the energies and resources of the private sector. Yet there are numerous institutional, economic, and regulatory obstacles to the transfer and commercialization of environmental restoration and waste management technologies. These obstacles discourage private sector involvement and investment in Federal efforts to develop and use innovative technologies. A further effect is to impede market development even where private sector interest is high. Lowering these market barriers will facilitate the commercialization of innovative environmental cleanup technologies and expedite the cleanup of contaminated Federal and private facilities. This paper identifies the major barriers to transfer and commercialization of innovative technologies and suggests possible strategies to overcome them. Emphasis is placed on issues particularly relevant to the Department of Energy's Environmental Restoration and Waste Management (EM) program, but which are applicable to other Federal agencies confronting complex environmental cleanup problems

Technology management for environmentally sound and sustainable development

International Nuclear Information System (INIS)

Zaidi, S.M.J.

1992-01-01

With the evolutionary change in the production activities of human societies, the concept of development has also been changing. In the recent years the emphasis has been on the environmentally sound and sustainable development. The environmentally sound and sustainable development can be obtained through judicious use of technology. Technology as a resource transformer has emerged as the most important factor which can constitute to economic growth. But technology is not an independent and autonomous force, it is only an instrument which needs to be used carefully, properly and appropriately which necessitates technology management. (author)

Development of technologies for utilizing geothermal energy

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

In verifying the effectiveness of the deep geothermal resource exploration technology, development is being carried out on a fracture-type reservoir exploration method. The seismic exploration method investigates detailed structures of underground fracture systems by using seismic waves generated on the ground surface. Verification experiments for fiscal 1994 were carried out by selecting the Kakkonda area in which small fracture networks form reservoir beds. Geothermal resources in deep sections (deeper than 2000 m with temperatures higher than 350{degree}C) are promising in terms of amount of the resources, but anticipated with difficulty in exploration and impediments in drilling. To avoid these risks, studies are being progressed on the availability of resources in deep sections, their utilization possibility, and technologies of effective exploration and drilling. This paper summarizes the results of deep resource investigations during fiscal 1994. It also describes such technological development as hot water utilizing power generation. Development is performed on a binary cycle power generation plant which pumps and utilizes hot water of 150 to 200{degree}C by using a downhole pump. The paper also reports development on element technologies for hot rock power generation systems. It also dwells on development of safe and effective drilling and production technologies for deep geothermal resources.

Developing a Strategic Plan for NASA JSC's Technology Investments

Science.gov (United States)

Stecklein, Jonette M.

2012-01-01

Human space exploration has always been heavily influenced by goals to achieve a specific mission on a specific schedule. This approach drove rapid technology development, the rapidity of which adds risks as well as provides a major driver for costs. The National Aeronautics and Space Administration (NASA) is now approaching the extension of human presence throughout the solar system by balancing a proactive yet less schedule-driven development of technology with opportunistic scheduling of missions as the needed technologies are realized. This approach should provide cost effective, low risk technology development that will enable efficient and effective manned spaceflight missions. As a first step, the NASA Human Spaceflight Architecture Team (HAT) has identified a suite of critical technologies needed to support future manned missions across a range of destinations, including in cislunar space, near earth asteroid visits, lunar exploration, Mars space, and Mars exploration. The challenge now is to develop a strategy and plan for technology development that efficiently enables these missions over a reasonable time period, without increasing technology development costs unnecessarily due to schedule pressure, and subsequently mitigating development and mission risks. NASA fs Johnson Space Center (JSC), as the nation's primary center for human exploration, is addressing this challenge through an innovative approach allocating Internal Research and Development funding to projects that have been prioritized using four focus criteria, with appropriate importance weighting. These four focus criteria are the Human Space Flight Technology Needs, JSC Core Technology Competencies, Commercialization Potential, and Partnership Potential. The inherent coupling in these focus criteria have been captured in a database and have provided an initial prioritization for allocation of technology development research funding. This paper will describe this process and this database

Driving forces and barriers for environmental technology development

International Nuclear Information System (INIS)

2005-01-01

Driving forces and barriers behind development and usage of environmental technology is discussed, and also whether there are certain characteristics related to environmental innovations compared to other innovations in general. The development of environmental technology is in principle dominated by the same drivers and barriers as any other technology, but the order and strength of the various factors may be different. This examination as well as other empirical studies shows that regulations play a greater part for environmental technology than 'pure market forces'. To many participants it is important to be one step ahead of the regulations, i.e. the expected regulations are equally important as the factual ones in driving the technology development. Players in the business community express that it is important that the authorities cooperate with them when introducing new regulations. This will increase acceptance for the regulations and facilitate the necessary adjustments. The most important barrier in the development and use of the technologies studied is probably the lack of demand

Parabolic-trough technology roadmap: A pathway for sustained commercial development and deployment of parabolic-trough technology

International Nuclear Information System (INIS)

David Kearney; Hank Price

1999-01-01

Technology roadmapping is a needs-driven technology planning process to help identify, select, and develop technology alternatives to satisfy a set of market needs. The DOE's Office of Power Technologies' Concentrating Solar Power (CSP) Program recently sponsored a technology roadmapping workshop for parabolic trough technology. The workshop was attended by an impressive cross section of industry and research experts. The goals of the workshop were to evaluate the market potential for trough power projects, develop a better understanding of the current state of the technology, and to develop a conceptual plan for advancing the state of parabolic trough technology. This report documents and extends the roadmap that was conceptually developed during the workshop

Assessing medical technologies in development; a new paradigm of medical technology assessment

NARCIS (Netherlands)

Hummel, J. Marjan; van Rossum, Wouter; Verkerke, Gijsbertus Jacob; Rakhorst, Gerhard

2000-01-01

Objective: Our study aims to provide a practical contribution to the field of medical technology assessment within a new paradigm. This paradigm indicates the need for more comprehensive technology assessments in the development stage of a new technology. - Method: We introduce a method, based on

Assessing medical technologies in development - A new paradigm of medical technology assessment

NARCIS (Netherlands)

Hummel, MJM; van Rossum, W; Verkerke, GJ; Rakhorst, G

2000-01-01

Objective: Our study aims to provide a practical contribution to the field of medical technology assessment within a new paradigm. This paradigm indicates the need for more comprehensive technology assessments in the development stage of a new technology. Method: We introduce a method, based on

Technology development for meeting with automobiles negotiation

Energy Technology Data Exchange (ETDEWEB)

Chung, Yong Il [Korea Institute of Machinery and Materials, Seoul (Korea)

2000-06-01

The direction of technology development for meeting with automobiles negotiation is to establish a development and supply policy of automobile with the minimum mileage. Furthermore the development policy of diesel car should be promoted with the same level of gasoline engine emission and a new concept of developing clean diesel engine is needed to achieve this goal. Therefore a smoke-filtering device, developed in Korea, should be promoted for supplying and post-process technology development such as SCR and DeNox catalyzer should be promoted.

Review of NRC Commission Papers on Regulatory Basis for Licensing and Regulating Reprocessing Facilities

Energy Technology Data Exchange (ETDEWEB)

Park, Jae Yeong; Shin, Hyeong Ki [KINS, Daejeon (Korea, Republic of)

2016-05-15

Spent nuclear fuel (SNF) accumulated in nuclear power plant has been a serious issue in most countries with operating nuclear power plants. Direct disposal of SNF could be a solution of the problem but many countries including the Republic of Korea have had a hard time selecting a site for high level waste repository because of low public acceptance. SNF recycling technologies consisting of reprocessing and transmutation have been developed so as to reduce the final volume of the disposed radioactive waste and to diminish the radiotoxicity of the waste. The Republic of Korea is now developing pyroprocessing and sodium-cooled fast reactor (SFR) technology to be used for the recycling of the wastes. KAERI has a plan to construct a pyroprocessing facility with a capacity of 30 tHM/y and a facility manufacturing TRU fuel for SFR by 2025. However, to license these facility and secure the safety, the current regulatory system related to SNF treatment needs to be improved and amended since the system has been developed focusing on facilities to examine irradiated nuclear materials. Status of reprocessing facility regulations developed by U.S.NRC was reviewed based on SECY papers. U.S.NRC has approved the development of a new rule referred to nationally as '10CFR Part 7x'. Existing 10CFR 50 and 70 has been evolved mainly for nuclear power plants and fuel cycle facilities whose radiological hazard is much lower than reprocessing plants respectively. U.S.NRC also derived many regulatory gaps including safety assessment methods, technical specification, general design criteria and waste classification and continue to develop the regulatory framework limited in scope to the resolution of Gap 5.

Aligning Technology Education Teaching with Brain Development

Science.gov (United States)

Katsioloudis, Petros

2015-01-01

This exploratory study was designed to determine if there is a level of alignment between technology education curriculum and theories of intellectual development. The researcher compared Epstein's Brain Growth Theory and Piaget's Status of Intellectual Development with technology education curriculum from Australia, England, and the United…

Development of Flow Accelerated Corrosion Reduction Technology

Energy Technology Data Exchange (ETDEWEB)

Heo, Min Bum; Choi, Won Yeol; Lee, Jong Chan; Lim, Dong Seok; Kwon, Byung Il; Ku, Hee Kwon; Kim, Jong Uk [FNC Tech, Yongin (Korea, Republic of)

2015-10-15

Development of flow accelerated corrosion reduction technology is necessary for prevent this kind of accidents. This study deals with development of flow accelerated corrosion reduction technology through platinum injection and developed of flow accelerated corrosion reduction technology by imitating water chemical condition in PWR secondary system in practice. In addition, in order to get reliability of water chemical simulator in PWR secondary system, analyzed and compared with test result through CFD analysis. This study composed test device that can simulate water chemical environment in PWR secondary system, in order to develop flow accelerated corrosion reduction , and evaluated the ratio of corrosion in water chemical environment in PWR secondary system. In conclusion, corrosion ratio of low alloy steel material that includes more Cr and Mo was lower. And the results were confirmed to be the maximum corrosion rate in the case that replicate the 90 elbow. Additionally, inserted Pt nano particle for developing flow accelerated corrosion rate reduction technology, the test results, it was confirmed for about 80% of the flow accelerated corrosion rate reduction than before input.

Large Deployable Reflector (LDR) system concept and technology definition study. Volume 2: Technology assessment and technology development plan

Science.gov (United States)

Agnew, Donald L.; Jones, Peter A.

1989-01-01

A study was conducted to define reasonable and representative LDR system concepts for the purpose of defining a technology development program aimed at providing the requisite technological capability necessary to start LDR development by the end of 1991. This volume presents thirteen technology assessments and technology development plans, as well as an overview and summary of the LDR concepts. Twenty-two proposed augmentation projects are described (selected from more than 30 candidates). The five LDR technology areas most in need of supplementary support are: cryogenic cooling; astronaut assembly of the optically precise LDR in space; active segmented primary mirror; dynamic structural control; and primary mirror contamination control. Three broad, time-phased, five-year programs were synthesized from the 22 projects, scheduled, and funding requirements estimated.

Genetic technology and agricultural development.

Science.gov (United States)

Staub, W J; Blase, M G

1971-07-09

The genetic technologies being adopted in South Asia are significant factors in the agricultural development of the area. But, labeling them " miracle seeds," solely responsible for recent agricultural growth, is misleading. Certainly the introduction of new genetic technology has catalyzed South Asian agriculture and has instilled a new dynamism essential to economic development. Somewhat similar phenomena have, however, been observed in other parts of the world in other periods of history. The nature of these genetic technologies, how they are being applied, and their limits and potential have been explored above. Also, the effects of these varieties on the generation of employment, and the distribution of benefits accruing from them have been examined in preliminary fashion. Stemming from the preceding discussion, two areas of priority appear obvious. First, the close association of genetic technologies with irrigation suggests that irrigation should receive more attention than it has in the past. Large-scale public irrigation schemes are expensive and have tended to yield low rates of return. However, there appears to be room for marginal increases in, or improvements of, existing irrigation facilities. Second, even with a rapid spread of the practices associated with highyeild varieties, it may be too much to expect the farm sector to absorb the expected increases in the rural labor force. The generation of employment is a major problem in India as well as in most other developing countries. Hence, possibilities for expanding rural, nonfarm employment and controlling population growth should be sought vigorously.

Marine and Hydrokinetic Technology Development Risk Management Framework

Energy Technology Data Exchange (ETDEWEB)

Snowberg, David [National Renewable Energy Lab. (NREL), Golden, CO (United States); Weber, Jochem [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2015-09-01

Over the past decade, the global marine and hydrokinetic (MHK) industry has suffered a number of serious technological and commercial setbacks. To help reduce the risks of industry failures and advance the development of new technologies, the U.S. Department of Energy (DOE) and the National Renewable Energy Laboratory (NREL) developed an MHK Risk Management Framework. By addressing uncertainties, the MHK Risk Management Framework increases the likelihood of successful development of an MHK technology. It covers projects of any technical readiness level (TRL) or technical performance level (TPL) and all risk types (e.g. technological risk, regulatory risk, commercial risk) over the development cycle. This framework is intended for the development and deployment of a single MHK technology—not for multiple device deployments within a plant. This risk framework is intended to meet DOE’s risk management expectations for the MHK technology research and development efforts of the Water Power Program (see Appendix A). It also provides an overview of other relevant risk management tools and documentation.1 This framework emphasizes design and risk reviews as formal gates to ensure risks are managed throughout the technology development cycle. Section 1 presents the recommended technology development cycle, Sections 2 and 3 present tools to assess the TRL and TPL of the project, respectively. Section 4 presents a risk management process with design and risk reviews for actively managing risk within the project, and Section 5 presents a detailed description of a risk registry to collect the risk management information into one living document. Section 6 presents recommendations for collecting and using lessons learned throughout the development process.

Modular, Reconfigurable, High-Energy Technology Development

Science.gov (United States)

Carrington, Connie; Howell, Joe

2006-01-01

The Modular, Reconfigurable High-Energy (MRHE) Technology Demonstrator project was to have been a series of ground-based demonstrations to mature critical technologies needed for in-space assembly of a highpower high-voltage modular spacecraft in low Earth orbit, enabling the development of future modular solar-powered exploration cargo-transport vehicles and infrastructure. MRHE was a project in the High Energy Space Systems (HESS) Program, within NASA's Exploration Systems Research and Technology (ESR&T) Program. NASA participants included Marshall Space Flight Center (MSFC), the Jet Propulsion Laboratory (JPL), and Glenn Research Center (GRC). Contractor participants were the Boeing Phantom Works in Huntsville, AL, Lockheed Martin Advanced Technology Center in Palo Alto, CA, ENTECH, Inc. in Keller, TX, and the University of AL Huntsville (UAH). MRHE's technical objectives were to mature: (a) lightweight, efficient, high-voltage, radiation-resistant solar power generation (SPG) technologies; (b) innovative, lightweight, efficient thermal management systems; (c) efficient, 100kW-class, high-voltage power delivery systems from an SPG to an electric thruster system; (d) autonomous rendezvous and docking technology for in-space assembly of modular, reconfigurable spacecraft; (e) robotic assembly of modular space systems; and (f) modular, reconfigurable distributed avionics technologies. Maturation of these technologies was to be implemented through a series of increasingly-inclusive laboratory demonstrations that would have integrated and demonstrated two systems-of-systems: (a) the autonomous rendezvous and docking of modular spacecraft with deployable structures, robotic assembly, reconfiguration both during assembly and (b) the development and integration of an advanced thermal heat pipe and a high-voltage power delivery system with a representative lightweight high-voltage SPG array. In addition, an integrated simulation testbed would have been developed

Integrating the fuel cycle at IFR [Integral Fast Reactor

International Nuclear Information System (INIS)

Till, C.E.; Chang, Y.I.

1992-01-01

During the past few years Argonne National Laboratory has been developing the Integral Fast Reactor (IFR), an advanced liquid metal reactor. Much of the IFR technology stems from Argonne National Laboratory's experience with the Experimental Breeder Reactors, EBR 1 and 2. The unique aspect of EBR 2 is its success with high-burnup metallic fuel. Irradiation tests of the new U-Pu-Zr fuel for the IFR have now reached a burnup level of 20%. The results to date have demonstrated excellent performance characteristics of the metallic fuel in both steady-state and off-normal operating conditions. EBR 2 is now fully loaded with the IFR fuel alloys and fuel performance data are being generated. In turn, metallic fuel becomes the key factor in achieving a high degree of passive safety in the IFR. These characteristics were demonstrated dramatically by two landmark tests conducted at EBR 2 in 1986: loss of flow without scram; and loss of heat sink without scram. They demonstrated that the combination of high heat conductivity of metallic fuel and thermal inertia of the large sodium pool can shut the reactor down during potentially severe accidents without depending on human intervention or the operation of active engineered components. The IFR metallic fuel is also the key factor in compact pyroprocessing. Pyroprocessing uses high temperatures, molten salt and metal solvents to process metal fuels. The result is suitable for fabrication into new fuel elements. Feasibility studies are to be conducted into the recycling of actinides from light water reactor spent fuel in the IFR using the pyroprocessing approach to extract the actinides (author)

Development of Fluid and I and C Systems Design Technology for LMR - Development of mechanical structure design technology for LMR

International Nuclear Information System (INIS)

Lee, Jae Han; Joo, Young Sang; Lee, Hueong Yeon and others

2005-03-01

The key research items during the fiscal years of Phase 3 of the mechanical design technology development for liquid metal reactor are described. The objective of this project is to develop the design technology for the mechanical system of 600MWe, pool type liquid metal reactor with sodium coolant, and the structural integrity evaluation technology for mechanical system of the reactor system, structures and equipments. In the design technology development for mechanical structures, the reactor internal structures, reactor head and piping system, reactor containment structures have been studied, and new structural concepts compatible with the new reactor have been proposed. The thermal protection devices of reactor vessel and the refueling system have been conceptually established and the feasibility study for 3-D seismic isolation of reactor building was performed. The structural damage detection technology for reactor internal structures has been studied and its application has been confirmed. In the structural integrity evaluation technology development, the sensitivities of material constants for inelastic analysis codes have been studied and the applicabilities of the developed codes are enhanced. The high temperature creep-fatigue structural behavior test has been conducted so that high temperature structural damage test and evaluation technology were ensured at first in domestic. The high temperature seismic buckling analysis method to evaluate the buckling of thin reactor shell structure under the transient thermal load was established. In addition, the core seismic response analysis code reflected the fluid effect of core was developed and its accuracy was confirmed with a scale-down model test

Cyberfeminism, technology, and international "development".

Science.gov (United States)

Gajjala, R; Mamidipudi, A

1999-07-01

This article reports on the implications and benefits of Internet technology among women from developing countries. Cyberfeminism is the practice of feminism in cyberspace. Feminists believe that women should take control and augment Internet technologies to empower themselves. Learning to use the computers, getting "connected," and surfing the Internet are encouraged among all women with the aim of advancing feminist causes and empowering women. The Internet has been observed to cause radical changes in the way business and social activities are conducted. A description of how two women have engaged in cyberfeminism and worked in development and technology programs is included. One contributor, Annapurna Mamipudi, is involved in a non-governmental organization working with traditional handloom weavers in India Another contributor is Radhika Gajjala, who works in academia and creates on-line "discussion lists" and Web sites from her North American geographical location. Her job is to create spaces that provide opportunities for dialogue and collaboration among women with Internet access all over the world.

Technological development with reference to hydro-power, nuclear, and alternative energy technologies

Energy Technology Data Exchange (ETDEWEB)

Burns, T R; Baumgartner, T

1985-01-01

This report outlines a theoretical framework for describing and analyzing the introduction of new technologies and the development of socio-technical systems associated with such innovations. While the report is largely theoretical in nature, it refers to certain strategic aspects of the development of nuclear, hydro-power and alternative energy systems. The ease with which technological innovation and development occur, the directions they take, and the impacts they have on the social and physical environments depend not only on purely technical and economic factors. Barriers, regulators and facilitators are inherent in the socio-political, institutional and cultural structures within which any attempts at innovation and technological development take place. The final section of the report explores some of the implications of the theory for policy and strategy, including consideration of environmental policy.

CROSSCUTTING TECHNOLOGY DEVELOPMENT AT THE CENTER FOR ADVANCED SEPARATION TECHNOLOGIES

Energy Technology Data Exchange (ETDEWEB)

Christopher E. Hull

2005-11-04

This Technical Progress Report describes progress made on the twenty nine subprojects awarded in the second year of Cooperative Agreement DE-FC26-02NT41607: Crosscutting Technology Development at the Center for Advanced Separation Technologies. This work is summarized in the body of the main report: the individual sub-project Technical Progress Reports are attached as Appendices.

Crosscutting Technology Development at the Center for Advanced Separation Technologies

Energy Technology Data Exchange (ETDEWEB)

Christopher E. Hull

2006-09-30

This Technical Progress Report describes progress made on the twenty nine subprojects awarded in the second year of Cooperative Agreement DE-FC26-02NT41607: Crosscutting Technology Development at the Center for Advanced Separation Technologies. This work is summarized in the body of the main report: the individual sub-project Technical Progress Reports are attached as Appendices.

CROSSCUTTING TECHNOLOGY DEVELOPMENT AT THE CENTER FOR ADVANCED SEPARATION TECHNOLOGIES

Energy Technology Data Exchange (ETDEWEB)

Christopher E. Hull

2006-05-15

This Technical Progress Report describes progress made on the twenty nine subprojects awarded in the second year of Cooperative Agreement DE-FC26-02NT41607: Crosscutting Technology Development at the Center for Advanced Separation Technologies. This work is summarized in the body of the main report: the individual sub-project Technical Progress Reports are attached as Appendices.

Let nuclear technology create new brilliancy for china's sustainable development

International Nuclear Information System (INIS)

Du Xiangwan

2008-01-01

This paper summarizes the development and application directions of nuclear technology, including five aspects: nuclear technology and energy nuclear technology and medicine, nuclear anclear analysis technology, nuclear radiation technology, astronautics and voyage's nuclear power, etc. The paper discusses the importance of them to sustainable development and generalizes the development trilogy of nuclear science and technology and its prospect. (authors)

"Design for Somebody" - Approach Enabling Mobile Technology Development.

Science.gov (United States)

Sirkka, Andrew; Merilampi, Sari; Koivisto, Antti; Tommiska, Janika; Saarinen, Tatu-Pekka

2017-01-01

This paper presents case examples of Design for Somebody (DfS) philosophy used both in developing novel technologies and modifying existing main stream technologies applicable for users with special needs. DfS embodies variety of mobile technology approaches to generate personalised means to enable and motivate physical, cognitive and social skills development.

Development of an integrated crucible for the salt separation

Energy Technology Data Exchange (ETDEWEB)

Kwon, S. W.; Park, K. M.; Jeong, J. H.; Lee, H. S.; Kim, J. G. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2012-05-15

Pyroprocessing has been developed for the recovery of actinide elements from spent fuel due to its advantages. Electrorefining is a key step in pyroprocessing. The electrorefining process is generally composed of two recovery steps. The deposit of uranium onto a solid cathode and the recovery of the remaining uranium and TRU elements simultaneously by a liquid cadmium cathode. The solid cathode processing is necessary to separate the salt from the cathode since the uranium deposit in a solid cathode contains electrolyte salt. A physical separation process, such as distillation separation, is more attractive than a chemical or dissolution process because physical processes generate much less secondary process. Distillation process was employed for the cathode process sing due to the advantages of minimal generation of secondary waste, compact unit process, simple and low cost equipment. The basis for vacuum distillation separation is the difference in vapor pressures between salt and uranium. A solid cathode deposit is heated in a heating region and salt vaporizes, while non volatile uranium remains behind. It is very important to increase the throughput of the salt separation system due to the high uranium content of spent nuclear fuel and high salt fraction of uranium dendrites. The evaporation rate of the LiCl-KCl eutectic salt in vacuum distiller is not so high to come up with the generation capacity of uranium dendrites in electro-refiner. Therefore, wide evaporation area or high distillation temperature is necessary for the successful salt separation. In this study, the integrated salt separation system was developed to increase the throughput of the salt removal process by the separation of the liquid salt prior to the distillation of the LiCl-KCl eutectic salt from the uranium deposits

Scientific projection paper for cluster B: technology development

International Nuclear Information System (INIS)

Sinclair, W.K.

1980-01-01

This section deals with new technology developments in fields primarily concerned with dose reduction and matters relating to radiation protection rather than toward technology developments that might enhance the beneficial uses of ionizing radiation, except for the consideration of diagnostic techniques which may result in alternatives to ionizing radiation. Three major areas have been identified in which progress can be made via technology development: diagnostic radiology, occupational exposure and exposure of the public to radioactivity

Technology transfer in the Clean Development Mechanism

International Nuclear Information System (INIS)

De Coninck, H.C.; Haake, F.; Van der Linden, N.H.

2007-01-01

Technology transfer is often mentioned as an ancillary benefit of the Kyoto Protocol's Clean Development Mechanism (CDM), but this claim has never been researched or substantiated. The question of technology transfer is important from two perspectives: for host countries, whether the CDM provides a corridor for foreign, climate-friendly technologies and investment, and for industrialised countries as it provides export potential for climate-friendly technologies developed as a consequence of stringent greenhouse gas targets. In order to better understand whether technology transfer from the EU and elsewhere is occurring through the CDM, and what is the value of the associated foreign investment, this paper examines technology transfer in the 63 CDM projects that were registered on January 1st, 2006. Technology originates from outside the host country in almost 50% of the evaluated projects. In the projects in which the technology originates from outside the host country, 80% use technology from the European Union. Technologies used in non-CO2 greenhouse gas and wind energy projects, and a substantial share of the hydropower projects, use technology from outside the host country, but biogas, agricultural and biomass projects mainly use local technology. The associated investment value with the CDM projects that transferred technology is estimated to be around 470 million Euros, with about 390 coming from the EU. As the non-CO2 greenhouse gas projects had very low capital costs, the investment value was mostly in the more capital-intensive wind energy and hydropower projects

Systems engineering identification and control of mixed waste technology development

International Nuclear Information System (INIS)

Beitel, G.A.

1997-01-01

The Department of Energy (DOE) established the Mixed Waste Characterization, Treatment, and Disposal Focus Area (MWFA) to develop technologies required to meet the Department's commitments for treatment of mixed low-level and transuranic wastes. Waste treatment includes all necessary steps from generation through disposal. Systems engineering was employed to reduce programmatic risk, that is, risk of failure to meet technical commitments within cost and schedule. Customer needs (technology deficiencies) are identified from Site Treatment Plans, Consent Orders, ten year plans, Site Technical Coordinating Groups, Stakeholders, and Site Visits. The Technical Baseline, a prioritized list of technology deficiencies, forms the basis for determining which technology development activities will be supported by the MWFA. Technology Development Requirements Documents are prepared for each technology selected for development. After technologies have been successfully developed and demonstrated, they are documented in a Technology Performance Report. The Technology Performance Reports are available to any of the customers or potential users of the technology, thus closing the loop between problem identification and product development. This systematic approach to technology development and its effectiveness after 3 years is discussed in this paper

Development of a Virtual Technology Coach to Support Technology Integration for K-12 Educators

Science.gov (United States)

Sugar, William; van Tryon, Patricia J. Slagter

2014-01-01

In an effort to develop a virtual technology coach for K-12 educators, this article analyzed survey results from sixty teachers with regards to specific resources that a technology coach could provide within a virtual environment. A virtual technology coach was proposed as a possible solution to provide continual professional development for…

DOE SNF technology development necessary for final disposal

International Nuclear Information System (INIS)

Hale, D.L.; Fillmore, D.L.; Windes, W.E.

1996-01-01

Existing technology is inadequate to allow safe disposal of the entire inventory of US Department of Energy (DOE) spent nuclear fuel (SNF). Needs for SNF technology development were identified for each individual fuel type in the diverse inventory of SNF generated by past, current, and future DOE materials production, as well as SNF returned from domestic and foreign research reactors. This inventory consists of 259 fuel types with different matrices, cladding materials, meat composition, actinide content, and burnup. Management options for disposal of SNF include direct repository disposal, possible including some physical or chemical preparation, or processing to produce a qualified waste form by using existing aqueous processes or new treatment processes. Technology development needed for direct disposal includes drying, mitigating radionuclide release, canning, stabilization, and characterization technologies. While existing aqueous processing technology is fairly mature, technology development may be needed to apply one of these processes to SNF different than for which the process was originally developed. New processes to treat SNF not suitable for disposal in its current form were identified. These processes have several advantages over existing aqueous processes

Strategies for fuel cell product development. Developing fuel cell products in the technology supply chain

International Nuclear Information System (INIS)

Hellman, H.L.

2004-01-01

Due to the high cost of research and development and the broad spectrum of knowledge and competences required to develop fuel cell products, many product-developing firms outsource fuel cell technology, either partly or completely. This article addresses the inter-firm process of fuel cell product development from an Industrial Design Engineering perspective. The fuel cell product development can currently be characterised by a high degree of economic and technical uncertainty. Regarding the technology uncertainty: product-developing firms are more often then not unfamiliar with fuel cell technology technology. Yet there is a high interface complexity between the technology supplied and the product in which it is to be incorporated. In this paper the information exchange in three current fuel cell product development projects is analysed to determine the information required by a product designer to develop a fuel cell product. Technology transfer literature suggests that transfer effectiveness is greatest when the type of technology (technology uncertainty) and the type of relationship between the technology supplier and the recipient are carefully matched. In this line of thinking this paper proposes that the information required by a designer, determined by the design strategy and product/system volume, should be met by an appropriate level of communication interactivity with a technology specialist. (author)

Information technology research and development critical trends and issues

CERN Document Server

1985-01-01

Information Technology Research and Development: Critical Trends and Issues is a report of the Office of Technology Assessment of the United States Government on the research and development in the area of information technology. The report discusses information technology research and development - its goals, nature, issues, and strategies; environment and its changes; the roles of the participants; and the health of its field. The book then goes on to four selected case studies in information technology: advanced computer architecture; fiber optic communications; software engineering; and ar

Data-Base Software For Tracking Technological Developments

Science.gov (United States)

Aliberti, James A.; Wright, Simon; Monteith, Steve K.

1996-01-01

Technology Tracking System (TechTracS) computer program developed for use in storing and retrieving information on technology and related patent information developed under auspices of NASA Headquarters and NASA's field centers. Contents of data base include multiple scanned still images and quick-time movies as well as text. TechTracS includes word-processing, report-editing, chart-and-graph-editing, and search-editing subprograms. Extensive keyword searching capabilities enable rapid location of technologies, innovators, and companies. System performs routine functions automatically and serves multiple users.

Integrated Micro Product and Technology Development

DEFF Research Database (Denmark)

Hansen, Hans Nørgaard

2003-01-01

The paper addresses the issues of integrated micro product and technology development. The implications of the decisions in the design phase on the subsequent manufacturing processes are considered vital. A coherent process chain is a necessary prerequisite for the realisation of the industrial...... potential of micro technology....

The Clean Development Mechanism and Technology Transfer

DEFF Research Database (Denmark)

Aggarwal, Aradhna

2017-01-01

This study assesses the impact of the Clean Development Mechanism (CDM) on the transfer of clean technology in India. The reason this study is unique is because firstly, it adopts an outcome-oriented approach to define ‘technology transfer’, which means that technology transfer occurs if firms...

Development of geological disposal system for spent fuels and high-level radioactive wastes in Korea

International Nuclear Information System (INIS)

Choi, Heui Joo; Lee, Jong Youl; Choi, Jong Won

2013-01-01

Two different kinds of nuclear power plants produce a substantial amount of spent fuel annually in Korea. According to the current projection, it is expected that around 60,000 MtU of spent fuel will be produced from 36 PWR and APR reactors and 4 CANDU reactors by the end of 2089. In 2006, KAERI proposed a conceptual design of a geological disposal system (called KRS, Korean Reference disposal System for spent fuel) for PWR and CANDU spent fuel, as a product of a 4-year research project from 2003 to 2006. The major result of the research was that it was feasible to construct a direct disposal system for 20,000 MtU of PWR spent fuels and 16,000 MtU of CANDU spent fuel in the Korean peninsula. Recently, KAERI and MEST launched a project to develop an advanced fuel cycle based on the pyroprocessing of PWR spent fuel to reduce the amount of HLW and reuse the valuable fissile material in PWR spent fuel. Thus, KAERI has developed a geological disposal system for high-level waste from the pyroprocessing of PWR spent fuel since 2007. However, since no decision was made for the CANDU spent fuel, KAERI improved the disposal density of KRS by introducing several improved concepts for the disposal canister. In this paper, the geological disposal systems developed so far are briefly outlined. The amount and characteristics of spent fuel and HLW, 4 kinds of disposal canisters, the characteristics of a buffer with domestic Ca-bentonite, and the results of a thermal design of deposition holes and disposal tunnels are described. The different disposal systems are compared in terms of their disposal density.

Commercialization Development of Crop Straw Gasification Technologies in China

Directory of Open Access Journals (Sweden)

Zhengfeng Zhang

2014-12-01

Full Text Available Crop straw gasification technologies are the most promising biomass gasification technologies and have great potential to be further developed in China. However, the commercialization development of gasification technology in China is slow. In this paper, the technical reliability and practicability of crop straw gasification technologies, the economic feasibility of gas supply stations, the economic feasibility of crop straw gasification equipment manufacture enterprises and the social acceptability of crop straw gasification technologies are analyzed. The results show that presently both the atmospheric oxidation gasification technology and the carbonization pyrolysis gasification technology in China are mature and practical, and can provide fuel gas for households. However, there are still a series of problems associated with these technologies that need to be solved for the commercialization development, such as the high tar and CO content of the fuel gas. The economic feasibility of the gas supply stations is different in China. Parts of gas supply stations are unprofitable due to high initial investment, the low fuel gas price and the small numbers of consumers. In addition, the commercialization development of crop straw gasification equipment manufacture enterprises is hindered for the low market demand for gasification equipment which is related to the fund support from the government. The acceptance of the crop straw gasification technologies from both the government and the farmers in China may be a driving force of further commercialization development of the gasification technologies. Then, the crop straw gasification technologies in China have reached at the stage of pre-commercialization. At this stage, the gasification technologies are basically mature and have met many requirements of commercialization, however, some incentives are needed to encourage their further development.

Development of zirconium alloy tube manufacturing technology

International Nuclear Information System (INIS)

Kim, In Kyu; Park, Chan Hyun; Lee, Seung Hwan; Chung, Sun Kyo

2009-01-01

In late 2004, Korea Nuclear Fuel Company (KNF) launched a government funded joint development program with Westinghouse Electric Co. (WEC) to establish zirconium alloy tube manufacturing technology in Korea. Through this program, KNF and WEC have developed a state of the art facility to manufacture high quality nuclear tubes. KNF performed equipment qualification tests for each manufacturing machine with the support of WEC, and independently carried out product qualification tests for each tube product to be commercially produced. Apart from those tests, characterization test program consisting of specification test and characterization test was developed by KNF and WEC to demonstrate to customers of KNF the quality equivalency of products manufactured by KNF and WEC plants respectively. As part of establishment of performance evaluation technology for zirconium alloy tube in Korea, KNF carried out analyses of materials produced for the characterization test program using the most advanced techniques. Thanks to the accomplishment of the development of zirconium alloy tube manufacturing technology, KNF is expected to acquire positive spin off benefits in terms of technology and economy in the near future

Technology-Enhanced Learning in Developing Nations: A review