Proceedings of the symposium on nitride fuel cycle technology

International Nuclear Information System (INIS)

2004-12-01

This report is the Proceedings of the Symposium of Nitride Fuel Cycle Technology, which was held on July 28, 2004, at the Tokai Research Establishment of the Japan Atomic Energy Research Institute. The purpose of this symposium is to exchange information and views on nitride fuel cycle technology among researchers from foreign and domestic organizations, and to discuss the recent and future research activities. The topics in the symposium are Present State of the Technology Development in the World and Japan, Fabrication Technology, Property Measurement and Pyrochemical Process. The intensive discussion was made among 53 participants. This report consists of 2 papers as invited presentations and 12 papers as contributed papers. (author)

Proceedings - Alternate Fuels II: The disposal and productive use of industrial wastes

International Nuclear Information System (INIS)

Anon.

1991-01-01

The proceedings contain 26 papers dealing with the following topics: fuels (biomass, coal, petroleum coke, landfill gas, hazardous and toxic wastes, liquid wastes, and digester gas); combustion systems; plant systems (pollution control, combustion control, and materials handling systems); external factors (public relations, markets, hazardous waste, vitrification for waste management); and case histories of resource recovery facilities, process heating plants, and retrofits to alternative fuels. All papers have been processed separately for inclusion on the data base

Proceeding of the Scientific Presentation on Nuclear Fuel Cycle; Prosiding Presentasi Ilmiah Daur Bahan Bakar Nuklir

Energy Technology Data Exchange (ETDEWEB)

Suripto, A; Yuwono, I; Nasution, H; Hersubeno, B J; Amini, S; Sigit,; Cahyono, A [Nuclear Fuel Elements Development Centre, National Atomic Energy Agency, Serpong, Indonesia (Indonesia)

1996-11-01

The proceeding contains papers presented on Scientific Presentation on Nuclear Fuel Cycle held in Jakarta, 18-19 March 1996. These are 46 papers resulted from scientific works on various disciplines which have supported to nuclear fuel cycle activities both in and outside National Atomic Energy Agency of Indonesia.(ID)

Proceedings of the third annual fuel cells contractors review meeting

Energy Technology Data Exchange (ETDEWEB)

Huber, W.J. (ed.)

1991-06-01

The overall objective of this program is to develop the essential technology for private sector characterization of the various fuel cell electrical generation systems. These systems promise high fuel to electricity efficiencies (40 to 60 percent), distinct possibilities for cogeneration applications, modularity of design, possibilities of urban siting, and environmentally benign emissions. The purpose of this meeting was to provide the research and development (R D) participants in the DOE/Fossil Energy-sponsored Fuel Cells Program with the opportunity to present key results of their research and to establish closer business contacts. Major emphasis was on phosphoric acid, molten carbonate, and solid oxide technology efforts. Research results of the coal gasification and gas stream cleanup R D activities pertinent to the Fuel Cells Program were also highlighted. Two hundred seventeen attendees from industry, utilities, academia, and Government participated in this 2-day meeting. Twenty-three papers were given in three formal sessions: molten carbonate fuel cells R D (9 papers), solid oxide fuel cells (8 papers), phosphoric acid fuel cells R D (6 papers). In addition to the papers and presentations, these proceedings also include comments on the Fuel Cells Program from the viewpoint of DOE/METC Fuel Cell Overview by Rita A. Bajura, DOE/METC Perspective by Manville J. Mayfield, Electric Power Research Institute by Daniel M. Rastler, Natural Gas by Hugh D. Guthrie, and Transportation Applications by Pandit G. Patil.

Practices and developments in spent fuel burnup credit applications. Proceedings of a technical committee meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-10-01

The International Atomic Energy Agency convened a technical committee Meeting on Requirements, Practices and Developments in Burnup Credit (BUC) Applications in Madrid, Spain, from 22 to 26 April 2002. The purpose of this meeting was to explore the progress and status of international activities related to the BUC applications for spent nuclear fuel. This meeting was the third major meeting on the uses of BUC for spent fuel management systems held since the IAEA began to monitor the uses of BUC in spent fuel management systems in 1997. The first major meeting was an Advisory Group meeting (AGM), which was held in Vienna, in October 1997. The second major meeting was a technical committee meeting (TCM), which was held in Vienna, in July 2000. Several consultants meetings were held since 1997 to advise and assist the IAEA in planning and conducting its BUC activities. The proceedings of the 1997 AGM were published as IAEA-TECDOC-1013, and the proceedings of the 2000 TCM as IAEA-TECDOC-1241. BUC for wet and dry storage systems, spent fuel transport, reprocessing and final disposal is needed in many Member States to allow for increased enrichment, and to increase storage capacities, cask capacities and dissolver capacities avoiding the need for extensive modifications. The use of BUC is a necessity for spent fuel disposal.

Proceedings of the 5th international conference on stability and handling of liquid fuels. Volume 2

Energy Technology Data Exchange (ETDEWEB)

Giles, H.N. [ed.

1995-04-01

Volume 2 of these proceedings contains 34 papers divided into the following sessions: Deposit and insolubles measurement (5 papers); Gasolines (4 papers); Heavy oils and refinery processing (3 papers); Middle distillate fuels (7 papers); New fuels and environmental mandates (5 papers); and a Poster session (10 papers). Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

Storage of spent fuel from power reactors. 2003 conference proceedings

International Nuclear Information System (INIS)

2003-01-01

An International Conference on Storage of Spent Fuel from Power Reactors was organized by the IAEA in co-operation with the OECD Nuclear Energy Agency. The conference gave an opportunity to exchange information on the state of the art and prospects of spent fuel storage, to discuss the worldwide situation and the major factors influencing the national policies in this field and to identify the most important directions that national efforts and international co-operation in this area should take. The conference confirmed that the primary spent fuel management solution for the next decades will be interim storage. While the next step can be reprocessing or disposal, all spent fuel or high level waste from reprocessing must sooner or later be disposed of. The duration of interim storage is now expected to be much longer than earlier projections (up to 100 years and beyond). The storage facilities will have to be designed for these longer storage times and also for receiving spent fuel from advanced fuel cycle practices (i.e. high burnup and MOX spent fuel). It was noted that the handling and storage of spent fuel is a mature technology and meets the stringent safety requirements applicable in the different countries. The changes in nuclear policy and philosophy across the world, and practical considerations, have made storage a real necessity in the nuclear power industry. Utilities, vendors and regulators alike are addressing this adequately. The IAEA wishes to express appreciation to all chairs and co-chairs as well as all authors for their presentations to the conference and papers included in these proceedings

Storage of spent fuel from power reactors. 2003 conference proceedings

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-10-01

An International Conference on Storage of Spent Fuel from Power Reactors was organized by the IAEA in co-operation with the OECD Nuclear Energy Agency. The conference gave an opportunity to exchange information on the state of the art and prospects of spent fuel storage, to discuss the worldwide situation and the major factors influencing the national policies in this field and to identify the most important directions that national efforts and international co-operation in this area should take. The conference confirmed that the primary spent fuel management solution for the next decades will be interim storage. While the next step can be reprocessing or disposal, all spent fuel or high level waste from reprocessing must sooner or later be disposed of. The duration of interim storage is now expected to be much longer than earlier projections (up to 100 years and beyond). The storage facilities will have to be designed for these longer storage times and also for receiving spent fuel from advanced fuel cycle practices (i.e. high burnup and MOX spent fuel). It was noted that the handling and storage of spent fuel is a mature technology and meets the stringent safety requirements applicable in the different countries. The changes in nuclear policy and philosophy across the world, and practical considerations, have made storage a real necessity in the nuclear power industry. Utilities, vendors and regulators alike are addressing this adequately. The IAEA wishes to express appreciation to all chairs and co-chairs as well as all authors for their presentations to the conference and papers included in these proceedings.

Proceedings of the Third Scientific Presentation on Nuclear Fuel Cycle; Prosiding: Presentasi ilmiah daur bahan bakar nuklir 3

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-02-01

The proceeding contains papers presented in the Third Scientific Presentation on nuclear Fuel Element Cycle held on 4-5 Nov 1997 in Jakarta, Indonesia. These papers were divided by three groups that are technology of exploration, processing, purification and analysis of nuclear materials; technology of nuclear fuel elements and structures; and technology of waste management, safety and nuclear fuel cycle. There are 38 papers indexed individually. (ID)

Proceeding of the Fourth Scientific Presentation on Nuclear Fuel Cycle: Technology of Nuclear Fuel Cycle facing the Challenge of Energy Need on the 21-st Century

International Nuclear Information System (INIS)

Suripto, A.; Sajuti, D.; Aiman, S.; Yuwono, I.; Fathurrachman; Suwarno, H.; Suwardi; Amini, S.; Widjaksana

1999-03-01

The proceeding contains papers presented in the Fourth Scientific Presentation on Nuclear Fuel Element Cycle with theme of Technology of Nuclear Fuel Cycle facing the Challenge of Energy Need on the 21 s t Century, held on 1-2 December in Jakarta, Indonesia. These papers were divided by three groups that are technology of exploration, processing, purification and analysis of nuclear materials; technology of nuclear fuel elements and structures; and technology of waste management, safety and management of nuclear fuel cycle. There are 36 papers indexed individually. (ID)

Poolside inspection, repair and reconstitution of LWR fuel elements. Proceedings of a Technical Committee meeting

International Nuclear Information System (INIS)

1998-11-01

The Technical Committee Meeting on Poolside Inspection, repair and reconstruction of LWR Fuel Elements was organize by IAEA upon the recommendations of the International Working Group on Fuel performance Technology and held in Switzerland in October 1997. The purpose of the Meeting was to review the state of art in the area of poolside inspection, repair and reconstruction of light water fuel elements and to evaluate the progress achieved in this area since previous IAEA Meetings on the same topic in 1981 and 1984. The Meeting provided a forum on exchange of information between utilities, fuel designers and other authorities and specialists on a topic of current interest and real concern to industries in many Member States. The respective technologies are widely used or planned to be used in order to identify elementary major causes of fuel failure and to improve fuel utilization by repair and subsequent reuse of fuel elements. The Proceedings includes papers presented at the Meeting each described by a separate abstract

Fuel performance-REP, Seminars on nuclear fuel performance based on basic underlining phenomena, proceedings

International Nuclear Information System (INIS)

2008-01-01

possible. 2. Fission Gas Behaviour in Water Reactor Fuels, at Cadarache, France from 26-29 September 2000. The aim of this seminar was to draw up a comprehensive picture of our current understanding of fission gas behaviour and its impact on the fuel rod, under the widest possible conditions. 3. Pellet-Clad Interaction in Water Reactor Fuels, at Aix-en-Provence, France from 9-11 March 2004. The aim of this seminar was to draw up a comprehensive picture of our current understanding of pellet clad interaction and its impact on the fuel rod, under the widest possible conditions. The proceedings of these seminars are assembled here

Studies on fuels with low fission gas release. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

1997-10-01

For more than a decade, the IAEA has organized various specialists meetings to discuss advances in nuclear fuel technology for non-water cooled reactors. In order to review progress in research and development of fuels with low fission gas release for light water reactors, fast reactors and research reactors, an IAEA Technical Committee meeting was organized in October 1996. At the invitation of the Government of the Russian Federation, the meeting was held in Moscow. Experts from seven Member States and one international organization participated. The objective of the meeting was to exchange topical information on such fuels, to evaluate their advantages and drawbacks, and to explore their commercial utilization. The present volume contains the full text of the sixteen papers presented at the meeting. The information compiled in these proceedings should be useful for engineers, scientists and managers from nuclear fuel development organizations, fuel fabrication plants, utilities and regulatory bodies who are involved in the analysis of fuel behaviour under normal and accident conditions. Refs, figs, tabs

New Nuclear Materials Including Non Metallic Fuel Elements. Vol. II. Proceedings of the Conference on New Nuclear Materials Technology, Including Non Metallic Fuel Elements

International Nuclear Information System (INIS)

1963-01-01

One of the major aims of the International Atomic Energy Agency in furthering the peaceful uses of atomic energy is to encourage the development of economical nuclear power. Certainly, one of the more obvious methods of producing economical nuclear power is the development of economical fuels that can be used at high temperatures for long periods of time, and which have sufficient strength and integrity to operate under these conditions without permitting the release of fission products. In addition it is desirable that after irradiation these new fuels be economically reprocessed to reduce further the cost of the fuel cycle. As nuclear power becomes more and more competitive with conventional power the interest in new and more efficient higher-temperature fuels naturally increases rapidly. For these reasons, the Agency organized a Conference on New Nuclear Materials Technology, Including Non-Metallic Fuel Elements, which was held from 1 to 5 July 1963 at the International Hotel, Prague, with the assistance and co-operation of the Government of the Czechoslovak Socialist Republic. A total of 151 scientists attended, from 23 countries and 4 international organizations. The participants heard and discussed more than 60 scientific papers. The Agency wishes to thank the scientists who attended this Conference for their papers and for many spirited discussions that truly mark a successful meeting. The Agency wishes also to record its gratitude for the assistance and generous hospitality accorded the Conference, the participants and the Agency's staff by the Government of the Czechoslovak Socialist Republic and by the people of Prague. The scientific information contained in these Proceedings should help to quicken the pace of progress in the fabrication of new and m ore economical fuels, and it is hoped that these proceedings will be found useful to all workers in this and related fields

Advanced Fuel Pellet Materials and Fuel Rod Design for Water Cooled Reactors. Proceedings of a Technical Committee Meeting

International Nuclear Information System (INIS)

2010-10-01

institutions and regulatory authorities from 20 Member States. The papers submitted to the meeting were organized into three sessions, covering the areas of fabrication and design, advanced fuels and innovative fuel designs. In addition, there was a special round table discussion that addressed in detail the regulatory aspects of fuel quality assurance. These proceedings contain all the papers presented and discussed during the meeting, and highlight the key findings and recommendations based on the perceptions of the chairmen.

Proceedings of the KNS spring meeting

International Nuclear Information System (INIS)

2004-01-01

This proceedings contains articles of 2004 spring meeting of the Korean Nuclear Society. It was held on May 27-28, 2004 in Gyeongju, Korea. This proceedings is comprised of 10 sessions. The main subject titles of session are as follows: reactor physics and nuclear reactor design, thermodynamics and fluid flow, reactor operation and control, reactor safety, reactor fuels and nuclear materials, fuel cycle and waste management, radiation protection, nuclear fusion and laser technology, fuel cycle and waste management, nuclear fuel and nuclear materials, radiation protection, radiation application, life time management and decontamination, nuclear structure, nuclear beam application and nuclear fusion, nuclear policy. (Yi, J. H.)

Proceedings of the KNS spring meeting

International Nuclear Information System (INIS)

2003-01-01

This proceedings contains articles of 2003 spring meeting of the Korean Nuclear Society. It was held on May 29-30, 2003 in Gyeongju, Korea. This proceedings is comprised of 12 sessions. The main subject titles of session are as follows: reactor physics and nuclear reactor design, reactor operation and control, thermodynamics and fluid flow, reactor safety, reactor fuels and nuclear materials, fuel cycle and waste management, radiation protection, nuclear fusion and laser technology, fuel cycle and waste management, nuclear fuel and nuclear materials, radiation protection, radiation application, life time management and decontamination, nuclear structure, nuclear physics and nuclear fusion, nuclear policy. (Yi, J. H.)

Advances in fuel pellet technology for improved performance at high burnup. Proceedings of a Technical Committee meeting

International Nuclear Information System (INIS)

1998-08-01

The IAEA has recently completed two co-ordinated Research Programmes (CRPs) on The Development of Computer Models for Fuel Element Behaviour in Water Reactors, and on Fuel Modelling at Extended Burnup. Through these CRPs it became evident that there was a need to obtain data on fuel behaviour at high burnup. Data related o thermal behaviour, fission gas release and pellet to clad mechanical interaction were obtained and presented at the Technical Committee Meeting on Advances in Fuel Pellet Technology for Improved Performance at High Burnup which was recommended by the International Working Group on Fuel Performance and Technology (IWGFPT). The 34 papers from 10 countries are published in this proceedings and presented by a separate abstract. The papers were grouped in 6 sessions. First two sessions covered the fabrication of both UO 2 fuel and additives and MOX fuel. Sessions 3 and 4 covered the thermal behaviour of both types of fuel. The remaining two sessions dealt with fission gas release and the mechanical aspects of pellet to clad interaction

Symposium proceedings: environmental aspects of fuel conversion technology, IV (April 1979, Hollywood, FL)

Energy Technology Data Exchange (ETDEWEB)

Ayer, F.A.; Jones, N.S. (comps.)

1979-09-01

The proceedings document presentations made at the symposium on Environmental Aspects of Fuel Conversion Technology are presented. The symposium acted as a colloquium for discussion of environmentally related information on coal gasification and liquefaction. The program included sessions on program approach, environmental assessment, and control technology development. Process developers, process users, research scientists and state and federal government officials participated in this symposium, the fourth to be conducted by IERL-RTP on the subject since 1974. Separate abstracts have been prepared of individual presentations for inclusion in the Energy Data Base.

Proceeding of the Fifth Scientific Presentation on Nuclear Fuel Cycle: Development of Nuclear Fuel Cycle Technology in Third Millennium; Presentasi Ilmiah Daur Bahan Bakar Nuklir V: Pengembangan Teknologi Daur Bahan Bakar Nuklir Dalam Menyongsong Milenium Ketiga

Energy Technology Data Exchange (ETDEWEB)

Suripto, A; Sastratenaya, A S; Sutarno, D [National Atomic Energy Agency, Serpong (Indonesia); and others

2000-03-08

The proceeding contains papers presented in the Fifth Scientific Presentation on Nuclear Fuel Element Cycle with theme of Development of Nuclear Fuel Cycle Technology in Third Millennium, held on 22 February in Jakarta, Indonesia. These papers were divided by three groups that are technology of exploration, processing, purification and analysis of nuclear materials; technology of nuclear fuel elements and structures; and technology of waste management, safety and management of nuclear fuel cycle. There are 35 papers indexed individually. (id)

Proceedings of DUPIC fuel workshop 97

International Nuclear Information System (INIS)

1997-07-01

The researchers discuss the technical aspects of DUPIC fuel fabrication in the workshop as follows; 1) The DUPIC fuel development program in KAERI 2) AECL's progress in developing the DUPIC fuel fabrication process 3) Mechanical decladding 4) Nonproliferation and safeguards aspects of the DUPIC fuel cycle concept 5) Assessment of DUPIC fuel compatibility with CANDU-6 6) The development of combination software for spent PWR fuel to fabricate the homogeneous DUPIC fuel 7) Thermodynamic properties of the DUPIC fuel and its performance 8) Captural properties of cesium and ruthenium 9) A secondary fuel removal process : Plasma processing 10) Technology development for DUPIC process safeguards

Proceedings of DUPIC fuel workshop 97

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-07-01

The researchers discuss the technical aspects of DUPIC fuel fabrication in the workshop as follows; (1) The DUPIC fuel development program in KAERI (2) AECL`s progress in developing the DUPIC fuel fabrication process (3) Mechanical decladding (4) Nonproliferation and safeguards aspects of the DUPIC fuel cycle concept (5) Assessment of DUPIC fuel compatibility with CANDU-6 (6) The development of combination software for spent PWR fuel to fabricate the homogeneous DUPIC fuel (7) Thermodynamic properties of the DUPIC fuel and its performance (8) Captural properties of cesium and ruthenium (9) A secondary fuel removal process : Plasma processing (10) Technology development for DUPIC process safeguards.

Proceedings of fuel strategies for conventional and unconventional fuels

International Nuclear Information System (INIS)

Mahr, D.; Nechvatal, T.T.

1991-01-01

Fuel selection is a major decision for a power engineer. It is the single largest item in the power plant operating budget and has a major effect on power plant economics. Fuel determines plant design requirements and the types of systems that are provided. As a result, it affects capital budgets and financing requirements. In the last few decades, we have seen different fuels of choice at any one time. Coal has always been a staple for power generation. During the 1950s and 1960s, oil became an attractive alternative. Nuclear fuel became a popular choice due to its very low energy cost. After Three-Mile-Island, however, capital budgets went through the roof, resulting in severe financial constraints. Natural gas, which was rationed in some regions a few years ago, is now a popular choice. Some sources predict that its cost will increase faster than other fuels. To mitigate the relative variations in energy cost for different fuels, a balanced energy plan is required. A balanced power generation plan with fuel options provides the flexibility to react to unpredictable changes. The papers in this book are a continuation of the Fuel Strategies theme. Three technical topics are covered: Converting to Orimulsion, A Replacement Fuel for Heavy Oil; Innovations in Handling Conventional and Unconventional Fuels for Power Plants; and Pacific Rim Experience With Coal

36 CFR 218.14 - Judicial proceedings.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 2 2010-07-01 2010-07-01 false Judicial proceedings. 218.14... ADMINISTRATIVE REVIEW PROCESSES Predecisional Administrative Review Process for Hazardous Fuel Reduction Projects Authorized by the Healthy Forests Restoration Act of 2003 § 218.14 Judicial proceedings. The objection...

Design, Manufacturing and Irradiation Behaviour of Fast Reactor Fuel. Proceedings of a Technical Meeting

International Nuclear Information System (INIS)

2013-04-01

, Development of SFR Oxide Fuel, Development of Advanced Fuel and Structural Materials Development. These proceedings include all papers and session summaries, where the latter are based on contributions from session chairpersons.

Proceedings of the international meeting on research and test reactor core conversions from HEU to LEU fuels

Energy Technology Data Exchange (ETDEWEB)

Travelli, A [Argonne National Laboratory, Argonne, IL (United States)

1983-09-01

Conversion of research and test reactor cores from the use of high enrichment uranium to the use of low enrichment uranium depends on the cooperation of many research organizations, reactor operators, and government agencies. At a technical level, it involves almost all aspects of the fuel cycle, including fuel development, testing, shipping and reprocessing; experiment performance; economics; and safety and licensing aspects. The reactors involved and the conversion activities are distributed among approximately 25 countries, making this a subject which is best dealt with on an international basis. To foster direct communication in this area, the Reduced Enrichment Research and Test Reactor (RERTR) Program, at the Argonne National Laboratory, sponsored this meeting as the fifth of a series which began in 1978. The previous meetings were held at Argonne (International Meeting of Research Reactor Fuel Designers, Developers, and Fabricators, Argonne National Laboratory, Argonne, U.S.A., November 910, 1978), at Saclay (IAEA Consultants' Meeting on Research Reactor Core Conversions from HEU to LEU, Centre d'etudes Nucleaires de Saclay, Saclay, France, December 12-14, 1979), at Argonne (International Meeting on Development, Fabrication and Application of Reduced Enrichment Fuels for Research and Test Reactors, Argonne National Laboratory, Argonne, U.S.A., November 12-14, 1980) and at Juelich (Seminar on Research Reactor Operation and Use, Juelich Nuclear Research Center, Juelich, F.R.G., September 48, 1981). Proceedings from the two most recent previous meetings were published as ANL/RERTR/TM-3 (CONF-801144) and IAEA-SR-77. The spirit of this meeting differs slightly from that of the previous meetings. The advances which have been made and the growing maturity of the effort have caused a gradual shift of emphasis away from those topics which dominated the floor during the first meetings, such as fuel and methods development, and towards topics which concern more

Proceedings of the international meeting on research and test reactor core conversions from HEU to LEU fuels

International Nuclear Information System (INIS)

Travelli, A.

1983-09-01

Conversion of research and test reactor cores from the use of high enrichment uranium to the use of low enrichment uranium depends on the cooperation of many research organizations, reactor operators, and government agencies. At a technical level, it involves almost all aspects of the fuel cycle, including fuel development, testing, shipping and reprocessing; experiment performance; economics; and safety and licensing aspects. The reactors involved and the conversion activities are distributed among approximately 25 countries, making this a subject which is best dealt with on an international basis. To foster direct communication in this area, the Reduced Enrichment Research and Test Reactor (RERTR) Program, at the Argonne National Laboratory, sponsored this meeting as the fifth of a series which began in 1978. The previous meetings were held at Argonne (International Meeting of Research Reactor Fuel Designers, Developers, and Fabricators, Argonne National Laboratory, Argonne, U.S.A., November 910, 1978), at Saclay (IAEA Consultants' Meeting on Research Reactor Core Conversions from HEU to LEU, Centre d'etudes Nucleaires de Saclay, Saclay, France, December 12-14, 1979), at Argonne (International Meeting on Development, Fabrication and Application of Reduced Enrichment Fuels for Research and Test Reactors, Argonne National Laboratory, Argonne, U.S.A., November 12-14, 1980) and at Juelich (Seminar on Research Reactor Operation and Use, Juelich Nuclear Research Center, Juelich, F.R.G., September 48, 1981). Proceedings from the two most recent previous meetings were published as ANL/RERTR/TM-3 (CONF-801144) and IAEA-SR-77. The spirit of this meeting differs slightly from that of the previous meetings. The advances which have been made and the growing maturity of the effort have caused a gradual shift of emphasis away from those topics which dominated the floor during the first meetings, such as fuel and methods development, and towards topics which concern more

Structural behaviour of fuel assemblies for water cooled reactors. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2005-07-01

At the invitation of the Government of France and in response to a proposal of the IAEA Technical Working Group on Water Reactor Fuel Performance and Technology (TWGFPT), the IAEA convened a Technical Meeting on Fuel Assembly Structural Behaviour in Cadarache, France, from 22 to 26 November 2004. The meeting was hosted by the CEA Cadarache Centre, AREVA Framatome-ANP and Electricite de France. The meeting aimed to provide in depth technical exchanges on PWR and WWER operational experience in the field of fuel assembly mechanical behaviour and the potential impact of future high burnup fuel management on fuel reliability. It addressed in-service experience and remedial solutions, loop testing experience, qualification and damage assessment methods (analytic or experimental ones), mechanical behaviour of the fuel assembly including dynamic and fluid structure interaction aspects, modelling and numerical analysis methods, and impact of the in-service evolution of the structural materials. Sixty-seven participants from 17 countries presented 30 papers in the course of four sessions. The topics covered included the impact of hydraulic loadings on fuel assembly (FA)performance, FA bow and control rod (CR) drop kinetics, vibrations and rod-to-grid wear and fretting, and, finally, evaluation and modelling of accident conditions, mainly from seismic causes. FA bow, CR drop kinetics and hydraulics are of great importance under conditions of higher fuel duties including burnup increase, thermal uprates and longer fuel cycles. Vibrations and rod-to-grid wear and fretting have been identified as a key cause of fuel failure at PWRs during the past several years. The meeting demonstrated that full-scale hydraulic tests and modelling provide sufficient information to develop remedies to increase FA skeleton resistance to hydraulic loads, including seismic ones, vibrations and wear. These proceedings are presented as a book with an attached CD-ROM. The first part of the CD

Technologies for gas cooled reactor decommissioning, fuel storage and waste disposal. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

1998-09-01

Gas cooled reactors (GCRs) and other graphite moderated reactors have been important part of the world's nuclear programme for the past four decades. The wide diversity in status of this very wide spectrum of plants from initial design to decommissioning was a major consideration of the International Working group on Gas Cooled Reactors which recommended IAEA to convene a Technical Committee Meeting dealing with GCR decommissioning, including spent fuel storage and radiological waste disposal. This Proceedings includes papers 25 papers presented at the Meeting in three sessions entitled: Status of Plant Decommissioning Programmes; Fuels Storage Status and Programmes; waste Disposal and decontamination Practices. Each paper is described here by a separate abstract

IPHE Infrastructure Workshop Proceedings

Energy Technology Data Exchange (ETDEWEB)

None

2010-02-01

This proceedings contains information from the IPHE Infrastructure Workshop, a two-day interactive workshop held on February 25-26, 2010, to explore the market implementation needs for hydrogen fueling station development.

Third International Fuel Cell Conference. Proceedings

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-11-30

The Third International Fuel Cell Conference was held on November 30 to December 3, 1999 in City of Nagoya. A total of 139 papers, including those for plenary, sectional and poster cessions, were presented. In the plenary session, US's DOE presented fuel cell power plant development in the United States, EC fuel cells in perspective and fifth European framework programme, and Japan overview of the New Sunshine Program. In the polymer electrolyte fuel cells sessions, 23 papers were presented, including current status of commercialization and PEMFC systems developed by Toshiba. In the phosphoric acid fuel cells session, 6 papers were presented, including field test results and market developments. In the molten carbonate fuel cells session, 24 papers were presented, including development of 1,000kW MCFC power plant. In the solid oxide fuel cells session, 20 papers were presented, including 100kW SOFC field test results. The other topics include market analysis and fuel processes. (NEDO)

Third International Fuel Cell Conference. Proceedings

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-11-30

The Third International Fuel Cell Conference was held on November 30 to December 3, 1999 in City of Nagoya. A total of 139 papers, including those for plenary, sectional and poster cessions, were presented. In the plenary session, US's DOE presented fuel cell power plant development in the United States, EC fuel cells in perspective and fifth European framework programme, and Japan overview of the New Sunshine Program. In the polymer electrolyte fuel cells sessions, 23 papers were presented, including current status of commercialization and PEMFC systems developed by Toshiba. In the phosphoric acid fuel cells session, 6 papers were presented, including field test results and market developments. In the molten carbonate fuel cells session, 24 papers were presented, including development of 1,000kW MCFC power plant. In the solid oxide fuel cells session, 20 papers were presented, including 100kW SOFC field test results. The other topics include market analysis and fuel processes. (NEDO)

Proceedings: 1993 fuel oil utilization workshop

International Nuclear Information System (INIS)

1994-08-01

The primary objective of the Workshop was to utilize the experiences of utility personnel and continue the interchange of information related to fuel oil issues. Participants also identified technical problem areas in which EPRI might best direct its efforts in research and development of fuel oil utilization and to improve oil-fired steam generating systems' performance. Speakers presented specific fuel projects conducted at their particular utilities, important issues in the utilization of fuel oil, studies conducted or currently in the process of being completed, and information on current and future regulations for fuel utilization. Among the major topics addressed at the 1993 Fuel Oil Utilization Workshop were burner and ESP improvements for the reduction of particulate and NO x emissions, practical experience in utilization of low API gravity residual fuel oils, the use of models to predict the spread of oil spills on land, implementing OPA 90 preparedness and response strategies planning, a report on the annual Utility Oil Buyers Conference, ASTM D-396 specification for No. 6 fuel oil, the utilization of Orimulsion reg-sign in utility boilers, recent progress on research addressing unburned carbon and opacity from oil-fired utility boilers, EPRI's hazardous air pollutant monitoring and implications for residual fuel oil, and the feasibility of toxic metals removal from residual fuel oils. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

Proceedings of the second seminar on the new fuel technology toward the 21st century, November 25-26, 1997, Korea Atomic Energy Research Institute, Taejon, Korea

International Nuclear Information System (INIS)

1997-01-01

This proceedings includes, together with the discussion of the results obtained from the R and D works performed during this year, the topics on the various nuclear fuel technologies being conceived, envisaged or developed for various reactor systems with a wide spectrum from fundamental approaches to applied engineering and from fuel design technologies to manufacturing and materials problems

Proceedings of the second seminar on the new fuel technology toward the 21st century, November 25-26, 1997, Korea Atomic Energy Research Institute, Taejon, Korea

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

This proceedings includes, together with the discussion of the results obtained from the R and D works performed during this year, the topics on the various nuclear fuel technologies being conceived, envisaged or developed for various reactor systems with a wide spectrum from fundamental approaches to applied engineering and from fuel design technologies to manufacturing and materials problems.

Proceedings: pellet fuels conference

Energy Technology Data Exchange (ETDEWEB)

1995-12-31

The conference brought together professionals from the process- engineered-fuels (PEF), utility, paper, plastics, and boiler industries. Although the last two decades have produced technical breakthroughs, efforts to advance PEF must now focus on increasing commercial breakthroughs. Successful commercialization will depend on increasing supplier, consumer, and regulator confidence and support by demonstrating the performance and value of PEF products. Speakers provided updates on how PEF technology is evolving with respect to technical, economic, and regulatory challenges. Actions critical toward full commercialization of PEF were then considered. Discussion groups addressed materials sourcing, fuel processing and transportation, combustion, and ash handling.

Proceedings of the Water Reactor Fuel Performance Meeting - WRFPM / Top Fuel 2009

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-06-15

SFEN, ENS, SNR, ANS, AESJ, CNS KNS, IAEA and NEA are jointly organizing the 2009 International Water Reactor Fuel Performance / TopFuel 2009 Meeting following the 2008 KNS Water Reactor Performance Meeting held during October 19-23, 2008 in Seoul, Korea. This meeting is held annually on a tri-annual rotational basis in Europe, USA and Asia. In 2009, this meeting will be held in Paris, September 6-10, 2009 in coordination with the Global 2009 Conference at the same date and place. That would lead to a common opening session, some common technical presentations, a common exhibition and common social events. The technical scope of the meeting includes all aspects of nuclear fuel from fuel rod to core design as well as manufacturing, performance in commercial and test reactors or on-going and future developments and trends. Emphasis will be placed on fuel reliability in the general context of nuclear 'Renaissance' and recycling perspective. The meeting includes selectively front and/or back end issues that impact fuel designs and performance. In this frame, the conference track devoted to 'Concepts for transportation and interim storage of spent fuels and conditioned waste' will be shared with 'GLOBAL' conference. Technical Tracks: - 1. Fuel Performance, Reliability and Operational Experience: Fuel operating experience and performance; experience with high burn-up fuels; water side corrosion; stress corrosion cracking; MOX fuel performance; post irradiation data on lead fuel assemblies; radiation effects; water chemistry and corrosion counter-measures. - 2. Transient Fuel Behaviour and Safety Related Issues: Transient fuel behavior and criteria (RIA, LOCA, ATWS, Ramp tests..). Fuel safety-related issues such as PCI (pellet cladding interaction), transient fission gas releases and cladding bursting/ballooning during transient events - Advances in fuel performance modeling and core reload methodology, small and large-scale fuel testing

Proceedings of the Water Reactor Fuel Performance Meeting - WRFPM / Top Fuel 2009

International Nuclear Information System (INIS)

2009-06-01

SFEN, ENS, SNR, ANS, AESJ, CNS KNS, IAEA and NEA are jointly organizing the 2009 International Water Reactor Fuel Performance / TopFuel 2009 Meeting following the 2008 KNS Water Reactor Performance Meeting held during October 19-23, 2008 in Seoul, Korea. This meeting is held annually on a tri-annual rotational basis in Europe, USA and Asia. In 2009, this meeting will be held in Paris, September 6-10, 2009 in coordination with the Global 2009 Conference at the same date and place. That would lead to a common opening session, some common technical presentations, a common exhibition and common social events. The technical scope of the meeting includes all aspects of nuclear fuel from fuel rod to core design as well as manufacturing, performance in commercial and test reactors or on-going and future developments and trends. Emphasis will be placed on fuel reliability in the general context of nuclear 'Renaissance' and recycling perspective. The meeting includes selectively front and/or back end issues that impact fuel designs and performance. In this frame, the conference track devoted to 'Concepts for transportation and interim storage of spent fuels and conditioned waste' will be shared with 'GLOBAL' conference. Technical Tracks: - 1. Fuel Performance, Reliability and Operational Experience: Fuel operating experience and performance; experience with high burn-up fuels; water side corrosion; stress corrosion cracking; MOX fuel performance; post irradiation data on lead fuel assemblies; radiation effects; water chemistry and corrosion counter-measures. - 2. Transient Fuel Behaviour and Safety Related Issues: Transient fuel behavior and criteria (RIA, LOCA, ATWS, Ramp tests..). Fuel safety-related issues such as PCI (pellet cladding interaction), transient fission gas releases and cladding bursting/ballooning during transient events - Advances in fuel performance modeling and core reload methodology, small and large-scale fuel testing facilities. - 3. Advances in Water

Safety and engineering aspects of spent fuel storage. Proceedings of an international symposium held in Vienna, 10-14 October 1994

International Nuclear Information System (INIS)

1995-01-01

Spent fuel management is one of the most vital, and common, problems for countries with nuclear reactors. In the closed nuclear fuel cycle, further storage capacity may be required to match the arisings of spent fuel with the available capacity of reprocessing plants. With respect to the once-through cycle, interim storage of spent fuel is required until a final repository has been constructed and is in service. Though present spent fuel storage technologies provide adequate protection to the population and the environment, there is keen interest in seeing whether further improvements can be achieved in the area of spent fuel storage. This Symposium was a co-operative effort between the Nuclear Energy Agency of the OECD and the IAEA. Such meetings have been organized once every four years since 1987. The purpose is to: exchange information on the state of the art and on prospects for spent fuel storage; discuss the worldwide situation and the major factors influencing national policies in this field; and identify the most important direction that national efforts and international co-operation should take in this area. Over 140 participants from 39 countries and 4 international organizations attended the Symposium. Thirty-five full papers and 13 posters were presented and are included in these Proceedings. Refs, figs and tabs

Third international conference on CANDU fuel

International Nuclear Information System (INIS)

Boczar, Peter

1992-01-01

These proceedings contain full texts of all 49 papers from the ten sessions and the banquet address. The sessions were on the following subjects: International experience and programs; Fuel behaviour and operating experience; Fuel modelling; Fuel design; Advanced fuel and fuel cycle technology; AECL's concept for the disposal of nuclear fuel waste. The individual papers have been abstracted separately

Proceedings of the US Department of Energy environmental control symposium. Volume 1. Plenary session and fossil fuels

Energy Technology Data Exchange (ETDEWEB)

None

1979-09-01

Volume one of the proceedings (Plenary Session and Fossil Fuels) contains papers on environmental pollution control which resulted mainly from US DOE's research programs in coal (preparation, desulfurization, gasification, liquefaction, combustion, fluidized-bed combustion, and pollution control methods with respect to SO/sub 2/, NO/sub x/, and CO/sub 2/ (global effects and feasibility studies); a few papers deal with oil shale operations and the enhanced recovery of petroleum. Papers have been entered individually into EDB and ERA, with 3 also into EAPA; six papers had been entered previously from other sources. (LTN)

Experience with spent fuel storage at research and test reactors. Proceedings of an advisory group meeting held in Vienna, 5-8 July 1993

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-01-01

Irradiated fuel from research and test reactors has been stored at various facilities for several decades. As these facilities age and approach or exceed their original design lifetimes, there is mounting concern about closure of the fuel cycle and about the integrity of ageing fuels from the materials point of view as well as some concern about the loss of self-protection of the fuels as their activity decays. It is clear that an international effort is necessary to give these problems sufficient exposure and to ensure that work begins on appropriate solutions. To obtain an overall picture of the size and extent of these problems, an Advisory Group Meeting on Storage Experience with Spent Fuel from Research Reactors was convened in Vienna 5-8 July 1993, and attended by twelve participants and three observers representing thirteen different countries. These proceedings contain the country reports presented at the meeting. Refs, figs and tabs.

Experience with spent fuel storage at research and test reactors. Proceedings of an advisory group meeting held in Vienna, 5-8 July 1993

International Nuclear Information System (INIS)

1995-01-01

Irradiated fuel from research and test reactors has been stored at various facilities for several decades. As these facilities age and approach or exceed their original design lifetimes, there is mounting concern about closure of the fuel cycle and about the integrity of ageing fuels from the materials point of view as well as some concern about the loss of self-protection of the fuels as their activity decays. It is clear that an international effort is necessary to give these problems sufficient exposure and to ensure that work begins on appropriate solutions. To obtain an overall picture of the size and extent of these problems, an Advisory Group Meeting on Storage Experience with Spent Fuel from Research Reactors was convened in Vienna 5-8 July 1993, and attended by twelve participants and three observers representing thirteen different countries. These proceedings contain the country reports presented at the meeting. Refs, figs and tabs

Hot Cell Post-Irradiation Examination and Poolside Inspection of Nuclear Fuel. Proceedings of the IAEA-HOTLAB Technical Meeting

International Nuclear Information System (INIS)

2013-04-01

The growing operational requirements for nuclear fuel, such as longer fuel cycles, higher burnups and wider use of transient regimes, require more robust fuel designs and more radiation resistant materials. Development of such advanced fuels is only possible with testing and analysis of their performance and application of adequate post-irradiation examination (PIE) methods and techniques. In addition, operational feedback data from poolside and PIE facilities are absolutely necessary for verification of fuel modelling codes and analysis of fuel failure mechanisms. For these reasons, the International Atomic Energy Agency (IAEA) has supported the international exchange of knowledge and sharing of best practices in the application of modern destructive and non-destructive methods of investigation of highly radioactive materials through a series of technical meetings (TMs), the last of which was held in 2006 in Buenos Aires. Since 1963, similar meetings, initially at the European level, have been organized by the Hot Laboratories and Remote Handling Working Group (HOTLAB), a partner in the development of the IAEA's Post Irradiation Examination Facilities Database (PIEDB), part of the IAEA's Integrated Nuclear Fuel Cycle Information System. With this successful partnership in mind, in 2010 the IAEA Technical Working Group on Fuel Performance and Technology recommended that a joint IAEA-HOTLAB TM be held on 'Hot Cell Post-Irradiation Examination and Pool-Side Inspection of Nuclear Fuel', covering questions relevant to the IAEA sub-programmes on 'Nuclear Power Reactor Fuel Engineering' and 'Management of Spent Fuel from Nuclear Power Reactors'. The TM was held on 23-27 May 2011, in Smolenice, Slovakia, with the participation of a large number of interested organizations and comprehensive coverage of major PIE and poolside inspection issues relating to both operation and storage of fuel for nuclear power reactors. The proceedings, summaries and conclusions of that joint

Modelling of Water Cooled Fuel Including Design Basis and Severe Accidents. Proceedings of a Technical Meeting

International Nuclear Information System (INIS)

2015-11-01

The demands on nuclear fuel have recently been increasing, and include transient regimes, higher discharge burnup and longer fuel cycles. This has resulted in an increase of loads on fuel and core internals. In order to satisfy these demands while ensuring compliance with safety criteria, new national and international programmes have been launched and advanced modelling codes are being developed. The Fukushima Daiichi accident has particularly demonstrated the need for adequate analysis of all aspects of fuel performance to prevent a failure and also to predict fuel behaviour were an accident to occur.This publication presents the Proceedings of the Technical Meeting on Modelling of Water Cooled Fuel Including Design Basis and Severe Accidents, which was hosted by the Nuclear Power Institute of China (NPIC) in Chengdu, China, following the recommendation made in 2013 at the IAEA Technical Working Group on Fuel Performance and Technology. This recommendation was in agreement with IAEA mid-term initiatives, linked to the post-Fukushima IAEA Nuclear Safety Action Plan, as well as the forthcoming Coordinated Research Project (CRP) on Fuel Modelling in Accident Conditions. At the technical meeting in Chengdu, major areas and physical phenomena, as well as types of code and experiment to be studied and used in the CRP, were discussed. The technical meeting provided a forum for international experts to review the state of the art of code development for modelling fuel performance of nuclear fuel for water cooled reactors with regard to steady state and transient conditions, and for design basis and early phases of severe accidents, including experimental support for code validation. A round table discussion focused on the needs and perspectives on fuel modelling in accident conditions. This meeting was the ninth in a series of IAEA meetings, which reflects Member States’ continuing interest in nuclear fuel issues. The previous meetings were held in 1980 (jointly with

Proceedings of the international meeting on development, fabrication, and application of Reduced Enrichment fuels for Research and Test Reactors (RERTR). Base technology

Energy Technology Data Exchange (ETDEWEB)

NONE

1983-08-01

The international effort to develop new fuel materials and designs which will make it feasible to fuel research and test reactors throughout the world with low-enrichment uranium, instead of high-enrichment uranium, has made significant progress during the past year. This progress has taken place at research centers located in many different countries, and is of crucial interest to reactor operators and licensors whose geographical distribution is even more varied. It is appropriate, therefore, that international meetings be held periodically to foster direct communication among the specialists in this area. To achieve this purpose, the Reduced Enrichment Research and Test Reactor (RERTR) Program, at the Argonne National Laboratory, sponsored this meeting as the third of a series which begun in 1978. The papers presented at this meeting were divided into sessions according to relevant subject: status of RERTR program and safety issues; development of new fuel types; testing of new fuel elements; specific reactor applications. These proceedings were edited by various members of the RERTR Program.

Proceedings of the international meeting on development, fabrication, and application of Reduced Enrichment fuels for Research and Test Reactors (RERTR). Base technology

International Nuclear Information System (INIS)

1983-08-01

The international effort to develop new fuel materials and designs which will make it feasible to fuel research and test reactors throughout the world with low-enrichment uranium, instead of high-enrichment uranium, has made significant progress during the past year. This progress has taken place at research centers located in many different countries, and is of crucial interest to reactor operators and licensors whose geographical distribution is even more varied. It is appropriate, therefore, that international meetings be held periodically to foster direct communication among the specialists in this area. To achieve this purpose, the Reduced Enrichment Research and Test Reactor (RERTR) Program, at the Argonne National Laboratory, sponsored this meeting as the third of a series which begun in 1978. The papers presented at this meeting were divided into sessions according to relevant subject: status of RERTR program and safety issues; development of new fuel types; testing of new fuel elements; specific reactor applications. These proceedings were edited by various members of the RERTR Program

Mox fuels recycling

International Nuclear Information System (INIS)

Gay, A.

1998-01-01

This paper will firstly emphasis that the first recycling of plutonium is already an industrial reality in France thanks to the high degree of performance of La Hague and MELOX COGEMA's plants. Secondly, recycling of spent Mixed OXide fuel, as a complete MOX fuel cycle, will be demonstrated through the ability of the existing plants and services which have been designed to proceed with such fuels. Each step of the MOX fuel cycle concept will be presented: transportation, reception and storage at La Hague and steps of spent MOX fuel reprocessing. (author)

Proceedings of the fuel cells `95 review meeting

Energy Technology Data Exchange (ETDEWEB)

George, T.J.

1995-08-01

This document contains papers presented at the Fuel Cells `95` Review Meeting. Topics included solid oxide fuel cells; DOE`s transportation program; ARPA advanced fuel cell development; molten carbonate fuel cells; and papers presented at a poster session. Individual papers have been processed separately for the U.S. DOE databases.

Spent-fuel-storage alternatives

International Nuclear Information System (INIS)

1980-01-01

The Spent Fuel Storage Alternatives meeting was a technical forum in which 37 experts from 12 states discussed storage alternatives that are available or are under development. The subject matter was divided into the following five areas: techniques for increasing fuel storage density; dry storage of spent fuel; fuel characterization and conditioning; fuel storage operating experience; and storage and transport economics. Nineteen of the 21 papers which were presented at this meeting are included in this Proceedings. These have been abstracted and indexed

Proceedings of the fourth international conference on CANDU maintenance

International Nuclear Information System (INIS)

1997-01-01

These proceedings record the information presented at the 4th International Conference on CANDU Maintenance held November 16-18,1997 in Toronto, Canada. The papers for these proceedings were prepared on component maintenance, human performance, steam generator leak detection, fuel channel inspections, rotating equipment maintenance, surveillance programs, inspection techniques, valve maintenance, steam generator repairs and performance, reactor aging management and preventative maintenance

Proceedings of the fourth international conference on CANDU maintenance

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-07-01

These proceedings record the information presented at the 4th International Conference on CANDU Maintenance held November 16-18,1997 in Toronto, Canada. The papers for these proceedings were prepared on component maintenance, human performance, steam generator leak detection, fuel channel inspections, rotating equipment maintenance, surveillance programs, inspection techniques, valve maintenance, steam generator repairs and performance, reactor aging management and preventative maintenance.

Proceedings of the KNS Fall meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-10-15

This proceedings contains articles of 2013 Fall meeting of the Korean Nuclear Society. It was held on Oct 23-25 in Kyungju, Korea. This proceedings is comprised of 10 sessions. The main subject titles of session are as follows: Reactor system technology, Nuclear data, reactor physics and computational science, Radioactive waste management, Nuclear fuel and materials, Thermal hydraulics and safety, Radiation utilization and protection, Quantum engineering and nuclear fusion, Nuclear power plant construction and operation technology, Nuclear policy, human resources and cooperation, Nuclear I and C and remote operation. (Yi, J. H.)

Proceeding of the Fourth Scientific Presentation on Nuclear Fuel Cycle: Technology of Nuclear Fuel Cycle facing the Challenge of Energy Need on the 21-st Century; Prosiding presentasi ilmiah daur bahan bakar nuklir IV. Tema: teknologi daur bahan bakar nuklir menghadapi tantangan kebutuhan ketenagaan pada abad-21

Energy Technology Data Exchange (ETDEWEB)

Suripto, A [National Atomic Energy Agency, Serpong (Indonesia); Sajuti, D [Research and Development Center for Calibration Instrumentation and Metrology, Indonesian Institute of Sciences, Serpong (Indonesia); Aiman, S [Research and Development Center for Applied Chemistry, Indonesian Institute of Sciences, Serpong (Indonesia); Yuwono, I [National Atomic Energy Agency, Serpong (Indonesia); Fathurrachman, [National Atomic Energy Agency, Serpong (Indonesia); Suwarno, H [National Atomic Energy Agency, Serpong (Indonesia); Suwardi, [National Atomic Energy Agency, Serpong (Indonesia); Amini, S [National Atomic Energy Agency, Serpong (Indonesia); Widjaksana, [National Atomic Energy Agency, Serpong (Indonesia)

1999-03-01

The proceeding contains papers presented in the Fourth Scientific Presentation on Nuclear Fuel Element Cycle with theme of Technology of Nuclear Fuel Cycle facing the Challenge of Energy Need on the 21{sup s}t Century, held on 1-2 December in Jakarta, Indonesia. These papers were divided by three groups that are technology of exploration, processing, purification and analysis of nuclear materials; technology of nuclear fuel elements and structures; and technology of waste management, safety and management of nuclear fuel cycle. There are 36 papers indexed individually. (ID)

Proceedings of the Canadian Nuclear Society sixth annual conference

International Nuclear Information System (INIS)

French, P.M.; Phillips, G.J.

1985-01-01

The proceedings of the Sixth Annual Conference of the Canadian Nuclear Society comprise 103 papers on the following subjects: fuel technology, nuclear plant safety, instrumentation, public and regulatory matters, fusion, fuel behaviour under normal and accident conditions, nuclear plant design and operations, thermal hydraulics, reactor physics, accelerators, waste management, new reactor concepts

Spent-fuel-storage alternatives

Energy Technology Data Exchange (ETDEWEB)

1980-01-01

The Spent Fuel Storage Alternatives meeting was a technical forum in which 37 experts from 12 states discussed storage alternatives that are available or are under development. The subject matter was divided into the following five areas: techniques for increasing fuel storage density; dry storage of spent fuel; fuel characterization and conditioning; fuel storage operating experience; and storage and transport economics. Nineteen of the 21 papers which were presented at this meeting are included in this Proceedings. These have been abstracted and indexed. (ATT)

Proceedings of the Fuel Cells `97 Review Meeting

Energy Technology Data Exchange (ETDEWEB)

None

1998-01-01

The Federal Energy Technology Center (FETC) sponsored the Fuel Cells '97 Review Meeting on August 26-28, 1997, in Morgantown, West Virginia. The purpose of the meeting was to provide an annual forum for the exchange of ideas and discussion of results and plans related to the research on fuel cell power systems. The total of almost 250 conference participants included engineers and scientists representing utilities, academia, and government from the U.S. and eleven other countries: Canada, China, India, Iran, Italy, Japan, Korea, Netherlands, Russia, Taiwan, and the United Kingdom. On first day, the conference covered the perspectives of sponsors and end users, and the progress reports of fuel-cell developers. Papers covered phosphoric, carbonate, and solid oxide fuel cells for stationary power applications. On the second day, the conference covered advanced research in solid oxide and other fuel cell developments. On the third day, the conference sponsored a workshop on advanced research and technology development. A panel presentation was given on fuel cell opportunities. Breakout sessions with group discussions followed this with fuel cell developers, gas turbine vendors, and consultants.

Proceedings Forest & Field Fuels Symposium

Energy Technology Data Exchange (ETDEWEB)

None

1978-07-01

The purpose of the symposium is to examine two specific renewable resources, forest and field fuels, to pinpoint areas where funding of RD&D would be effective in expanding their marketability and use as substitutes for imported oil.

Proceedings of the 2007 LWR Fuel Performance Meeting / TopFuel 2007 'Zero by 2010'

International Nuclear Information System (INIS)

2007-01-01

ANS, ENS, AESJ and KNS are jointly organizing the 2007 International LWR Fuel Performance Meeting following the successful ENS TopFuel meeting held during 22-26 October, 2006 in Salamaca, Spain. Merging three premier nuclear fuel design and performance meetings: the ANS LWR Fuel Performance Meeting, the ENS TopFuel and Asian Water Reactor Fuel Performance Meeting (WRFPM) created this international meeting. The meeting will be held annually on a tri-annual rotational basis in USA, Asia, and Europe. The technical scope of the meeting includes all aspects of nuclear fuel from fuel rod to core design as well as performance experience in commercial and test reactors. The meeting excludes front end and back end fuel issues, however, it covers all front and/or back issues that impact fuel designs and performance

Proceedings of the Topical meeting on the reactor fuel performance - TopFuel 2012 Transactions

International Nuclear Information System (INIS)

2012-01-01

TopFuel is an annual topical meeting organised by ENS, the American Nuclear Society and the Atomic Energy Society of Japan. TopFuel's primary objective is to bring together leading specialists in the field from around the world to analyse advances in nuclear fuel management technology and to use the findings of the latest cutting-edge research to help manufacture the high performance nuclear fuels of today and tomorrow. Aim is to discuss the challenges facing the developers and manufacturers of new high-performance nuclear fuels - fuels that will help meet current and future energy demand and reduce man's over dependence upon CO 2 -emitting fossil fuels. The technical scope of Top Fuel 2012 includes all aspects of nuclear fuel from fuel rod to core design as well as manufacturing, performance in commercial and test reactors or on-going and future developments and trends. The meeting includes selectively front and/or back end issues that impact fuel designs and performance. (authors)

Proceedings of the GLOBAL 2009 congress - The Nuclear Fuel Cycle: Sustainable Options and Industrial Perspectives

International Nuclear Information System (INIS)

2009-06-01

GLOBAL 2009 is the ninth bi-annual scientific world meeting on the Nuclear Fuel Cycle (NFC) that started in 1993 in Seattle. This meeting has established itself as a dedicated international forum for experts, to provide an overall review of the status and new trends of research applications and policies related to the fuel cycle. The international nuclear community is actively developing advanced processes and innovative technologies that enhance economic competitiveness of nuclear energy and ensure its sustainability, through optimized utilization of natural resources, minimization of nuclear wastes, resistance to proliferation and compliance with safety requirements. In this context, and under the profound evolutions concerning energy supply, GLOBAL 2009 is a great opportunity for sharing ideas and visions on the NFC. Special emphasis are placed on the results of the international studies for developing next generation systems. GLOBAL 2009 highlights the technical challenges and successes involved in closing the NFC and recycling long lived nuclear waste. It is also an excellent occasion to review and discuss social and regulatory aspects as well as national plans and international policies and decision affecting the future of nuclear energy. This meeting provides a forum for the exchange of the newest ideas and developments related to the initiatives at of establishing an acceptable, reliable and universal international non proliferation regime. The congress, organized by the French Nuclear Energy Society (SFEN), under the aegis of the IAEA, NEA of the OECD and the UE Commission with the basic sponsorships of ANS, ENS and AESJ, combines plenary sessions, general panel sessions, parallel sessions and technical visits. The program has full length technical papers, which are peer reviewed and published in conference proceedings. A large industrial exhibition takes place to complement the congress. The GLOBAL 2009 congress is organized in coordination with the 2009

Proceedings of the GLOBAL 2009 congress - The Nuclear Fuel Cycle: Sustainable Options and Industrial Perspectives

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-06-15

GLOBAL 2009 is the ninth bi-annual scientific world meeting on the Nuclear Fuel Cycle (NFC) that started in 1993 in Seattle. This meeting has established itself as a dedicated international forum for experts, to provide an overall review of the status and new trends of research applications and policies related to the fuel cycle. The international nuclear community is actively developing advanced processes and innovative technologies that enhance economic competitiveness of nuclear energy and ensure its sustainability, through optimized utilization of natural resources, minimization of nuclear wastes, resistance to proliferation and compliance with safety requirements. In this context, and under the profound evolutions concerning energy supply, GLOBAL 2009 is a great opportunity for sharing ideas and visions on the NFC. Special emphasis are placed on the results of the international studies for developing next generation systems. GLOBAL 2009 highlights the technical challenges and successes involved in closing the NFC and recycling long lived nuclear waste. It is also an excellent occasion to review and discuss social and regulatory aspects as well as national plans and international policies and decision affecting the future of nuclear energy. This meeting provides a forum for the exchange of the newest ideas and developments related to the initiatives at of establishing an acceptable, reliable and universal international non proliferation regime. The congress, organized by the French Nuclear Energy Society (SFEN), under the aegis of the IAEA, NEA of the OECD and the UE Commission with the basic sponsorships of ANS, ENS and AESJ, combines plenary sessions, general panel sessions, parallel sessions and technical visits. The program has full length technical papers, which are peer reviewed and published in conference proceedings. A large industrial exhibition takes place to complement the congress. The GLOBAL 2009 congress is organized in coordination with the 2009

Fuels and auxiliary materials

International Nuclear Information System (INIS)

Svab, V.

A brief survey is given of the problems of fuels, fuel cans, absorption and moderator materials proceeding from the papers presented at the 1971 4th Geneva Conference on the Peaceful Uses of Nuclear Energy and the 1970 IAEA Conference in New York. Attention is focused on the behaviour of fuel and fuel can materials for thermal and fast reactors during irradiation, radiation stability of absorption materials and the effects of radiation on concrete and on moderator materials. (Z.M.)

Proceedings of the Korean Radioactive Waste Society Spring 2010

International Nuclear Information System (INIS)

2010-01-01

This proceedings contains articles of the Korean Radioactive Waste Society Spring 2010. It was held on May 13-14, 2010 in Yesan, Korea. The main topics are as follows: Radioactive wastes policy and decontamination and decommissioning, Radioactive waste treatment, Radioactive waste disposal and site selection, Spent fuel and fuel cycle and Radiation safety and environment. (Yi, J. H.)

Proceedings of the KNS 2015 Fall Meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-10-15

This proceedings contains articles of 2015 fall meeting of the Korean Nuclear Society. It was held on October 28-30 in Kyungju, Korea. This proceedings is comprised of 11 sessions. The main subject titles of session are as follows: Reactor system technology, Reactor physics and computational science, Radioactive waste management, Nuclear fuel and materials, Thermal hydraulics and safety, Radiation utilization and protection, Quantum engineering and nuclear fusion, Nuclear power plant construction and operation technology, Nuclear policy, human resources and cooperation, Nuclear I and C and automatic remote systems, Competition Session. (Yi, J. H.)

Proceedings of the KNS 2014 Fall Meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-10-15

This proceedings contains articles of 2014 Fall Meeting of the Korean Nuclear Society. It was held on Oct 29-31 in Pyongchang, Korea. This proceedings is comprised of 10 sessions. The main subject titles of session are as follows: Reactor system technology, Reactor physics and computational science, Radioactive waste management, Nuclear fuel and materials, Thermal hydraulics and safety, Radiation utilization and protection, Quantum engineering and nuclear fusion, Nuclear power plant construction and operation technology, Nuclear policy, human resources and cooperation, MMIS and remote control and Competition (Yi, J. H.)

Proceedings of the KNS 2016 Autumn Meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

2016-10-15

This proceedings contains articles of 2016 autumn meeting of the Korean Nuclear Society. It was held on Oct. 26-28 in Kyungju, Korea. This proceedings is comprised of 11 sessions. The main subject titles of session are as follows: Reactor system technology, Reactor physics and computational science, Radioactive waste management, Nuclear fuel and materials, Thermal hydraulics and safety, Radiation utilization and protection, Quantum engineering and nuclear fusion, Nuclear power plant construction and operation technology, Nuclear policy, human resources and cooperation, Nuclear I and C, human factors and automatic remote systems, Competition Session. (Yi, J. H.)

An impressive proceeding for the seven-year Finnish Tekes fuel cell programme : how a small country can be strong in developing emerging technologies

Energy Technology Data Exchange (ETDEWEB)

Ojapalo, A.; Saari, J.; Kotila, H.; Korkiakoski, M. [Tekes, Finnish Funding Agency for Technology and Innovation, Helsinki (Finland)

2009-07-01

Finland's national Fuel Cell strategy was created in 2006 in an effort to reduce air pollution and promote the use of renewable energy sources. The Fuel Cell Programme, which was launched in 2007 by the Finnish Funding Agency for Technology and Innovation has already funded 26 projects involving fuel cells for vehicles, as well as for stationary, portable and utility purposes. Total funding for the projects is over 12 million Euros. Industry partners have also invested in fuel cell development because of Tekes' promotion of consortium research projects that involve collaboration between public research organizations, universities, and companies. An essential feature of the Programme's activities is the cooperation between projects developing stationary SOFC, PEMFC, and hybrid solutions which enables synergy in component development. The corporate projects have resulted in successful demonstrations and commercial products. Finland is particularly strong in fuel cell system integration worldwide, and its technical research center (VTT) specializes in supporting industrial needs. Wartsila's integrated stationary system has proceeded to the field test phase with a fuel cell operated power unit in a housing area. Other commercial products are also being marketed, such as an alkaline fuel cell for cottage and leisure use. Other research projects involve telecommunications, nanotechnology, the printed enzymatic reel-to-reel fuel cell tag for RFID or medical applications, and hybridization for fuel cell vehicles. The programme encourages international collaboration through researcher exchange and coordinated research projects.

Proceedings of the 1991 Windsor workshop on alternative fuels

International Nuclear Information System (INIS)

1991-01-01

A workshop was held to exchange information among engine and vehicle manufacturers, fuel suppliers, research organizations, and academic and regulatory bodies on various aspects of alternative transportation fuels development. Papers were presented on alternative fuels policies and programs, zero-emission vehicles, emission control technologies, field evaluations of alternative fuel systems, and heavy duty alternate-fuel engines. Separate abstracts have been prepared for nine papers from this workshop

Proceedings -- US Russian workshop on fuel cell technologies

Energy Technology Data Exchange (ETDEWEB)

Baker, B.; Sylwester, A. [comps.

1996-04-01

On September 26--28, 1995, Sandia National Laboratories sponsored the first Joint US/Russian Workshop on Fuel Cell Technology at the Marriott Hotel in Albuquerque, New Mexico. This workshop brought together the US and Russian fuel cell communities as represented by users, producers, R and D establishments and government agencies. Customer needs and potential markets in both countries were discussed to establish a customer focus for the workshop. Parallel technical sessions defined research needs and opportunities for collaboration to advance fuel cell technology. A desired outcome of the workshop was the formation of a Russian/American Fuel Cell Consortium to advance fuel cell technology for application in emerging markets in both countries. This consortium is envisioned to involve industry and national labs in both countries. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

Proceedings of the 2nd NUCEF international symposium NUCEF`98. Safety research and development of base technology on nuclear fuel cycle

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

This volume contains 68 papers presented at the 2nd NUCEF International Symposium NUCEF`98 held on 16-17 November 1998, in Hitachinaka, Japan, following the 1st symposium NUCEF`95 (Proceeding: JAERI-Conf 96-003). The theme of this symposium was `Safety Research and Development of Base Technology on Nuclear Fuel Cycle`. The papers were presented in oral and poster sessions on following research fields: (1) Criticality Safety, (2) Reprocessing and Partitioning, (3) Radioactive Waste Management. The 68 papers are indexed individually. (J.P.N.)

Proceedings of the 2nd NUCEF international symposium NUCEF'98. Safety research and development of base technology on nuclear fuel cycle

International Nuclear Information System (INIS)

1999-03-01

This volume contains 68 papers presented at the 2nd NUCEF International Symposium NUCEF'98 held on 16-17 November 1998, in Hitachinaka, Japan, following the 1st symposium NUCEF'95 (Proceeding: JAERI-Conf 96-003). The theme of this symposium was 'Safety Research and Development of Base Technology on Nuclear Fuel Cycle'. The papers were presented in oral and poster sessions on following research fields: (1) Criticality Safety, (2) Reprocessing and Partitioning, (3) Radioactive Waste Management. The 68 papers are indexed individually. (J.P.N.)

Proceedings of the Canadian Nuclear Society 15. annual conference

Energy Technology Data Exchange (ETDEWEB)

Huynh, H M [Hydro-Quebec, Montreal, PQ (Canada)

1994-12-31

The proceedings of the 15. annual conference of the Canadian Nuclear Society cover a wide range of nuclear topics, but the emphasis is on CANDU reactors and Canadian experience. The 89 papers are arranged in 17 sessions dealing with the following subjects: thermalhydraulics, fuel channels, operations, reactor physics, fuel, new technology, safety, training, waste management. The individual papers have been abstracted separately.

Proceedings of the Canadian Nuclear Society 15. annual conference

International Nuclear Information System (INIS)

Huynh, H.M.

1994-01-01

The proceedings of the 15. annual conference of the Canadian Nuclear Society cover a wide range of nuclear topics, but the emphasis is on CANDU reactors and Canadian experience. The 89 papers are arranged in 17 sessions dealing with the following subjects: thermalhydraulics, fuel channels, operations, reactor physics, fuel, new technology, safety, training, waste management. The individual papers have been abstracted separately

Status and prospects for gas cooled reactor fuels. Proceedings of two IAEA meetings held in June 2004 and June 2005

International Nuclear Information System (INIS)

2009-04-01

Recently, efforts to develop high temperature gas cooled reactors with an aim to building futuristic nuclear energy systems with advanced nuclear fuel cycles in the context of the Generation IV International Forum have increased significantly. In addition, several development projects are ongoing, focusing on the burning of weapons grade plutonium, including civil plutonium and other transuranic elements using the 'deep-burn concept', or 'inert matrix fuels', especially in the form of coated particles in gas cooled reactor systems. There is also considerable global interest in developing 'nuclear hydrogen' energy systems using high temperature gas cooled reactors. Apart from these developments, the value of preserving the large technology base developed in Germany, the United Kingdom and the United States of America, as well as information developed in other countries, has also been a subject of interest to the IAEA. At the second annual meeting of the 'technical working group on nuclear fuel cycles options and spent fuel management' (TWG-NFCO), held in Vienna from 28-30 May 2003, it was recommended to hold a technical meeting on Current Status and Future Prospects of Gas Cooled Reactor Fuels. The meeting should cover the technological progress that has been made in the last three years and plan future fabrication and qualification facilities for GCR/HTR fuel. TWG-NFCO considered it timely that this progress should be presented and discussed in the interested community. Recognizing the numerous activities being pursued in many Member States, the IAEA convened the technical meeting on this topic in June 2004 in Vienna. Consequently, an update meeting was held in June 2005, which was hosted by the Kharkov Institute of Physics and Technology of Ukraine to review and integrate the latest developments. This publication combines the results of the technical meeting of June 2004 and the meeting of June 2005. The proceedings presented here contain 25 in depth papers on the

WWER reactor fuel performance, modelling and experimental support. Proceedings

International Nuclear Information System (INIS)

Stefanova, S.; Chantoin, P.; Kolev, I.

1994-01-01

This publication is a compilation of 36 papers presented at the International Seminar on WWER Reactor Fuel Performance, Modelling and Experimental Support, organised by the Institute for Nuclear Research and Nuclear Energy (BG), in cooperation with the International Atomic Energy Agency. The Seminar was attended by 76 participants from 16 countries, including representatives of all major Russian plants and institutions responsible for WWER reactor fuel manufacturing, design and research. The reports are grouped in four chapters: 1) WWER Fuel Performance and Economics: Status and Improvement Prospects: 2) WWER Fuel Behaviour Modelling and Experimental Support; 3) Licensing of WWER Fuel and Fuel Analysis Codes; 4) Spent Fuel of WWER Plants. The reports from the corresponding four panel discussion sessions are also included. All individual papers are recorded in INIS as separate items

WWER reactor fuel performance, modelling and experimental support. Proceedings

Energy Technology Data Exchange (ETDEWEB)

Stefanova, S; Chantoin, P; Kolev, I [eds.

1994-12-31

This publication is a compilation of 36 papers presented at the International Seminar on WWER Reactor Fuel Performance, Modelling and Experimental Support, organised by the Institute for Nuclear Research and Nuclear Energy (BG), in cooperation with the International Atomic Energy Agency. The Seminar was attended by 76 participants from 16 countries, including representatives of all major Russian plants and institutions responsible for WWER reactor fuel manufacturing, design and research. The reports are grouped in four chapters: (1) WWER Fuel Performance and Economics: Status and Improvement Prospects: (2) WWER Fuel Behaviour Modelling and Experimental Support; (3) Licensing of WWER Fuel and Fuel Analysis Codes; (4) Spent Fuel of WWER Plants. The reports from the corresponding four panel discussion sessions are also included. All individual papers are recorded in INIS as separate items.

Water Reactor Fuel Performance Meeting 2008

International Nuclear Information System (INIS)

2008-10-01

This meeting contains articles of the Water Reactor Fuel Performance Meeting 2008 of Korean Nuclear Society, Atomic Energy Society of Japan, Chinese Nuclear Society, European Nuclear Society and American Nuclear Society. It was held on Oct. 19-23, 2008 in Seoul, Korea and subject of Meeting is 'New Clear' Fuel - A green energy solution. This proceedings is comprised of 5 tracks. The main topic titles of track are as follows: Advances in water reactor fuel technology, Fuel performance and operational experience, Transient fuel behavior and safety-related issues, Fuel cycle, spent fuel storage and transportations and Fuel modeling and analysis. (Yi, J. H.)

Proceedings of the fuel cells 1994 contractors review meeting

Science.gov (United States)

Carpenter, C. P., II; Mayfield, M. J.

1994-08-01

METC annually sponsors this conference to provide a forum for energy executives, engineers, etc. to discuss advances in fuel cell research and development projects, to exchange ideas with private sector attendees, and to review relevant results in fuel cell technology programs. Two hundred and three people from industry, academia, and Government attended. The conference attempts to showcase the partnerships with the Government and with industry, by seeking activity participation and involvement from the Office of Energy Efficiency and Renewable Energy, EPRI, GRI, and APRA. In addition to sessions on fuel cells (solid oxide, molten carbonate, etc.) for stationary electric power generation, sessions on US DOE's Fuel Cell Transportation Program and on DOD/APRA's fuel cell logistic fuel program were presented. In addition to the 29 technical papers, an abstract of an overview of international fuel cell development and commercialization plans in Europe and Japan is included. Selected papers were indexed separately for inclusion in the Energy Science and Technology Database.

Proceedings of the fuel cells `94 contractors review meeting

Energy Technology Data Exchange (ETDEWEB)

Carpenter, C.P. II; Mayfield, M.J. [eds.] [USDOE Morgantown Energy Technology Center, WV (United States)

1994-08-01

METC annually sponsors this conference to provide a forum for energy executives, engineers, etc. to discuss advances in fuel cell research and development projects, to exchange ideas with private sector attendees, and to review relevant results in fuel cell technology programs. Two hundred and three people from industry, academia, and Government attended. The conference attempts to showcase the partnerships with the Government and with industry, by seeking activity participation and involvement from the Office of Energy Efficiency and Renewable Energy, EPRI, GRI, and APRA. In addition to sessions on fuel cells (solid oxide, molten carbonate, etc.) for stationary electric power generation, sessions on US DOE`s Fuel Cell Transporation Program and on DOD/APRA`s fuel cell logistic fuel program were presented. In addition to the 29 technical papers, an abstract of an overview of international fuel cell development and commercialization plans in Europe and Japan is included. Selected papers were indexed separately for inclusion in the Energy Science and Technology Database.

Proceedings of the 1993 Windsor Workshop on Alternative Fuels

Energy Technology Data Exchange (ETDEWEB)

1993-10-01

This report contains viewgraph papers on the following topics on alternative fuels: availability of alternative fueled engines and vehicles; emerging technologies; overcoming barriers to alternative fuels commercialization; infrastructure issues; and new initiatives in research and development.

Proceedings of the 2006 International Meeting on LWR fuel performance 'Nuclear Fuel: Addressing the future' - TopFuel 2006 Transactions

International Nuclear Information System (INIS)

2006-01-01

From 22-26 October, 340 researchers, nuclear engineers and scientists from across Europe and beyond congregated in the ancient university city of Salamanca, Spain, to discuss the challenges facing the developers and manufacturers of new high-performance nuclear fuels-fuels that will help meet current and future energy demand and reduce man's over dependence upon CO 2 -emitting fossil fuels. TopFuel is an annual topical meeting organised by ENS, the American Nuclear Society and the Atomic Energy Society of Japan. This year it was co-sponsored by the IAEA, the OECD/NEA and the Spanish Nuclear Society (SNE). TopFuel's primary objective was to bring together leading specialists in the field from around the world to analyse advances in nuclear fuel management technology and to use the findings of the latest cutting-edge research to help manufacture the high performance nuclear fuels of today and tomorrow. The TopFuel 2006 agenda revolved around ten technical sessions dedicated to priority issues such as security of supply, new fuel and reactor core designs, fuel cycle strategies and spent fuel management. Among the many topics under discussion were new developments in fuel performance modelling, advanced fuel assembly design and the improved conditioning and processing of spent fuel. During the week, a poster exhibition also gave delegates the opportunity to display and discuss the results of their latest work and to network with fellow professionals. One important statement to emerge from TopFuel 2006 was that the world has enough reserves of uranium to support the large-scale and long-term production of nuclear energy. The OECD/NEA and the IAEA recently published a report entitled Uranium 2005: Resources, Production and Demand (the Red Book). The report, which makes a comprehensive assessment of uranium supplies and projected demand up until the year 2025, concludes by saying 'the uranium resource base is adequate to meet projected future requirements'. With the

Use of regenerative energy sources and hydrogen technology 2014. Proceedings

International Nuclear Information System (INIS)

Luschtinetz, Thomas; Lehmann, Jochen

2014-01-01

This proceedings contains 38 papers with the following main topics: wind and hydrogen technology, developments in the use of bioenergy, fuel cells, photovoltaics. Two contributions were recorded separately for this database. [de

Proceedings of the 1996 Windsor workshop on alternative fuels

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-10-01

This document contains information which was presented at the 1996 Windsor Workshop on Alternative Fuels. Topics include: international links; industry topics and infrastructure issues; propane; engine developments; the cleanliness of alternative fuels; heavy duty alternative fuel engines; California zev commercialization efforts; and in-use experience.

Eighteenth symposium on biotechnology for fuels and chemicals: Program and abstracts

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-31

This volume provides the proceedings for the Eighteenth Symposium on Biotechnology for Fuels and Chemicals held May 5-9, 1996 in Gatlinburg, Tennessee. The proceedings contains abstracts for oral and poster presentations.

Proceedings of the 6th Korea-China Joint workshop on nuclear waste management

International Nuclear Information System (INIS)

2005-11-01

This proceedings contains articles of 6th Korea-China Joint workshop on nuclear waste management. It was held on November 16-17, 2005 in Kyeongju, Korea. This proceedings is comprised of 3 sessions. The main subject titles of session are as follows: Nuclear fuel cycle, Radioactive waste treatment, Radwaste disposal and decontamination and decommissioning. (Yi, J. H.)

Proceedings of the 13. annual conference of the Canadian Nuclear Society. V. 1

Energy Technology Data Exchange (ETDEWEB)

1993-12-31

Volume 1 of the proceedings of the 13. annual conference of the Canadian Nuclear Society includes sessions on the following topics: reactor physics, new concepts and technology, fuel behaviour, reactor design, safety analysis, fuel channel behaviour, equipment and design qualification. The individual papers have been abstracted separately.

Advances in applications of burnup credit to enhance spent fuel transportation, storage, reprocessing and disposition. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2007-05-01

Given a trend towards higher burnup power reactor fuel, the IAEA began an active programme in burnup credit (BUC) with major meetings in 1997 (IAEA-TECDOC-1013), 2000 (IAEA-TECDOC-1241) and 2002 (IAEA-TECDOC-1378) exploring worldwide interest in using BUC in spent fuel management systems. This publication contains the proceedings of the IAEA's 4th major BUC meeting, held in London. Sixty participants from 18 countries addressed calculation methodology, validation and criticality, safety criteria, procedural compliance with safety criteria, benefits of BUC applications, and regulatory aspects in BUC. This meeting encouraged the IAEA to continue its activities on burnup credit including dissemination of related information, given the number of Member States having to deal with increased spent fuel quantities and extended durations. A 5th major meeting on burnup credit is planned 2008. Burnup credit is a concept that takes credit for the reduced reactivity of fuel discharged from the reactor to improve loading density of irradiated fuel assemblies in storage, transportation, and disposal applications, relative to the assumption of fresh fuel nuclide inventories in loading calculations. This report has described a general four phase approach to be considered in burnup credit implementation. Much if not all of the background research and data acquisition necessary for successful burnup credit development in preparation for licensing has been completed. Many fuel types, facilities, and analysis methods are encompassed in the public knowledge base, such that in many cases this guidance will provide a means for rapid development of a burnup credit program. For newer assembly designs, higher enrichment fuels, and more extensive nuclide credit, additional research and development may be necessary, but even this work can build on the foundation that has been established to date. Those, it is hoped that this report will serve as a starting point with sufficient reference to

Proceedings of the international symposium NUCEF 2005

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-08-01

Japan Atomic Energy Research Institute (JAERI) held the international symposium NUCEF 2005 at Techno Community Square RICOTTI in Tokai-mura on February 9 and 10, 2005. This symposium was co-organized by Japan Nuclear Cycle Development Institute (JNC), and Nuclear Fuel Cycle Safety Research Committee authorized the program. Two hundred thirty-nine participants from 11 countries presented fifty-nine papers, and discussed recent research activities and its outputs on waste disposal safety, fuel cycle facility safety including criticality safety, and separation process development. The presented papers are compiled in the proceedings. (author)

Proceedings of the 32. annual conference of the Canadian Nuclear Association

International Nuclear Information System (INIS)

1992-01-01

The conference proceedings comprise 34 papers, arranged under the following sessions: Plenary; The international CANDU program; Canadian used fuel management program; Public information advocates; Fuel and electricity supply; In which direction should reactors advance?; Canadian advanced nuclear research programs; International cooperation in operations; Safety in design, operation, regulation; Renovation of operating stations; CNS/CNA luncheon addresses. The individual papers have been abstracted separately

Fuels Management-How to Measure Success: Conference Proceedings

Science.gov (United States)

Patricia L. Andrews; Bret W. Butler

2006-01-01

Fuels management programs are designed to reduce risks to communities and to improve and maintain ecosystem health. The International Association of Wildland Fire initiated the 1st Fire Behavior and Fuels Conference to address development, implementation, and evaluation of these programs. The focus was on how to measure success. Over 500 participants from several...

Krakow conference on low emissions sources: Proceedings

Energy Technology Data Exchange (ETDEWEB)

Pierce, B.L.; Butcher, T.A. [eds.

1995-12-31

The Krakow Conference on Low Emission Sources presented the information produced and analytical tools developed in the first phase of the Krakow Clean Fossil Fuels and Energy Efficiency Program. This phase included: field testing to provide quantitative data on missions and efficiencies as well as on opportunities for building energy conservation; engineering analysis to determine the costs of implementing pollution control; and incentives analysis to identify actions required to create a market for equipment, fuels, and services needed to reduce pollution. Collectively, these Proceedings contain reports that summarize the above phase one information, present the status of energy system management in Krakow, provide information on financing pollution control projects in Krakow and elsewhere, and highlight the capabilities and technologies of Polish and American companies that are working to reduce pollution from low emission sources. It is intended that the US reader will find in these Proceedings useful results and plans for control of pollution from low emission sources that are representative of heating systems in central and Eastern Europe. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

Proceedings of the 11th Annual Conference of the Canadian Nuclear Society

International Nuclear Information System (INIS)

Rouben, B.

1990-01-01

This volume contains the proceedings of the thirteen technical sessions at the 11. annual conference of the Canadian Nuclear Society. The 68 papers presented at this conference cover the areas of programmes and issues for the 90's; thermalhydraulics; reactor physics and fuel management; nuclear safety; small reactors; fuel behaviour; energy production and the environment; computer applications; nuclear systems; fusion; reactor decommissioning, irradiated fuel and materials handling; and reactor components, (L.L.)

Proceedings of the fifth International Slovak Biomass Forum (ISBF)

International Nuclear Information System (INIS)

2005-02-01

The publication has been set up as a proceedings of the conference dealing with use of biomass for energy production. The main conference topics are focused on the following scopes: Session 1: RES Policies, strategies, political background; Session 2: Bioenergy markets, tools and influence factors; Session 3: Biomass fuels production and trading; Parallel Session 4: Biomass firing technologies; Parallel Session 5: Municipal projects uptake; Parallel Session 6: Biomass large and small CHP; Parallel Session 7: Environmental biomass technologies; Session 8: Biomass projects financing roundtable; In this proceedings 54 contributions is included

Proceedings of the Canadian Nuclear Society 12. annual conference

International Nuclear Information System (INIS)

1991-01-01

This volume contains the Proceedings of the seventeen Technical Sessions from the Twelfth Annual Conference of the Canadian Nuclear Society held in Saskatoon, Saskatchewan, June 9 to 12, 1991. As in previous years, the Annual Conference of the Canadian Nuclear Society was held in conjunction with the Annual Conference of the Canadian Nuclear Association. The major topics of discussion included: reactor physics; thermal hydraulics; industrial irradiation; computer applications; fuel channel analysis; small reactors; severe accidents; fuel behaviour under accident conditions; reactor components; safety related computer software; nuclear fuel management; nuclear waste management; and, uranium mining processing

Proceedings of the 10. Meeting on Reactor Physics and Thermal Hydraulics

International Nuclear Information System (INIS)

Santos Bastos, W. dos

1995-01-01

These proceedings presents all the Meeting papers emphasizing specific aspects on reactor physics method, criticality, fuel management, nuclear data, safety analysis, simulation and shielding, neutronics, thermal hydraulics, reactor operation and computational methods

Wood fuel and the environment

International Nuclear Information System (INIS)

Foster, C.A.

1992-01-01

The purpose of this paper is to try and demonstrate the role that the use of Wood as a Fuel can play in our environment. The term ''Wood Fuel'', for the purposes of these proceedings, refers to the use of wood obtained from the forest or the farm. It does not refer to waste wood from for example buildings. The role of wood fuel in the environment can be assessed at many different levels. In this paper three different scales of ''Environment'' and the role of wood fuel in each, will be considered. These three scales are namely the global environment, the local environment, and the National (community) environment. (Author)

Proceedings of the 1999 Review Conference on Fuel Cell Technology

Energy Technology Data Exchange (ETDEWEB)

None Available

2000-06-05

The 1999 Review Conference on Fuel Cell Technology was jointly sponsored by the U.S. Department of Energy, Federal Energy Technology Center (FETC), the Gas Research Institute (GRI), and the Electric Power Research Institute (EPRI). It was held August 3 to 5 in Chicago, Illinois. The goal of this conference was to provide a forum for reviewing fuel cell research and development (R&D) programs, assist in strategic R&D planning, promote awareness of sponsor activities, and enhance interactions between manufacturers, researchers, and stakeholders. This conference was attended by over 250 representatives from industry, academia, national laboratories, gas and electric utilities, DOE, and other Government agencies. The conference agenda included a keynote session, five presentation sessions, a poster presentation reception, and three breakout sessions. The presentation session topics were DOD Fuel Cell Applications, Low-Temperature Fuel Cell Manufacturers, Low-Temperature Component Research, High-Temperature Fuel Cell Manufacturers, and High-Temperature Component Research; the breakout session topics were Future R&D Directions for Low-Temperature Fuel Cells, Future R&D Directions for High-Temperature Fuel Cells, and a plenary summary session. All sessions were well attended.

Proceedings of the fuels technology contractors review meeting

Energy Technology Data Exchange (ETDEWEB)

Malone, R.D. [ed.

1993-11-01

The Fuels Technology Contractors Review Meeting was held November 16-18, 1993, at the Morgantown Energy Technology Center (METC) in Morgantown, West Virginia. This meeting was sponsored and hosted by METC, the Office of Fossil Energy, U.S. Department of Energy (DOE). METC periodically provides an opportunity to bring together all of the R&D participants in a DOE-sponsored contractors review meeting to present key results of their research and to provide technology transfer to the active research community and to the interested public. This meeting was previously called the Natural Gas Technology Contractors Review Meeting. This year it was expanded to include DOE-sponsored research on oil shale and tar sands and so was retitled the Fuels Technology Contractors Review Meeting. Current research activities include efforts in both natural gas and liquid fuels. The natural gas portion of the meeting included discussions of results summarizing work being conducted in fracture systems, both natural and induced; drilling, completion, and stimulation research; resource characterization; delivery and storage; gas to liquids research; and environmental issues. The meeting also included project and technology summaries on research in oil shale, tar sands, and mild coal gasification, and summaries of work in natural-gas fuel cells and natural-gas turbines. The format included oral and poster session presentations. Individual papers have been processed separately for inclusion in the Energy Science and Technology database.

Metallic fuel development

International Nuclear Information System (INIS)

Walters, L.C.

1987-01-01

Metallic fuels are capable of achieving high burnup as a result of design modifications instituted in the late 1960's. The gap between the fuel slug and the cladding is fixed such that by the time the fuel swells to the cladding the fission gas bubbles interconnect and release the fission gas to an appropriately sized plenum volume. Interconnected porosity thus provides room for the fuel to deform from further swelling rather than stress the cladding. In addition, the interconnected porosity allows the fuel pin to be tolerant to transient events because as stresses are generated during a transient event the fuel flows rather than applying significant stress to the cladding. Until 1969 a number of metallic fuel alloys were under development in the US. At that time the metallic fuel development program in the US was discontinued in favor of ceramic fuels. However, development had proceeded to the point where it was clear that the zirconium addition to uranium-plutonium fuel would yield a ternary fuel with an adequately high solidus temperature and good compatibility with austenitic stainless steel cladding. Furthermore, several U-Pu-Zr fuel pins had achieved about 6 at.% bu by the late 1960's, without failure, and thus the prospect for high burnup was promising

Proceedings of the 38th international instrumentation symposium

International Nuclear Information System (INIS)

Richter, S.H.; Smith, E.A.

1991-01-01

This volume covers the proceedings of a symposium on instrumentation within the Aerospace and Test Measurement Divisions of the Instrument Society of America. Topics covered included: PC control in turbine engine testing, energy measurement of high proton beams, instrumentation for sampling related to the US clean Air Act, and instrumentation for monitoring in-reactor severe fuel damage tests

Proceedings of the 2008 transportation technologies and fuels forum

International Nuclear Information System (INIS)

2008-01-01

As a large emitter of pollutants, the transportation industry is now seeking to develop a sustainable transportation plan for the future by developing methods of reducing emissions and improving the fuel efficiency of vehicles. This forum discussed recent innovations in vehicle transportation technologies. Industry leaders, government representatives, and researchers discussed methods of reducing greenhouse gases (GHGs) and air pollution in the transportation sector. Advanced combustion technologies were outlined, and recent developments in hybrid electric-powered vehicles were discussed. Research related to fuel cells, hydrogen fuels and biofuels was presented. The impacts of polluting vehicles on public health were also discussed. The forum was divided into the following 5 sessions: (1) setting the scene, (2) future fuels, (3) emissions, (4) EVs now, and (5) the road to the future. The sessions were followed by a panel on technology roadmaps. The forum featured 14 presentations, of which 4 have been catalogued separately for inclusion in this database. tabs., figs.

8. annual U.S. hydrogen meeting: Proceedings

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-01-01

The proceedings contain 35 papers arranged under the following topical sections: Government`s partnership role for hydrogen technology development; Government/industry partnerships -- Demonstrations; Entering the market -- Partnerships in transportation; Hydrogen -- The aerospace fuel; Codes and Standards; Advanced technologies; and Opportunities for partnerships in the utility market. Of the three markets identified (transportation, power production, and village power) papers are presented dealing with the first two. Three parts of the transportation market were covered: cars, trucks, and buses. Progress was reported in both fuel cell and internal combustion engine vehicle propulsion systems. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

Proceedings of the fifth international conference on CANDU fuel. V.1,2

International Nuclear Information System (INIS)

Lau, J.H.

1997-01-01

The First International Conference on CANDU Fuel was held in Chalk River in 1986. The CANDU Fuel community has gathered every three years since. The papers presented include topics on international experience, CANFLEX fuel bundles, Fuel design, Fuel modelling, Manufacturing and Quality assurance, Fuel performance and Safety, Fuel cycles and Spent Fuel management. Volume One was published in advance of the conference and Volume Two was printed after the conference

Proceedings of the fifth international conference on CANDU fuel. V.1,2

Energy Technology Data Exchange (ETDEWEB)

Lau, J H [ed.

1997-07-01

The First International Conference on CANDU Fuel was held in Chalk River in 1986. The CANDU Fuel community has gathered every three years since. The papers presented include topics on international experience, CANFLEX fuel bundles, Fuel design, Fuel modelling, Manufacturing and Quality assurance, Fuel performance and Safety, Fuel cycles and Spent Fuel management. Volume One was published in advance of the conference and Volume Two was printed after the conference.

Proceedings of the 24th KAIF/KNS Annual Conference

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-04-15

This proceedings contains articles of the 24th KAIF/KNS Annual Conference of the KAIF and Korean Nuclear Society. It was held on Apr. 8-10, 2009 in Seoul, Korea and subject of 24th Conference is the role of nuclear energy: Green enertopia with nuclear. This proceedings is comprised of 8 sessions. The main topic titles of session are as follows: Operation and maintenance of nuclear power plants, Betterment of nuclear power utilization, Enhanced future application of nuclear science and technology, Radioactive waste management, RI production and its utilization, Design, engineering, manufacturing, and construction of NPP in Korea, Nuclear fuel cycle, Nuclear safety and regulation. (Yi, J. H.)

Fuel Cell Seminar, 1992: Program and abstracts

Energy Technology Data Exchange (ETDEWEB)

1992-12-31

This year`s theme, ``Fuel Cells: Realizing the Potential,`` focuses on progress being made toward commercial manufacture and use of fuel cell products. Fuel cell power plants are competing for market share in some applications and demonstrations of market entry power plants are proceeding for additional applications. Development activity on fuel cells for transportation is also increasing; fuel cell products have potential in energy and transportation industries, with very favorable environmental impacts. This Seminar has the purpose of fostering communication by providing a forum for the international community interested in development, application, and business opportunities related fuel cells. Over 190 technical papers are included, the majority being processed for the data base.

CNS proceedings of the 16. annual conference, volume I and II

Energy Technology Data Exchange (ETDEWEB)

Wight, A L; Loewer, R [eds.

1996-12-31

The proceedings of the 16. annual conference of the Canadian Nuclear Society cover a wide range of nuclear topics, but the emphasis is on CANDU reactors and Canadian experience. The 82 papers are arranged in 16 sessions dealing with the following subjects: thermalhydraulics, containment, control and instrumentation, reactor physics, fuel channels, engineering and maintenance, safety and licensing, severe accidents and probabilistic safety assessment, new reactors and applications, radiation, fuel, computers. The individual papers have been abstracted separately.

CNS proceedings of the 16. annual conference, volume I and II

International Nuclear Information System (INIS)

Wight, A.L.; Loewer, R.

1995-01-01

The proceedings of the 16. annual conference of the Canadian Nuclear Society cover a wide range of nuclear topics, but the emphasis is on CANDU reactors and Canadian experience. The 82 papers are arranged in 16 sessions dealing with the following subjects: thermalhydraulics, containment, control and instrumentation, reactor physics, fuel channels, engineering and maintenance, safety and licensing, severe accidents and probabilistic safety assessment, new reactors and applications, radiation, fuel, computers. The individual papers have been abstracted separately

Proceedings of the 1. General Congress of Nuclear Energy. v. 2

International Nuclear Information System (INIS)

1986-01-01

The proceedings of I General Congress of Nuclear Energy are presented. All fields related to nuclear energy are enclosed. In the second part the following fields are shown: reactor instrumentation and control, nuclear medicine, radioisotopes uses, fuel cycle and radiation protection. (M.C.K.) [pt

Water channel reactor fuels and fuel channels: Design, performance, research and development. Proceedings of a technical committee meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-01-01

The International Working Group on Water Reactor Fuel Performance and Technology (IWGFPT) recommended holding a Technical Committee Meeting on Water Channel Reactor Fuel including into this category fuels and pressure tubes/fuel channels for Atucha-I and II, BWR, CANDU, FUGEN and RBMK reactors. The IWGFPT considered that even if the characteristics of Atucha, CANDUs, BWRs, FUGEN and RBMKs differ considerably, there are also common features. These features include materials aspects, as well as core, fuel assembly and fuel rod design, and some safety issues. There is also some similarity in fuel power history and operating conditions (Atucha-I and II, FUGEN and RBMK). Experts from 11 countries participated at the meeting and presented papers on technology, performance, safety and design, and materials aspects of fuels and pressure tubes/fuel channels for the above types of water channel reactors. Refs, figs, tabs.

Water channel reactor fuels and fuel channels: Design, performance, research and development. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

1998-01-01

The International Working Group on Water Reactor Fuel Performance and Technology (IWGFPT) recommended holding a Technical Committee Meeting on Water Channel Reactor Fuel including into this category fuels and pressure tubes/fuel channels for Atucha-I and II, BWR, CANDU, FUGEN and RBMK reactors. The IWGFPT considered that even if the characteristics of Atucha, CANDUs, BWRs, FUGEN and RBMKs differ considerably, there are also common features. These features include materials aspects, as well as core, fuel assembly and fuel rod design, and some safety issues. There is also some similarity in fuel power history and operating conditions (Atucha-I and II, FUGEN and RBMK). Experts from 11 countries participated at the meeting and presented papers on technology, performance, safety and design, and materials aspects of fuels and pressure tubes/fuel channels for the above types of water channel reactors

Proceedings of the 24th NSRR technical review meeting

Energy Technology Data Exchange (ETDEWEB)

Uetsuka, Hiroshi; Fuketa, Toyoshi; Suzuki, Motoe [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

2001-09-01

The 24th NSRR Technical Review Meeting was held at Tranomon Pastoral, Tokyo, on November 13 and 14, 2000. The purpose of the meeting was to present and discuss the recent progress of the NSRR program and other LWR fuel safety researches at JAERI. Twenty-one papers, including five by foreign institutes, were presented and discussed regarding fuel behavior during normal operation, reactivity initiated accident (RIA) and loss-of-coolant accident (LOCA) and FP release behavior during severe accident. The meeting was a great help in planning future research and promoting research cooperation. This proceeding contains the papers presented in the meeting. (author)

Effects of the preparation process on the quality of refuse-derived fuels: The example of chlorine; Einfluss der Aufbereitung auf die Qualitaet der Ersatzbrennstoffe am Beispiel von Chlor

Energy Technology Data Exchange (ETDEWEB)

Kost, T.; Roetter, S.; Bilitewski, B. [Technische Univ. Dresden (Germany)

2000-07-01

The different interest groups (environmental authorities, licensing authorities, producers and users of refuse-derived fuels) have different guidelines, proposals and product specifications for quality assurance. While the limiting values for heavy metals reflect the controversial positions of the parties concerned, limiting values for chlorine are generally set at less than 1 percent by weight. This is not an ecological consideration but derives from the technical aspects of safe operation in the industries concerned. [German] Fuer die Guetesicherung von Ersatzbrennstoffen liegen von den beteiligten Interessengruppen (Umweltaemter, Genehmigungsbehoerden, Hersteller und Anwender von Ersatzbrennstoffen) verschiedene Grenzwerte als Richtlinien, Vorschlaege und Produktspezifikationen vor. Waehrend die Werte fuer Schwermetalle die teilweise kontraere Positionen der Beteiligten widerspiegeln, besteht fuer den Parameter Chlor dagegen eine einheitliche Spezifikation von <1 Gew.-% (wf). Dieser Wert ergibt sich nicht in erster Linie aus oekologischen Anforderungen, sondern ist vielmehr an technischen Aspekten der Betriebssicherheit beim Einsatz in den Anwenderindustrien orientiert. (orig.)

Increased Accident Tolerance of Fuels for Light Water Reactors - Workshop Proceedings, OECD/NEA Headquarters, Issy-les-Moulineaux, France, 10-12 December 2012

International Nuclear Information System (INIS)

2013-01-01

The Fukushima accident in March 2011 raised concerns about the safety of current and future nuclear power plants both inside and outside the international nuclear energy community. With a view to learning lessons from this accident a large consensus emerged on the need to strengthen each level of Defence-In-Depth, reinforcing both prevention and mitigation. The fuel performance characteristics identified as being central to increased accident tolerance for long-term loss of coolant include reduced clad-steam reactions, reduced hydrogen production and improved fission product retention. New fuel designs which offered the potential to incorporate these characteristics, while retaining the operational performance of existing designs, would therefore be considered as suitable candidates for further investigation. Under the auspices of the NEA Nuclear Science Committee, a workshop has been organised to bring together international experts from the modelling, safety, operations and regulatory technical disciplines to discuss the various issues related to increased accident tolerance of fuels for Light Water Reactors and to help establish a co-ordinated international approach in this field. The organisation of this workshop was also supported by the NEA Committee on the Safety of Nuclear Installations. These proceedings include all the abstract papers presented at this workshop. The programme was comprised of 4 sessions: - Session 1: Lessons learned from the Fukushima accident; - Session 2: Accident-tolerant fuel design; - Session 3: Reactor operation, safety, fuel cycle constraints, economics and licensing; - Session 4: Synthesis and future programmes. A total of 55 participants from 16 countries attended the workshop, with 26 technical presentations and 2 breakout parallel sessions (one on safety issues, the other on reactor performance, R and D and technological issues). The attendees represented a broad spectrum of stakeholders involved in different nuclear energy

MOX fuel cycle technologies for medium and long term deployment. Proceedings

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

More than thirty years of reactor experience using MOX fuel as well as the fabrication of 2000 MOX assemblies with the use of 85 t of Pu separated from spent fuel from power reactors indicates that the recycling of plutonium as MOX fuel in LWRs has become a mature industry. The number of countries engaged in plutonium recycling could be increasing in the near future, aiming for the reduction of stockpiles of separated plutonium from earlier and existing reprocessing contracts. Economic and strategic considerations are the main factors on which to base such a decision to use MOX. Transport of MOX fuel assemblies is a vital element in these recycle programmes but could have the potential to be a weak link in the chain. To avoid problems, it is essential that sufficient numbers of transport flasks of the required types, licensed for the increasing Pu contents, be made available in a timely manner to keep pace with the planned increases in fabrication rates. Despite the excellent safety records for radioactive and MOX transports over many decades, continuous attention should be drawn to establishing the transport modalities, buffer stores, secure vehicles, and transport routes, at the same time accounting for public sensitivities on radioactive transports in general and MOX transport in particular. A large number of technical presentations updated and reconfirmed the good and almost defect-free performance of MOX fuel at increasingly high burn-up levels. MOX fuel is designed to meet the same operational and safety criteria as uranium fuels under equivalent conditions. This is also confirmed by the parallel development of design codes to accommodate the special characteristics of MOX. Integral and specific parameter testing of MOX fuel in normal and off-normal operation is under way in a number of countries with particular emphasis on high burnup behaviour. Here the important contributions of the OECD/NEA Halden BWR programme should be mentioned. The reactor

MOX fuel cycle technologies for medium and long term deployment. Proceedings

International Nuclear Information System (INIS)

2000-01-01

More than thirty years of reactor experience using MOX fuel as well as the fabrication of 2000 MOX assemblies with the use of 85 t of Pu separated from spent fuel from power reactors indicates that the recycling of plutonium as MOX fuel in LWRs has become a mature industry. The number of countries engaged in plutonium recycling could be increasing in the near future, aiming for the reduction of stockpiles of separated plutonium from earlier and existing reprocessing contracts. Economic and strategic considerations are the main factors on which to base such a decision to use MOX. Transport of MOX fuel assemblies is a vital element in these recycle programmes but could have the potential to be a weak link in the chain. To avoid problems, it is essential that sufficient numbers of transport flasks of the required types, licensed for the increasing Pu contents, be made available in a timely manner to keep pace with the planned increases in fabrication rates. Despite the excellent safety records for radioactive and MOX transports over many decades, continuous attention should be drawn to establishing the transport modalities, buffer stores, secure vehicles, and transport routes, at the same time accounting for public sensitivities on radioactive transports in general and MOX transport in particular. A large number of technical presentations updated and reconfirmed the good and almost defect-free performance of MOX fuel at increasingly high burn-up levels. MOX fuel is designed to meet the same operational and safety criteria as uranium fuels under equivalent conditions. This is also confirmed by the parallel development of design codes to accommodate the special characteristics of MOX. Integral and specific parameter testing of MOX fuel in normal and off-normal operation is under way in a number of countries with particular emphasis on high burnup behaviour. Here the important contributions of the OECD/NEA Halden BWR programme should be mentioned. The reactor

Storage of spent fuel from power reactors. Proceedings of a symposium

International Nuclear Information System (INIS)

1999-07-01

The symposium gave an opportunity to exchange information on the state of the art and prospects of spent fuel storage, to discuss the worldwide situation and the major factors influencing the national policies in this field and to identify the most important directions that national efforts an international cooperation in this area should take. Dominant message retrieved from the symposium are that the primary spent fuel management solution for the next decades will be interim storage, the duration of time of interim storage becomes longer than earlier anticipated and the storage facilities will have to be designed for receiving also spent fuel from advanced fuel cycle practices (i.e. high burnup and MOX spent fuel). It was noted that the handling and storage of spent fuel is a mature technology and meets the stringent safety requirements applicable in different countries. The changes in nuclear policy and philosophy across the world, and practical considerations, have made interim storage a real necessity in the nuclear power industry. This is being addressed adequately by utilities, vendors and regulators alike

Storage of spent fuel from power reactors. Proceedings of a symposium

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

The symposium gave an opportunity to exchange information on the state of the art and prospects of spent fuel storage, to discuss the worldwide situation and the major factors influencing the national policies in this field and to identify the most important directions that national efforts an international cooperation in this area should take. Dominant message retrieved from the symposium are that the primary spent fuel management solution for the next decades will be interim storage, the duration of time of interim storage becomes longer than earlier anticipated and the storage facilities will have to be designed for receiving also spent fuel from advanced fuel cycle practices (i.e. high burnup and MOX spent fuel). It was noted that the handling and storage of spent fuel is a mature technology and meets the stringent safety requirements applicable in different countries. The changes in nuclear policy and philosophy across the world, and practical considerations, have made interim storage a real necessity in the nuclear power industry. This is being addressed adequately by utilities, vendors and regulators alike Refs, figs, tabs

Proceedings of the international symposium on alcohol fuel technology: methanol and ethanol

Energy Technology Data Exchange (ETDEWEB)

None

1978-07-01

The papers presented dealt with the following topics: international situation and economic and political aspects, use of alcohol fuels as automotive fuels, production of methanol and methyl fuels, production of ethanol, methanol application and modeling, alcohol fuel optimization, and environmental considerations. Each paper was prepared for introduction into the EDB data base. (JSR)

The proceedings of China-Japan workshop on nuclear waste management and reprocessing

International Nuclear Information System (INIS)

2000-01-01

China-Japan workshop on Nuclear Waste Management and Reprocessing held by sponsors, Nuclear Chemical Engineering Association, Chinese nuclear Society and Division of nuclear Fuel Cycle and Environment, Atomic Energy Society of Japan and by co-sponsor, Nuclear and Radiochemistry Association, Chinese Nuclear Society, on April 5-7, 2000, in Beijing, China. The proceedings is published. It collected 34 articles. The contents include nuclear fuel reprocessing, radioactive waste processing and radioactive waste disposal, partitioning and transmutation, radionuclide migration, sorption and diffusion and actinide chemistry

Remote technology in spent fuel management. Proceedings of an advisory group meeting

International Nuclear Information System (INIS)

1999-01-01

Spent fuel management has always been one of the important stages in the nuclear fuel cycle and it is still one of the most vital problems common to all countries with nuclear reactors. It begins with the discharge of spent fuel from a power or research reactor and ends with its ultimate disposition either by direct disposal or by reprocessing of the spent fuel. Continuous attention is being given by the IAEA to the collection, analysis and exchange of information on spent fuel management. Its role in this area is to provide a forum for exchanging information and development activities that are of common interest. Within its spent fuel management programme, the IAEA has monitored the progress, the benefits and the implementation of remote technologies such as remote tools, robotics, etc. An Advisory Group Meeting on Remote Technology in Spent Fuel Management was held in September 1997 in order to bring together specialists working in this field and to collect information on new technical and economic developments. The objective of the Advisory Group meeting was to review remote technologies in use for the complete range of spent fuel handling and spent fuel management covering wet and dry environments, to describe ongoing developments and to prepare a technical report. This document contains contributions presented at the Meeting. Each paper was indexed and provided with an abstract

The environmental impacts of the nuclear fuel cycle

International Nuclear Information System (INIS)

Hamard, J.

1975-01-01

A survey about the environmental pollution and the population exposure caused by the nuclear fuel cycle is set up. Proceeding from the environmental changes caused by the construction of plants, the author shows the hazards of the operation of the plants. The fuel cycle beginning with the mining of nuclear fuels and reaching to their reprocessing, the environmental pollution by radionuclides and the population exposure resulting from this are outlined. After indicating the advantages of the concentration of nuclear plants, the author shows comparatively the hazards caused by conventional energy sources. (ORU) [de

Plant-scale anodic dissolution of unirradiated N-Reactor fuel

International Nuclear Information System (INIS)

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

1995-01-01

Anodic dissolution tests were made with unirradiated N-Reactor fuel to determine the fuel segment length, diameter, and shape required for high throughput electrorefiner treatment for ultimate disposal in a geologic repository. Based on these tests, a conceptual design was produced of an electrorefiner for a full-scale plant to process N-Reactor spent fuel. In this design, the diameter of an electrode assembly is about 0.6 m (25 in.). Eight of these assemblies in an electrorefiner would accommodate a 1.333-metric-ton batch of N-Reactor fuel. Electrorefining would proceed at a rate of 40 kg uranium per hour

Main conditions and effectiveness of gas fuel use for powering of dual fuel IC self-ignition engine

Directory of Open Access Journals (Sweden)

Stefan POSTRZEDNIK

2015-09-01

Full Text Available Internal combustion engines are fuelled mostly with liquid fuels (gasoline, diesel. Nowadays the gaseous fuels are applied as driving fuel of combustion engines. In case of spark ignition engines the liquid fuel (petrol can be totally replaced by the gas fuels. This possibility in case of compression engines is essentially restricted through the higher self-ignition temperatures of the combustible gases in comparison to classical diesel oil. Solution if this problem can be achieved by using of the dual fuel system, where for ignition of the prepared fuel gas - air mixture a specified amount of the liquid fuel (diesel oil should be additionally injected into the combustion chamber. For assurance that the combustion process proceeds without mistakes and completely, some basic conditions should be satisfied. In the frame of this work, three main aspects of this problem are taken into account: a. filling efficiency of the engine, b. stoichiometry of the combustion, c. performance of mechanical parameters (torque, power. A complex analysis of these conditions has been done and some achieved important results are presented in the paper.

Influence of the fuel operational parameters on the aluminium cladding quality of discharged fuel

Energy Technology Data Exchange (ETDEWEB)

Chwaszczewski, S.; Czajkowski, W.; Borek-Kruszewska, E. [Institute of Atomic Energy, Otwock Swierk (POLAND)

2002-07-01

In the last two years, the new MR6 type fuel containing 1550 g of U with 36% enrichment has been loaded into MARIA reactor core. Its aluminium cladding thickness is 0,6 mm and typical burnup -about 4080 MWh (as compared to 2880 MWh for the 80% enriched fuel used). However, increased fission product release from these assemblies was observed near the end of its operational time. The results presented earlier [1] show that the corrosion behaviour of aluminium cladding depends on the conditions of fuel operation in the reactor. The corrosion process in the aluminum of fuel cladding proceeds faster then in the aluminum of constructional elements. This tendency was also observed in MR-6/80% and in WWR- SM fuel assemblies. Therefore the visual tests of discharged MR-6/36% fuel elements were performed. Some change of appearance of aluminum cladding was observed, especially in the regions with large energy generation i.e. in the centre of reactor core and in the strong horizontal gradient of neutron flux. In the present paper, the results of visual investigation of discharged fuel assemblies are presented. The results of the investigation are correlated with the operational parameters. (author)

FAST FLUX TEST FACILITY DRIVER FUEL MEETING

Energy Technology Data Exchange (ETDEWEB)

None,

1966-06-01

The Pacific Northwest Laboratory has convened this meeting to enlist the best talents of our laboratories and industry in soliciting factual, technical information pertinent to the Pacific Northwest's Laboratory's evaluation of the potential fuel systems for the Fast Flux Test Facility. The particular factors emphasized for these fuel systems are those associated with safety, ability to meet testing objectives, and economics. The proceedings includes twenty-three presentations, along with a transcript of the discussion following each, as well as a summary discussion.

Future technology fuel cells; Zukunftstechnologie Brennstoffzelle. Themen 1999/2000

Energy Technology Data Exchange (ETDEWEB)

Hertlein, H.P. (comp.)

2000-02-01

The proceedings volume contains 14 papers and presents a survey of the state of the art of fuel cell developments. [German] Dieser Band gibt in 14 Beitraegen einen Ueberblick ueber den Stand der Entwicklung der Brennstoffzellen.

Answering Key Fuel Cycle Questions

International Nuclear Information System (INIS)

Piet, S.J.; Dixon, B.W.; Bennett, R.G.; Smith, J.D.; Hill, R.N.

2004-01-01

Given the range of fuel cycle goals and criteria, and the wide range of fuel cycle options, how can the set of options eventually be narrowed in a transparent and justifiable fashion? It is impractical to develop all options. We suggest an approach that starts by considering a range of goals for the Advanced Fuel Cycle Initiative (AFCI) and then posits seven questions, such as whether Cs and Sr isotopes should be separated from spent fuel and, if so, what should be done with them. For each question, we consider which of the goals may be relevant to eventually providing answers. The AFCI program has both ''outcome'' and ''process'' goals because it must address both waste already accumulating as well as completing the fuel cycle in connection with advanced nuclear power plant concepts. The outcome objectives are waste geologic repository capacity and cost, energy security and sustainability, proliferation resistance, fuel cycle economics, and safety. The process objectives are rea diness to proceed and adaptability and robustness in the face of uncertainties

International Nuclear Fuel Cycle Fact Book

International Nuclear Information System (INIS)

Leigh, I.W.

1992-05-01

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need exists costs for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book has been compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NMEA activities reports; and proceedings of conferences and workshops. The data listed typically do not reflect any single source but frequently represent a consolidation/combination of information

International Nuclear Fuel Cycle Fact Book

International Nuclear Information System (INIS)

Leigh, I.W.; Mitchell, S.J.

1990-01-01

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops, etc. The data listed do not reflect any one single source but frequently represent a consolidation/combination of information

International Nuclear Fuel Cycle Fact Book

Energy Technology Data Exchange (ETDEWEB)

Leigh, I W; Mitchell, S J

1990-01-01

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops, etc. The data listed do not reflect any one single source but frequently represent a consolidation/combination of information.

Fission gas behaviour in water reactor fuels

International Nuclear Information System (INIS)

2002-01-01

During irradiation, nuclear fuel changes volume, primarily through swelling. This swelling is caused by the fission products and in particular by the volatile ones such as krypton and xenon, called fission gas. Fission gas behaviour needs to be reliably predicted in order to make better use of nuclear fuel, a factor which can help to achieve the economic competitiveness required by today's markets. These proceedings communicate the results of an international seminar which reviewed recent progress in the field of fission gas behaviour in light water reactor fuel and sought to improve the models used in computer codes predicting fission gas release. State-of-the-art knowledge is presented for both uranium-oxide and mixed-oxide fuels loaded in water reactors. (author)

Underwater inspection, repair and reconstitution of water reactor fuel

International Nuclear Information System (INIS)

1988-06-01

On-site fuel examination plays an important role for evaluation of fuel irradiation performance under reactor operating conditions. Also fuel assembly repairs are economically very attractive for operating nuclear utilities. The status of the processes of examination and repair, equipment used and research plans in Member States are reviewed in these Proceedings. All presentations were divided into three sessions: inspection diagnostic: facilities, techniques, and programmes (8 papers); repair and reconstitution techniques (6 papers); power plant experience (6 papers). A separate abstract was prepared for each of these 20 papers. Refs, figs and tabs

Status and trends in spent fuel reprocessing. Proceedings of an advisory group meeting

International Nuclear Information System (INIS)

1999-08-01

Spent fuel management has always been an important part of the nuclear fuel cycle and is still one of the most important activities in all countries exploiting the peaceful use of nuclear energy. Continuous attention is being given by the IAEA to the collection, analysis and exchange of information on spent fuel management. Its role in this area is to provide a forum for exchanging information and to coordinate and encourage closer co-operation among Member States in certain research and developing activities that are of common interest. As part of spent fuel management, reprocessing activities have been reviewed from time to time on a low profile level under the terminology 'spent fuel treatment'. However, spent fuel treatment covers, in broad terms, spent fuel storage (short, interim and long term), fuel rod consolidation, reprocessing and, in case the once-through cycle is selected, conditioning of the spent fuel for disposal. Hence the reprocessing activities under the heading 'spent fuel treatment' were somewhat misleading. Several meetings on spent fuel treatment have been organized during the fast decade: an Advisory Group meeting (AGM) in 1992, a Technical Committee meeting in 1995 and recently an Advisory Group meeting from 7 to 10 September 1998. The objectives of the meetings were to review the status and trends of spent fuel reprocessing, to discuss the environmental impact and safety aspects of reprocessing facilities and to define the most important issues in this field. Notwithstanding the fact that the Summary of the report does not include aspects of military reprocessing, some of the national presentations do refer to some relevant aspects (e.g. experience, fissile stockpiles)

Proceedings of NEDO International Geothermal Symposium

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-03-11

This is a proceedings of the NEDO International Geothermal Symposium held in Sendai in 1997. The worldwide geothermal energy power generation capacity exceeds 7000 MW. Geothermal energy is widely used also for heating, snow melting, greenhouse cultivation as well as electric power generation. Geothermal energy generates far less CO2 causing the global warming than fossil fuels. The geothermal energy is clean and renewable. Considering the environmental issue and energy supply/demand of the world, we have to exert further efforts for the geothermal development. In this conference, discussions were made on each country`s experiences of the geothermal development, and future prediction and strategies for geothermal utilization in the Asia/Pacific region, in particular. Further, in the technical session, conducted were the IEA study and technical presentation/discussion for technical cooperation. The proceedings includes research reports of more than 30, which are clarified into three fields: impacts of the geothermal development on the environment, technical development of the hot dry rock power generation system, and development of technology for collecting deep-seated geothermal resource

DE-NE0000735 - FINAL REPORT ON THORIUM FUEL CYCLE NEUP PROJECT

Energy Technology Data Exchange (ETDEWEB)

Krahn, Steven [Vanderbilt Univ., Nashville, TN (United States); Ault, Timothy [Vanderbilt Univ., Nashville, TN (United States); Worrall, Andrew [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-09-30

The report is broken into six chapters, including this executive summary chapter. Following an introduction, this report discusses each of the project’s three major components (Fuel Cycle Data Package (FCDP) Development, Thorium Fuel Cycle Literature Analysis and Database Development, and the Thorium Fuel Cycle Technical Track and Proceedings). A final chapter is devoted to summarization. Various outcomes, publications, etc. originating from this project can be found in the Appendices at the end of the document.

Plant-scale anodic dissolution of unirradiated N-Reactor fuel

International Nuclear Information System (INIS)

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

1995-01-01

Anodic dissolution tests were made with unirradiated N-Reactor fuel to determine the fuel segment length, diameter, and shape required for high throughput electro-refiner treatment for ultimate disposal in a geologic repository. Based on these tests, a conceptual design was produced of an electro-refiner for a full-scale plant to process N-Reactor spent fuel. In this design, the diameter of an electrode assembly is about 0.6 m (25 in.). Eight of these assemblies in an electro-refiner would accommodate a 1.333-metric-ton batch of N-Reactor fuel. Electrorefining would proceed at a rate of 40 kg uranium per hour. (author)

Proceedings of the Canadian Nuclear Association 34. annual conference

International Nuclear Information System (INIS)

Girard, A.M.

1994-01-01

The proceedings of the thirty-fourth annual conference of the Canadian Nuclear Association contain 23 complete papers and three speeches organized in the following sessions: opening, plenary, new environmental regulations and their effect on the energy industry, CANDU update, life cycle management of nuclear power plants, evolution of nuclear technology, technologies for tomorrow, nuclear used fuel and disposal of low-level waste, world economics and energy consumption. The complete papers have been abstracted separately

Proceedings of the Canadian Nuclear Association 34. annual conference

Energy Technology Data Exchange (ETDEWEB)

Girard, A M [Atomic Energy of Canada Ltd., Montreal, PQ (Canada). CANDU Operations

1994-12-31

The proceedings of the thirty-fourth annual conference of the Canadian Nuclear Association contain 23 complete papers and three speeches organized in the following sessions: opening, plenary, new environmental regulations and their effect on the energy industry, CANDU update, life cycle management of nuclear power plants, evolution of nuclear technology, technologies for tomorrow, nuclear used fuel and disposal of low-level waste, world economics and energy consumption. The complete papers have been abstracted separately.

Enduring Nuclear Fuel Cycle, Proceedings of a panel discussion

Energy Technology Data Exchange (ETDEWEB)

Walter, C. E., LLNL

1997-11-18

The panel reviewed the complete nuclear fuel cycle in the context of alternate energy resources, energy need projections, effects on the environment, susceptibility of nuclear materials to theft, diversion, and weapon proliferation. We also looked at ethical considerations of energy use, as well as waste, and its effects. The scope of the review extended to the end of the next century with due regard for world populations beyond that period. The intent was to take a long- range view and to project, not forecast, the future based on ethical rationales, and to avoid, as often happens, long-range discussions that quickly zoom in on only the next few decades. A specific nuclear fuel cycle technology that could satisfy these considerations was described and can be applied globally.

Annual meeting on nuclear technology 2005. Proceedings

International Nuclear Information System (INIS)

2005-03-01

The proceedings of the annual meeting on nuclear technology 2005 covers the following issues: (1) reactor physics and methods of calculation: design and transients; method development and validation; (2): thermodynamics and fluid dynamics: analytical thermohydraulics for existing reactors; experiments and operational behavior; analytical methods for innovative reactors; (3) Safety of nuclear installations - methods, analysis, results: special problems; PSA and in-vessel phenomena; ex-vessel phenomena; (4) front end and back end of the fuel cycle, radioactive waste, storage: intermediate storage of fuel elements, waste treatment, (5) fuel elements and core components: fuel elements, new methods in the interpretation, manufacturing and service; (6) operation of nuclear installations: experience with the operation of NPPs; management systems, digital instrumentation and control of NPPs revision management; (7) decommissioning of nuclear installations: concepts and strategies for decommissioning and dismantling; experiences with decommissioning projects; (8) fusion technology: fusion facilities; materials and test facility; cryo technique and simulations; (9) research reactors: building new and backfitting of existing research reactors; current development; dismantling of research reactors; (10) advanced reactor concepts, energy systems, energy economics; (11) communication with the public; (12) component materials, fabrication and service behavior: degradation effects of component materials; component behavior; (13): radiation protection: PSA and in-vessel phenomena, ex-vessel phenomena.

Fuel failure in water reactors: Causes and mitigation. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2003-03-01

The objective of this technical meeting (TM) was to review the present knowledge of the causes and mechanisms of fuel failure in water reactors during normal operational conditions. Emphasis has been given to analysis of failure causes and their mitigation by means of design as well as plant and core operation including strategies for operation with failed fuel. Some information on detection techniques (on-line monitoring and diagnostics, flux tilting, sipping techniques, etc) has also been presented. This TM presented also the progress on the above-mentioned subjects since the last meeting held in 1992 (Dimitrovgrad, Russian Federation). The topics covered in the papers were as follows: Experience feedback on fuel reliability (8 papers); Strategies to avoid or mitigate fuel failures (4 papers); Experimental studies on fuel failures and degradation mechanisms (4 papers); Modelling of fuel failure mechanisms (3 papers); Detection and monitoring during operation or outage (4 papers); Modelling and assessment of fuel failures (3 papers)

Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and systems

International Nuclear Information System (INIS)

2007-01-01

In keeping with the 12-year history of this conference, GLOBAL 2007 focuses on future nuclear energy systems and fuel cycles. With the increasing public acceptance and political endorsement of nuclear energy, it is a pivotal time for nuclear energy research. Significant advances have been made in development of advanced nuclear fuels and materials, reactor designs, partitioning, transmutation and reprocessing technologies, and waste management strategies. In concert with the technological advances, it is more important than ever to develop sensible nuclear proliferation policies, to promote sustainability, and to continue to increase international collaboration. To further these aims, GLOBAL 2007 highlights recent developments in the following areas: advanced integrated fuel cycle concepts, spent nuclear fuel reprocessing, advanced reprocessing technology, advanced fuels and materials, advanced waste management technology, novel concepts for waste disposal and repository development, advanced reactors, partitioning and transmutation, developments in nuclear non-proliferation technology, policy, and implementation, sustainability and expanded global utilization of nuclear energy, and international collaboration on nuclear energy

Fuel chemistry and pellet-clad interaction related to high burnup fuel. Proceedings of the technical committee

International Nuclear Information System (INIS)

2000-10-01

The purpose of the meeting was to review new developments in clad failures. Major findings regarding the causes of clad failures are presented in this publication, with the main topics being fuel chemistry and fission product behaviour, swelling and pellet-cladding mechanical interaction, cladding failure mechanism at high burnup, thermal properties and fuel behaviour in off-normal conditions. This publication contains 17 individual presentations delivered at the meeting; each of them was indexed separately

Prospects and future utilization. Proceedings of a colloquium held in Petten (Netherlands), 20-21 April 1989

International Nuclear Information System (INIS)

Ahlf, J.; Roettger, H.

1989-01-01

These proceedings of a colloquium held in Petten on prospects and future utilization of the HFR reactor are divided into 6 sessions bearing on: - The high flux reactor - irradiation testing of fuel and material for fast breeder reactors - irradiation testing of fuel and material for high temperature reactors and light water reactors - irradiation testing for fusion reactors - neutron radiography, radioisotopes, neutron capture therapy - neutron beam research and application of neutron activation analysis

Uranium hexafluoride handling. Proceedings

Energy Technology Data Exchange (ETDEWEB)

1991-12-31

The United States Department of Energy, Oak Ridge Field Office, and Martin Marietta Energy Systems, Inc., are co-sponsoring this Second International Conference on Uranium Hexafluoride Handling. The conference is offered as a forum for the exchange of information and concepts regarding the technical and regulatory issues and the safety aspects which relate to the handling of uranium hexafluoride. Through the papers presented here, we attempt not only to share technological advances and lessons learned, but also to demonstrate that we are concerned about the health and safety of our workers and the public, and are good stewards of the environment in which we all work and live. These proceedings are a compilation of the work of many experts in that phase of world-wide industry which comprises the nuclear fuel cycle. Their experience spans the entire range over which uranium hexafluoride is involved in the fuel cycle, from the production of UF{sub 6} from the naturally-occurring oxide to its re-conversion to oxide for reactor fuels. The papers furnish insights into the chemical, physical, and nuclear properties of uranium hexafluoride as they influence its transport, storage, and the design and operation of plant-scale facilities for production, processing, and conversion to oxide. The papers demonstrate, in an industry often cited for its excellent safety record, continuing efforts to further improve safety in all areas of handling uranium hexafluoride. Selected papers were processed separately for inclusion in the Energy Science and Technology Database.

Fact sheet on spent fuel management

International Nuclear Information System (INIS)

2006-01-01

The IAEA gives high priority to safe and effective spent fuel management. As an example of continuing efforts, the 2003 International Conference on Storage of Spent Fuel from Power Reactors gathered 125 participants from 35 member states to exchange information on this important subject. With its large number of Member States, the IAEA is well-positioned to gather and share information useful in addressing Member State priorities. IAEA activities on this topic include plans to produce technical documents as resources for a range of priority topics: spent fuel performance assessment and research, burnup credit applications, cask maintenance, cask loading optimization, long term storage requirements including records maintenance, economics, spent fuel treatment, remote technology, and influence of fuel design on spent fuel storage. In addition to broader topics, the IAEA supports coordinated research projects and technical cooperation projects focused on specific needs. The proceedings of the 2003 IAEA conference on storage of spent fuel from power reactors has been ranked in the top twenty most accessed IAEA publications. These proceedings are available for free downloads at http://www-pub.iaea.org/MTCD/publications/PubDetails.asp?pubId=6924]. The IAEA organized and held a 2004 meeting focused on long term spent fuel storage provisions in Central and Eastern Europe, using technical cooperation funds to support participation by these Member States. Over ninety percent of the participants in this meeting rated its value as good or excellent, with participants noting that the IAEA is having a positive effect in stimulating communication, cooperation, and information dissemination on this important topic. The IAEA was advised in 2004 that results from a recent coordinated research project (IAEA-TECDOC-1343) were used by one Member State to justify higher clad temperatures for spent fuel in dry storage, leading to more efficient storage and reduced costs. Long term

Proceedings of American Nuclear Society topical meeting on light water reactor fuel performance

International Nuclear Information System (INIS)

1979-01-01

Separate abstracts are included for 32 of the 39 papers presented concerning fuel performance; fuel performance under transient and off-normal operations; fuel-cladding interactions; and fission product release. Seven papers have previously been input into the data base

Proceedings of the 3. General Congress on Nuclear Energy. v. 9

International Nuclear Information System (INIS)

1990-01-01

The Proceedings of the 3. General Congress on Nuclear Energy (CGEN), present about 200 contributed papers. The topics covered by the meeting are: reactor physics and operation; risk analysis, safety analysis, nuclear power plants construction; thermohydraulics; nuclear power plants control and instrumentation; equipment and system design, radioactive management; fuel cycle; design and fabrication of fuel elements, science and technology materials; instrumentation for radiation detection and dosimetry; shielding, radiation protection, licensing, safeguards, social and environmental impacts; radioisotopes production and application; radiochemistry, radioecology; nuclear medicine and radiobiology. In this volume the contributed papers emphasize the topics shielding, radiation protection, licensing, safeguards and social and environmental impacts. (M.I.A.)

International conference on innovative technologies for nuclear fuel cycles and nuclear power. Unedited proceedings

International Nuclear Information System (INIS)

2004-01-01

Nuclear power is a significant contributor to the global supply of electricity, and continues to be the major source that can provide electricity on a large scale with a comparatively minimal impact on the environment. But it is evident that, despite decades of experience with this technology, nuclear power today remains mainly in a holding position, with its future somewhat uncertain primarily due to concerns related to waste, safety and security. One of the most important factors that would influence future nuclear growth is the innovation in reactor and fuel cycle technologies to successfully maximize the benefits of nuclear power while minimizing the associated concerns. The main objectives of the Conference were to facilitate exchange of information between senior experts and policy makers from Member States and international organizations on important aspects of the development of innovative technologies for future generations of nuclear power reactors and fuel cycles; to create an understanding of the social, environmental and economic conditions that would facilitate innovative and sustainable nuclear technologies; and to identify opportunities for collaborative work between Member States and international organizations and programmes. All relevant aspects of innovative technologies for nuclear fuel cycles and nuclear power were discussed in an open, frank and objective manner. These proceedings contain a summary of the results of the conference, invited and contributed papers, and summaries of panel discussions. No large increase in the use of nuclear energy is foreseen in the near and medium term, but is likely in the long term if developing country per-capita electricity consumption reaches that of the developed world. The nuclear sector including regulators view an increased use of nuclear energy as the solution for global sustainable energy needs considering that significant reductions in CO 2 emissions would be required. Although the current nuclear

Accident Tolerant Fuel Concepts for Light Water Reactors. Proceedings of a Technical Meeting

International Nuclear Information System (INIS)

2016-06-01

Nuclear fuel is a highly complex material that has been subject to continuous development over the past 40 years and has reached a stage where it can be safely and reliably irradiated up to 65 GWd/tU in commercial nuclear reactors. During this time, there have been many improvements to the original designs and materials used. However, the basic design of uranium oxide fuel pellets clad with zirconium alloy tubing has remained the fuel choice for the vast majority of commercial nuclear power plants. Severe accidents, such as those at the Three Mile Island and Fukushima Daiichi have shown that under such extreme conditions, nuclear fuel will fail and the high temperature reactions between zirconoi alloys and water will lead to the generation of hydrogen, with the potential for explosions to occur, daming the plant further. Recognizing that the current fuel designs are vulnerable to severe accident conditions, tehre is renewed interesst in alternative fuel designs that would be more resistant to fuel failure and hydrogen production. Such new fuel designs will need to be compatible with existing fuel and reactor systems if they are to be utilized in the current reactor fleet and in current new build designs, but there is also the possibility of new designs for new reactor systems. This publication provides a record of the Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, held at Oak Ridge National Laboratories (ORNL), United States of America, 13-16 October 2014, to consider the early stages of research and development into accident tolerant fuel. There were 45 participants from 10 countries taking part in the meeting, with 32 papers organized into 7 sessions, of which 27 are included in this publication. This meeting is part of a wider investigation into such designs, and it is anticipated that further Technical Meetings and research programmes will be undertaken in this field

Fuel Cell / electrolyser, Solar Photovoltaic Powered

Directory of Open Access Journals (Sweden)

Chioncel Cristian Paul

2012-01-01

Full Text Available The paper presents experimental obtained results in the operation ofelectrolyzer powered by solar photovoltaic modules, for the waterelectrolysis and with the obtained hydrogen and oxygen proceeds tothe operation in fuel cell mode, type PEM. The main operatingparameters and conditions to optimize the energy conversion on thesolar-hydrogen-electricity cycle are highlighted, so that those arecomparable or superior to conventional cycles.

Heavy-Water Power Reactors. Proceedings Of A Symposium

International Nuclear Information System (INIS)

1968-01-01

Proceedings of a Symposium organized by the IAEA and held in Vienna, 11-15 September 1967. The timeliness of the meeting was underlined by the large gathering of over 225 participants from 28 countries and three international organizations. Contents: Experience with heavy-water power and experimental reactors and projects (14 papers); New and advanced power reactor designs and concepts (8 papers); Development programmes and thorium cycle (9 papers); Economics and prospects of heavy-water power reactors (7 papers); Physics and fuel management (8 papers); Fuels (5 papers); Safety, control and engineering (6 papers); Panel discussion. Except for one Russian paper, which is published in English, each paper is in its original language (49 English and 8 French) and is preceded by an abstract in English with a second one in the original language if this is not English. Discussions are in English. (author)

Heavy-Water Power Reactors. Proceedings Of A Symposium

Energy Technology Data Exchange (ETDEWEB)

NONE

1968-04-15

Proceedings of a Symposium organized by the IAEA and held in Vienna, 11-15 September 1967. The timeliness of the meeting was underlined by the large gathering of over 225 participants from 28 countries and three international organizations. Contents: Experience with heavy-water power and experimental reactors and projects (14 papers); New and advanced power reactor designs and concepts (8 papers); Development programmes and thorium cycle (9 papers); Economics and prospects of heavy-water power reactors (7 papers); Physics and fuel management (8 papers); Fuels (5 papers); Safety, control and engineering (6 papers); Panel discussion. Except for one Russian paper, which is published in English, each paper is in its original language (49 English and 8 French) and is preceded by an abstract in English with a second one in the original language if this is not English. Discussions are in English. (author)

High Burnup Fuel: Implications and Operational Experience. Proceedings of a Technical Meeting

International Nuclear Information System (INIS)

2016-08-01

This publication reports on the outcome of a technical meeting on high burnup fuel experience and economics, held in Buenos Aires, Argentina in 2013. The purpose of the meeting was to revisit and update the current operational experience and economic conditions associated with high burnup fuel. International experts with significant experience in experimental programmes on high burnup fuel discussed and evaluated physical limitations at pellet, cladding and structural component levels, with a wide focus including fabrication, core behaviour, transport and intermediate storage for most types of commercial nuclear power plants

Proceedings of the specialist meeting on the safety of water reactors fuel elements

International Nuclear Information System (INIS)

1973-01-01

This specialist meeting on the safety of water reactors fuel elements was held in Saclay (France) in October 1973, and was organized by CSNI and CEA. It attracted specialists from 14 countries. Session I was devoted to normal operating conditions (coolant-cladding and fuel-cladding interactions, fission product release, effects of cladding deformation on fuel element performances and reactor operating limits); Session II was devoted to operating reactor accidents and failures, anomalous transients and handling accidents; Session III was devoted to modifications to be applied to fuel elements in order to enhance their safety and reliability; Session IV was devoted to Loss-of-Coolant Accidents (LOCA)(cladding behaviour during the accident, assembly behaviour during the accident, criteria to be considered for the study of fuel element behaviour during a LOCA)

Conference on natural gas use state regulation and market dynamics in the Post 636/Energy Policy Act Era: Proceedings

Energy Technology Data Exchange (ETDEWEB)

1993-08-01

Reports in this Record of Proceedings explore a wide variety of issues related to the regulation of natural gas and its future role as one of the critical fuels that powers the economy of the United States. The focus is mainly on problems, obstacles, barriers, and the incredibly complex system created to bring a fuel from wellhead to burner tip. Individual papers have been cataloged separately.

Conference on natural gas use state regulation and market dynamics in the Post 636/Energy Policy Act Era: Proceedings

International Nuclear Information System (INIS)

1993-01-01

Reports in this Record of Proceedings explore a wide variety of issues related to the regulation of natural gas and its future role as one of the critical fuels that powers the economy of the United States. The focus is mainly on problems, obstacles, barriers, and the incredibly complex system created to bring a fuel from wellhead to burner tip. Individual papers have been cataloged separately

Proceedings of condensed papers on alternate energy sources

Energy Technology Data Exchange (ETDEWEB)

Veziroglu, T.N. (ed.)

1979-01-01

The conference covers the results of research and developments which have taken place during the last 2 years. It includes sessions on solar energy, ocean thermal energy, wind energy, hydro power, nuclear breeders and nuclear fusion, synthetic fuels from coal or waste, hydrogen production and uses. The volume of the Proceedings presents the papers and lectures in condensed format grouped by their subjects under 40 technical sessions. Condensed papers are presented for the 336 presentations; abstracts have previously appeared in the DOE Energy Data Base for 33 of the full-length papers.

Proceedings of the 1992 topical meeting on advances in reactor physics

International Nuclear Information System (INIS)

1992-01-01

This document, Volume 1, presents proceedings of the 1992 Topical Meeting on Advances in Reactor Physics on March 8--11, 1992 at Charleston, SC. Session topics were as follows: Code Benchmarks and Validation; Fuel Management; Nodal Methods for Diffusion Theory; Criticality Safety and Applications and Waste; Core Computational Systems; Nuclear Data; Safety Aspects of Heavy Water Reactors; and Space-Time Core Kinetics. The individual papers have been cataloged separately. (FI)

Third international spent fuel storage technology symposium/workshop: proceedings. Volume 2

International Nuclear Information System (INIS)

1986-01-01

The scope of this meeting comprised dry storage and rod consolidation, emphasizing programs on water reactor fuel with zirconium alloy cladding. Volume 2 contains the papers from the poster session and workshops that were conducted during the meeting. There were 18 poster presentations. Four workshops were held: Fuel Integrity; Storage System Modeling and Analysis; Rod Consolidation Technology; and System Integration and Optimization. Individual papers were processed for inclusion in the Energy Data Base

Alternatives for water basin spent fuel storage: executive summary and comparative evaluation

International Nuclear Information System (INIS)

Viebrock, J.M.

1979-09-01

A five part report identifies and evaluates alternatives to conventional methods for water basin storage of irradiated light water reactor fuel assemblies (spent fuel). A recommendation is made for development or further evaluation of one attractive alternative: Proceed to develop fuel disassembly with subsequent high density storage of fuel pins (pin storage). The storage alternatives were evaluated for emplacement at reactor, in existing away-from-reactor storage facilities and in new away-from-reactor facilities. In the course of the study, the work effort necessarily extended beyond the pool wall in scope to properly assess the affects of storage alternatives on AFT systems

Proceedings of a topical meeting on safety of the nuclear fuel cycle

International Nuclear Information System (INIS)

1996-01-01

The topical meeting on the safety of the nuclear fuel cycle is composed of 17 papers grouped into four sessions which titles are: operational safety in nuclear fuel facilities; safety criteria and regulatory philosophy; plant hazard analysis and mitigation; plant experience and emergency planning

Technical and economic limits to fuel burnup extension. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

2002-07-01

For many years, the increase of efficiency in the production of nuclear electricity has been an economic challenge in many countries which have developed this kind of energy. The increase of fuel burnup leads to a reduction in the volume of spent fuel discharged to longer fuel cycles in the reactor, which means bigger availability and capacity factors. After having increased the authorized burnup in plants, developing new alloys capable of resisting high burnup, and having accumulated data on fuel evolution with burnup, it has become necessary to establish the limitations which could be imposed by the physical evolution of the fuel, influencing fuel management, neutron properties, reprocessing or, more generally, the management of waste and irradiated fuels. It is also necessary to verify whether the benefits of lower electricity costs would not be offset by an increase in fuel management costs. The main questions are: Are technical and economic limits to the increasing of fuel burnup in parallel? Can we envisage nowadays the hardest limitation in some of these areas? Which are the main points to be solved from the technical point of view? Is this effort worthwhile considering the economy of the cycle? To which extent? For these reasons, the IAEA, following a recommendation by the International Working Group on Fuel Performance and Technology, held a Technical Committee Meeting on Technical and Economic Limits to Fuel Burnup Extension. The purpose of this meeting was to provide an international forum to review the evolution of fuel properties at increased burnup in order to estimate the limitations both from a physical and an economic point of view. The meeting was therefore divided into two parts. The first part, focusing on technical limits, was devoted to the improvement of the fuel element, such as fission gas release (FGR), RIM effect, cladding, etc. and the fabrication, core management, spent fuel and reprocessing. Eighteen related papers were presented which

Proceedings of the 25th intersociety energy conversion engineering conference

International Nuclear Information System (INIS)

Nelson, P.A.; Schertz, W.W.; Till, R.H.

1990-01-01

This book contains the proceedings of the 25th intersociety energy conversion engineering conference. Volume 1 is organized under the following headings: space power systems requirements and issues, space power systems; space power systems 2; space nuclear power reactors space nuclear reactor technology I; space nuclear reactor technology II; reactor technology; isotopic fueled power systems I, isotopic fueled power systems II, space power automation; space power automation II, space power automation III; space power automation IV; space power automation V; power systems hardware and design selection, power components, pulse power, power management and distribution, power management and distribution II, power management and distribution III; space energy conversion: solar dynamic, space energy conversion: static and dynamic, space solar array technology, advanced space solar cells

Thorium-based nuclear fuel: current status and perspectives

International Nuclear Information System (INIS)

1987-03-01

Until the present time considerable efforts have already been made in the area of fabrication, utilization and reprocessing of Th-based fuels for different types of reactors, namely: by FRG and USA - for HTRs; FRG and Brazil, Italy - for LWRs; India - for HWRs and FBRs. Basic research of thorium fuels and thorium fuel cycles are also being undertaken by Australia, Canada, China, France, FRG, Romania, USSR and other countries. Main emphasis has been given to the utilization of thorium fuels in once-through nuclear fuel cycles, but in some projects closed thorium-uranium or thorium-plutonium fuel cycles are also considered. The purpose of the Technical Committee on the Utilization of Thorium-Based Nuclear Fuel: Current Status and Perspective was to review the world thorium resources, incentives for further exploration, obtained experience in the utilization of Th-based fuels in different types of reactors, basic research, fabrication and reprocessing of Th-based fuels. As a result of the panel discussion the recommendations on future Agency activities and list of major worldwide activities in the area of Th-based fuel were developed. A separate abstract was prepared for each of the 9 papers in this proceedings series

Proceedings of the 5th International workshop on hydrogen and fuel cells WICaC 2010

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

The 5th International Workshop on Hydrogen and Fuel Cells - WICaC 2010 aims to bring the most recent advances on fuel cell and hydrogen technologies. The conference will address the trends on hydrogen production, distribution, delivery, storage and infrastructure as well as fuel cell research, development, demonstration and commercialization. Some of the issues addressed at WICaC 2010 are: the official Brazilian hydrogen and fuel cell programs and its participation in the international programs and partnerships such as the IPHE (The International Partnership for Hydrogen and Fuel Cells in the Economy); the integration of renewable energy sources with hydrogen and fuel cell systems; the challenges to deploy the commercialization and use of fuel cells and hydrogen; distributed generation of energy; fuel cell uses in portable devices and in vehicles; life-cycle assessment of fuel cells and hydrogen technologies; environmental aspects; energy efficiency.

Simulation of fuel demand for wood-gas in combustion engine

Directory of Open Access Journals (Sweden)

Botwinska Katarzyna

2017-01-01

Full Text Available In the era of the oil crisis and proceeding contamination of the natural environment, it is attempted to substitute fossil raw materials with alternative carriers. For many years, road transport has been considered as one of the main sources of the substances deteriorating air quality. Applicable European directives oblige the member states to implement biofuels and biocomponents into the general fuel market, however, such process is proceeding gradually and relatively slowly. So far, alternative fuels have been used on a large scale to substitute diesel fuel or petrol. Derivatives of vegetable raw materials, such as vegetable oils or their esters and ethanol extracted from biomass, are used to that end. It has been noticed that there is no alternative to LPG which, due to financial reasons, is more and more popular as fuel in passenger cars. In relation to solutions adopted in the past, it has been decided to analyse the option of powering a modern passenger car with wood gas - syngas. Such fuel has been practically used since the 1920's. To that end, a computer simulation created in SciLab environment was carried out. Passenger car Fiat Seicento, fitted with Fire 1.1 8V petrol engine with power of 40kW, whose parameters were used to prepare the model, was selected as the model vehicle. The simulation allows the determination of engine demand on the given fuel. Apart from the wood gas included in the title, petrol, methane and LPG were used. Additionally, the created model enables the determination of the engine power at the time of the indicated fuels supply. The results obtained in the simulation revealed considerable decrease in the engine power when the wood gas was supplied and the increased consumption of this fuel. On the basis of the analysis of the professional literature describing numerous inconveniences connected with the use of this fuel as well as the obtained results, it has been established that using the wood gas as alternative

Simulation of fuel demand for wood-gas in combustion engine

Science.gov (United States)

Botwinska, Katarzyna; Mruk, Remigiusz; Tucki, Karol; Wata, Mateusz

2017-10-01

In the era of the oil crisis and proceeding contamination of the natural environment, it is attempted to substitute fossil raw materials with alternative carriers. For many years, road transport has been considered as one of the main sources of the substances deteriorating air quality. Applicable European directives oblige the member states to implement biofuels and biocomponents into the general fuel market, however, such process is proceeding gradually and relatively slowly. So far, alternative fuels have been used on a large scale to substitute diesel fuel or petrol. Derivatives of vegetable raw materials, such as vegetable oils or their esters and ethanol extracted from biomass, are used to that end. It has been noticed that there is no alternative to LPG which, due to financial reasons, is more and more popular as fuel in passenger cars. In relation to solutions adopted in the past, it has been decided to analyse the option of powering a modern passenger car with wood gas - syngas. Such fuel has been practically used since the 1920's. To that end, a computer simulation created in SciLab environment was carried out. Passenger car Fiat Seicento, fitted with Fire 1.1 8V petrol engine with power of 40kW, whose parameters were used to prepare the model, was selected as the model vehicle. The simulation allows the determination of engine demand on the given fuel. Apart from the wood gas included in the title, petrol, methane and LPG were used. Additionally, the created model enables the determination of the engine power at the time of the indicated fuels supply. The results obtained in the simulation revealed considerable decrease in the engine power when the wood gas was supplied and the increased consumption of this fuel. On the basis of the analysis of the professional literature describing numerous inconveniences connected with the use of this fuel as well as the obtained results, it has been established that using the wood gas as alternative fuel is currently

Development of probabilistic fast reactor fuel design method

International Nuclear Information System (INIS)

Ozawa, Takayuki

1997-01-01

Under the current method of evaluating fuel robustness in FBR fuel rod design, a variety of uncertain quantities including fuel production tolerance and power density are estimated conservatively. In the future, in order to proceed with improvements in the FBR core's performance and optimize the fuel's specifications, a rationalization of fuel design tolerance is required. Among the measures aimed at realizing this rationalization, the introduction of a probabilistic fast reactor fuel design method is currently under consideration. I have developed a probabilistic fast reactor fuel design code named BORNFREE, in order to make use of this method in FBR fuel design. At the same time, I have carried out a trial calculation of the cladding stress using this code and made a study and an evaluation of the possibility of employing tolerance rationalization in fuel rod design. In this paper, I provide an outline description of BORNFREE and report the results of the above study and evaluation. After performing cladding stress trial calculations using the probabilistic method, I was able to confirm that this method promises more rational design evaluation results than the conventional deterministic method. (author)

Proceedings of the Canadian Nuclear Association 28. annual conference held in Winnipeg, Manitoba, June 12-15, 1988

International Nuclear Information System (INIS)

1988-01-01

The proceedings of the 28. CNA (Canadian Nuclear Association) conference contain 28 papers under the following headings: power reactors; fuel cycles; nuclear power and public understanding; future trends; and, applications of nuclear technology. CANDU reactors are emphasized. The individual papers have been abstracted separately

Towards a greener world : hydrogen and fuel cells 2004 conference and trade show. Conference proceedings

International Nuclear Information System (INIS)

2004-01-01

Fuel Cells Canada and the Canadian Hydrogen Association hosted the Hydrogen and Fuel Cells 2004 Conference and Tradeshow in Toronto, Ontario, Canada on September 25-28, 2004. Industry leaders from around the world showcased the latest developments in fuel cell and hydrogen technology, and shared research breakthroughs. The conference focussed on many aspects of hydrogen and fuel cell technology, specifically: hydrogen technology progress, including storage, infrastructure and production; fuel cells, including quality, cost and applications; economics and policy, including government and industry strategies; fuel cell demonstrations, including transportation, micro-fuel cells, and portable power; and, impact on climate change, including health and the Kyoto Accord

CFTSIM-ITER dynamic fuel cycle model

International Nuclear Information System (INIS)

Busigin, A.; Gierszewski, P.

1998-01-01

Dynamic system models have been developed for specific tritium systems with considerable detail and for integrated fuel cycles with lesser detail (e.g. D. Holland, B. Merrill, Analysis of tritium migration and deposition in fusion reactor systems, Proceedings of the Ninth Symposium Eng. Problems of Fusion Research (1981); M.A. Abdou, E. Vold, C. Gung, M. Youssef, K. Shin, DT fuel self-sufficiency in fusion reactors, Fusion Technol. (1986); G. Spannagel, P. Gierszewski, Dynamic tritium inventory of a NET/ITER fuel cycle with lithium salt solution blanket, Fusion Eng. Des. (1991); W. Kuan, M.A. Abdou, R.S. Willms, Dynamic simulation of a proposed ITER tritium processing system, Fusion Technol. (1995)). In order to provide a tool to understand and optimize the behavior of the ITER fuel cycle, a dynamic fuel cycle model called CFTSIM is under development. The CFTSIM code incorporates more detailed ITER models, specifically for the important isotope separation system, and also has an easier-to-use graphical interface. This paper provides an overview of CFTSIM Version 1.0. The models included are those with significant and varying tritium inventories over a test campaign: fueling, plasma and first wall, pumping, fuel cleanup, isotope separation and storage. An illustration of the results is shown. (orig.)

Influence of proceedings papers on citation impact in seven sub-fields of sustainable energy research 2005–2011

DEFF Research Database (Denmark)

Ingwersen, Peter; Larsen, Birger; Garcia-Zorita, J. Carlos

2014-01-01

and Wave Energy, Geo-thermal, Bio-fuel and Bio-mass energy ub-fields. The analyses cover peer reviewed research and review articles as well as two kinds of proceeding papers from conferences published 2005–2009 in (a) book series or volumes and (b) special journal issues excluding meeting abstracts cited......This paper analyses the following seven sub-fields of Sustainable Energy Research with respect to the influence of proceedings papers on citation patterns across citing and cited document types, overall sub-field and document type impacts and citedness: the Wind Power, Renewable Energy, Solar...

Proceedings of the 1983 civilian radioactive waste management information meeting

International Nuclear Information System (INIS)

1984-02-01

This proceedings document from the 1983 Civilian Radioactive Waste Management Information Meeting serves to highlight developments since the passage of the Nuclear Policy Act of 1982 and reviews program activities necessary to provide for the permanent disposal and storage of commercially generated high-level radioactive waste. Presentations included in this program cover topics concerning interim spent fuel, monitored retrievable storage, geologic repository deployment as well as management of the Nuclear Waste Fund. Individual papers were abstracted for inclusion in the Energy Data Base

Materials for advanced power engineering 2010. Proceedings

International Nuclear Information System (INIS)

Lecomte-Beckers, Jacqueline; Contrepois, Quentin; Beck, Tilmann; Kuhn, Bernd

2010-01-01

The 9th Liege Conference on ''Materials for Advanced Power Engineering'' presents the results of the materials related COST Actions 536 ''Alloy Development for Critical Components of Environmentally Friendly Power Plants'' and 538 ''High Temperature Plant Lifetime Extension''. In addition, the broad field of current materials research perspectives for high efficiency, low- and zero- emission power plants and new energy technologies for the next decades are reported. The Conference proceedings are structured as follows: 1. Materials for advanced steam power plants; 2. Gas turbine materials; 3. Materials for nuclear fission and fusion; 4. Solid oxide fuel cells; 5. Corrosion, thermomechanical fatigue and modelling; 6. Zero emission power plants.

Materials for advanced power engineering 2010. Proceedings

Energy Technology Data Exchange (ETDEWEB)

Lecomte-Beckers, Jacqueline; Contrepois, Quentin; Beck, Tilmann; Kuhn, Bernd [eds.

2010-07-01

The 9th Liege Conference on ''Materials for Advanced Power Engineering'' presents the results of the materials related COST Actions 536 ''Alloy Development for Critical Components of Environmentally Friendly Power Plants'' and 538 ''High Temperature Plant Lifetime Extension''. In addition, the broad field of current materials research perspectives for high efficiency, low- and zero- emission power plants and new energy technologies for the next decades are reported. The Conference proceedings are structured as follows: 1. Materials for advanced steam power plants; 2. Gas turbine materials; 3. Materials for nuclear fission and fusion; 4. Solid oxide fuel cells; 5. Corrosion, thermomechanical fatigue and modelling; 6. Zero emission power plants.

Nuclear fuel assembly with improved spectral shift-producing rods

International Nuclear Information System (INIS)

Ferrari, H.M.

1987-01-01

This patent describes a nuclear reactor having fuel assemblies and a moderator-coolant liquid flowing through the fuel assemblies, each fuel assembly including an organized array of nuclear fuel rods wherein the moderator-coolant liquid flows along the fuel rods, at least one improved spectral shift-producing rod disposed among the fuel rods. The spectra shift-producing rod consists of: (a) an elongated hollow hermetically-sealed tubular member; (b) a weakened region formed in a portion of the member, the portion being subject to rupture at a given level of internal pressure; and (c) burnable poison material contained in the member which generates gas in the member as operation of the reactor proceeds normally, the material being soluble in the moderator-coolant liquid when brought into contact therewith; (d) the given level of internal pressure being less than the maximum level of internal pressure normally expected to be generated within the member by the poison material by normal operation of the reactor

Spent fuel management: Current status and prospects 1995. Proceedings of a regular advisory group meeting

International Nuclear Information System (INIS)

1996-08-01

Spent fuel management has always been one of the important stages in the nuclear fuel cycle and it is still one of the most vital problems common to all countries with nuclear reactors. It begins with the discharge of spent fuel from a power or a research reactor and ends with its ultimate disposition, either by direct disposal or by reprocessing of the spent fuel. Two options exist - an open, once-through cycle with direct disposal of the spent fuel and a closed cycle with reprocessing of the spent fuel and recycling of plutonium and uranium in new mixed oxide fuels. The selection of a spent fuel strategy is a complex procedure in which many factors have to be weighed, including political, economic and safeguards issues as well as protection of the environment. This report gives an overview of the status of spent fuel management programmes in a number of countries, a description of the current status and prospects of activities in this field and recommendations of the participants. Refs, figs, tabs

Proceedings of the first symposium on Monte Carlo simulation

International Nuclear Information System (INIS)

2001-01-01

The first symposium on Monte Carlo simulation was held at Mitsubishi Research Institute, Otemachi, Tokyo, on 10th and 11st of September, 1998. This symposium was organized by Nuclear Code Research Committee at Japan Atomic Energy Research Institute. In the sessions, were presented orally 21 papers on code development, parallel calculation, reactor physics, burn-up, criticality, shielding safety, dose evaluation, nuclear fusion reactor, thermonuclear fusion plasma, nuclear transmutation, electromagnetic cascade, fuel cycle facility. Those presented papers are compiled in this proceedings. The 21 of the presented papers are indexed individually. (J.P.N.)

Reduced enrichment for research and test reactors: Proceedings

Energy Technology Data Exchange (ETDEWEB)

1993-08-01

November 9--10, 1978, marked the first of what has become an annual event--the International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR). The meeting brought together for the first time many people who became major program participants in later years. This first meeting emphasized fuel development, and it established the basis for all later meetings. Believing that the proceedings of this first meeting are important as a historical record of the beginning of the international RERTR effort. This report provides presentations and discussions of this original meeting. Individual papers have been cataloged separately.

Reduced enrichment for research and test reactors: Proceedings

International Nuclear Information System (INIS)

1993-08-01

November 9--10, 1978, marked the first of what has become an annual event--the International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR). The meeting brought together for the first time many people who became major program participants in later years. This first meeting emphasized fuel development, and it established the basis for all later meetings. Believing that the proceedings of this first meeting are important as a historical record of the beginning of the international RERTR effort. This report provides presentations and discussions of this original meeting. Individual papers have been cataloged separately

Properties of light water reactor spent fuel cladding. Interim report

International Nuclear Information System (INIS)

Farwick, D.G.; Moen, R.A.

1979-08-01

The Commercial Waste and Spent Fuel Packaging Program will provide containment packages for the safe storage or disposal of spent Light Water Reactor (LWR) fuel. Maintaining containment of radionuclides during transportation, handling, processing and storage is essential, so the best understanding of the properties of the materials to be stored is necessary. This report provides data collection, assessment and recommendations for spent LWR fuel cladding materials properties. Major emphasis is placed on mechanical properties of the zircaloys and austenitic stainless steels. Limited information on elastic constants, physical properties, and anticipated corrosion behavior is also provided. Work is in progress to revise these evaluations as the program proceeds

Proceedings of the 10. Meeting on Reactor Physics and Thermal Hydraulics; Anais do 10. Encontro de Fisica de Reatores e Termo-Hidraulica

Energy Technology Data Exchange (ETDEWEB)

Santos Bastos, W. dos

1995-12-31

These proceedings presents all the Meeting papers emphasizing specific aspects on reactor physics method, criticality, fuel management, nuclear data, safety analysis, simulation and shielding, neutronics, thermal hydraulics, reactor operation and computational methods.

Guidebook on destructive examination of water reactor fuel

International Nuclear Information System (INIS)

1997-01-01

As a result of common efforts of fuel vendors, utilities and research institutes the average burnup pf design batch fuels was increased for both PWRs and BWRs and the fuel failure rate has been reduced. The previously published Guidebook on Non-Destructive Examination of Water Reactor Fuel recommended that more detailed destructive techniques are required for complete understanding of fuel performance. On the basis of contributions of the 14 participants in the ED-WARF-II CRP and proceedings of IAEA Technical Committee on Recent Developments in Post-irradiation Examination Techniques for Water Reactor Fuel this guidebook was compiled. It gives a complete survey of destructive techniques available to date worldwide. The following examination techniques are described in detailed including major principles of equipment design: microstructural studies; elemental analysis; isotopic analysis; measurement of physical properties; measurement of mechanical properties. Besides the examination techniques, methods for refabrication of experimental rods from high burnup power reactor rods as well as methods for verification of non-destructive techniques by using destructive techniques is included

Spent fuel management: Current status and prospects 1997. Proceedings of a regular advisory group meeting

International Nuclear Information System (INIS)

1998-03-01

Spent fuel management has always been one of the important stages in the nuclear fuel cycle and it is still most vital problems common to all countries with nuclear reactors. It begins with the discharge of spent fuel from a power or a research reactor and ends with its ultimate disposition. Two options exist - an open, once-through cycle with direct disposal of the spent fuel and a closed cycle with reprocessing of the spent fuel, recycling of reprocessed plutonium and uranium in new mixed oxide fuels and disposal of the radioactive waste. Continuous attention is being given by the IAEA to the collection, analysis and exchange of information on spent fuel management. Its role in this area is to provide a forum for exchanging information and to co-ordinate and to encourage closer co-operation among Member States in certain research and development activities that are of common interest. Spent fuel management is recognized as a high priority IAEA activity. The Regular Advisory Group on Spent Fuel Management was established in 1982. The objective of the Regular Advisory Group is to serve as a means of exchanging information on the current status and progress of national programmes on spent fuel management and to provide advice to the IAEA. The results of the last Regular Advisory Group meeting (9-12 September 1997) are reflected in this report. It gives an overview of the status of spent fuel management programmes in a number of countries, a description of the current status and prospects of activities in this field and recommendations of the participants

Babcock and Wilcox plate fabrication experience with uranium silicide spherical fuel

International Nuclear Information System (INIS)

Todd, Lawrence E.; Pace, Brett W.

1996-01-01

This report is written to present the fuel fabrication experience of Babcock and Wilcox using atomized spherical uranium silicide powder. The intent is to demonstrate the ability to fabricate fuel plates using spherical powder and to provide useful information proceeding into the next phase of work using this type of fuel. The limited quantity of resources- spherical powder and time, did not allow for much process optimizing in this work scope. However, the information contained within provides optimism for the future of spherical uranium silicide fuel plate fabrication at Babcock and Wilcox.The success of assembling fuel elements with spherical powder will enable Babcock and Wilcox to reduce overall costs to its customers while still maintaining our reputation for providing high quality research and test reactor products. (author)

The nuclear fuel cycle is complete

International Nuclear Information System (INIS)

Hildenbrand, G.

1984-01-01

The nuclear fuel cycle in the Federal Republic of Germany has a firm base. Its entry stages, natural uranium, conversion, enrichment, and fuel fabrication, have not only been put on solid grounds in terms of supplies, but have also attained a high degree of technical maturity and a high quality level. Further efforts are being devoted to cost reductions. Especially higher burnups and the recycling of plutonium in the form of MOX fuel assemblies in light water reactors must be mentioned under this heading. In the field of back end fuel cycle steps, the important sector of interim storage has now found a practical solution, which is also fully sufficient with respect to capacity. The project of a German reprocessing plant has now entered its decisive stage with the filling of the licensing applications and the awarding of the planning contracts. The study on alternative waste management techniques entitled ''Direct Final Storage'' is about to be concluded, and a work on the exploration and development of a repository proceeds on schedule. (orig.) [de

Proceedings of workshop on reactor shutdown system

International Nuclear Information System (INIS)

1997-03-01

India has gained considerable experience in design, development, construction and operation of research and power reactors during the last four decades. Reactor shutdown system (RSS) is the most important engineered safety system of any reactor. A lot of technological developments have taken place to improve the reactor shutdown systems, particularly with advancement in reliability analysis and instrumentation and control. If the reactor is not shutdown, the fuel may melt, releasing radioactivity and possibly reactivity addition as in the case of Fast Breeder Reactor (FBR). Apart from radiological safety consequences, large investment has to be written off. The function of the RSS is to stop fission chain reaction and prevent breach of fuel. The design of RSS is multidisciplinary. It requires reactor physics analysis, design of absorber rods, drive mechanisms, safety logic to order shutdown and instrumentation to detect unsafe conditions. High reliability is essential and this requires two independent shutdown systems. This book contains the proceedings of the workshop on reactor shutdown system and papers relevant to INIS are indexed separately

Proceedings of the third specialist meeting on sodium/fuel interaction in fast reactors

International Nuclear Information System (INIS)

1976-01-01

This specialist meeting, sponsored by the OECD-NEA and organized by the Power Reactor and Nuclear Fuel Development Corporation, was attended by 56 delegates from 6 countries and the CEC (Commission of the European Communities). The purpose of the meeting was to bring together and discuss in depth the Fuel-Sodium Interaction, a phenomenon of major importance in the assessment of the Hypothetical Core Disruptive Accident in the Liquid Metal Fast Breeder Reactor. The meeting was essentially a follow-up of an earlier meeting held at Ispra in December 1973. In all, 29 papers were presented, covering the following topics: 1. Current perspective on sodium-fuel interaction in LMFBR safety; 2. Basic experimental and theoretical studies including other materials; 3. In-pile and out-of-pile experimental studies on sodium-fuel interaction; 4. Theoretical models for the interpretation of experiments and for application to reactor situations. The meeting is considered useful in narrowing down the chain of events necessary to get energetic interaction, large work potential, but many points are being clarified on the gap between the basic vapor explosions and the real fuel sodium interactions in the HCDA scenario of LMFBR. Finally another meeting of the same nature as this one has been recommended

Concept for a small, colocated fuel cycle facility for oxide breeder fuels

International Nuclear Information System (INIS)

Burch, W.D.; Stradley, J.G.; Lerch, R.E.

1987-01-01

As part of a United States Department of Energy (USDOE) program to examine innovative liquid-metal reactor (LMR) system designs over the past three years, the Oak Ridge National Laboratory (ORNL) and the Westinghouse Hanford Company (WHC) collaborated on studies of mixed oxide fuel cycle options. A principal effort was an advanced concept for a small integrated fuel cycle colocated with a 1300-MW(e) reactor station. The study provided a scoping design and a basis on which to proceed with implementation of such a facility if future plans so dictate. The facility integrated reprocessing, waste management, and refabrication functions in a single facility of nominal 35-t/year capacity utilizing the latest technology developed in fabrication programs at WHC and in reprocessing at ORNL. The concept was based on many years of work at both sites and extensive design studies of prior years

Concept for a small, colocated fuel cycle facility for oxide breeder fuels

International Nuclear Information System (INIS)

Burch, W.D.; Lerch, R.E.; Stradley, J.G.

1987-01-01

As part of a United States Department of Energy (USDOE) program to examine innovative liquid-metal reactor (LMR) system designs over the past three years, the Oak Ridge National Laboratory (ORNL) and the Westinghouse Hanford Company (WHC) collaborated on studies of mixed oxide fuel cycle options. A principal effort was an advanced concept for a small integrated fuel cycle colocated with a 1300-MW(e) reactor station. The study provided a scoping design, capital and operating cost estimates, and a basis on which to proceed with implementation of such a facility if future plans so dictate. The facility integrated reprocessing, waste management, and refabrication functions in a single facility of nominal 35-t/year capacity utilizing the latest technology developed in fabrication programs at WHC and in reprocessing at ORNL. The concept was based on many years of work at both sites and extensive design studies of prior years

Proceedings of the 8th topical meeting on nuclear code development

International Nuclear Information System (INIS)

1993-03-01

The 8th Topical Meeting on Nuclear Code Development, organized by Committee on Reactor Physics and Nuclear Codes Committee of Japan Atomic Energy Research Institute (JAERI), was held at Tokai Research Establishment of JAERI, on 11th and 12th of November, 1992. In the meeting, 14 papers were presented on the topics of (1) the next generation nuclear reactor design system and (2) advances of the nuclear fuel reprocessing safety analysis codes. These papers are compiled in this proceedings. (author)

Supersymmetry: proceedings

International Nuclear Information System (INIS)

Brennan, E.C.

1985-07-01

Some lectures in these proceedings examine the theoretical basis for supersymmetry, recent developments in theories with compact dimensions, and experimental searches for supersymmetric signatures. Technologies are explored for obtaining very high energy electron-positron colliding beams. Separate abstracts were prepared for 35 papers in these conference proceedings

Proceedings of the 2000 U.S. DOE Hydrogen Program Review

Energy Technology Data Exchange (ETDEWEB)

NREL

2000-11-01

The 2000 US Department of Energy (DOE) Hydrogen Program Review was sponsored by the Office of Power Delivery Systems, Office of Power Technologies, US Department of Energy. The proceedings from this meeting serve as an important technology reference for the DOE Hydrogen Program. This document contains technical progress reports on research and technology validation projects funded by the DOE Hydrogen Program in Fiscal Year 2000. The growth of fuel cell technology will provide a basis for the establishment of the hydrogen option into both transportation and electricity supply markets.

Fusion Technology 1996. Proceedings. Volume 1 and 2

International Nuclear Information System (INIS)

Varandas, C.; Serra, F.

1997-01-01

The objective of these proceedings was to provide a platform for the exchange of information on the design, construction and operation of fusion experiments. The technology which is being developed for the next step devices and fusion reactors was also covered. Sections in volume 1 concern (A) first wall, divertors and vacuum systems; (B) plasma heating and control; (C) plasma engineering and control; and (D) experimental systems. The sections in volume 2 deal with (E) magnet and related power supplies; (F) fuel cycle and tritium processing systems; (G) blanket technology/materials; (H) assembly, remote handling and waste management and storage; and (I) safety and environment, and reactor studies

Proceedings of the American Power Conference. Volume 58-II

International Nuclear Information System (INIS)

McBride, A.E.

1996-01-01

This book is part 2 of the proceedings of the American Power Conference, Technology for Competition and Globalization, 1996. The topics of the papers include structural plant design; challenges of the global marketplace; thermal hydraulic methods for nuclear power plant safety and operation; decontamination and decommissioning; competitive operations and maintenance; fuel opportunities; cooling; competitive power pricing; operations; transformers; relays; plant controls; training to meet the competitive future; burning technologies; ash and byproducts utilization; advanced systems; computer tools for plant design; globalization of power; power system protection and power quality; life extension; grounding; and transmission line equipment

Supersymmetry: proceedings

Energy Technology Data Exchange (ETDEWEB)

Brennan, E.C. (ed.)

1985-07-01

Some lectures in these proceedings examine the theoretical basis for supersymmetry, recent developments in theories with compact dimensions, and experimental searches for supersymmetric signatures. Technologies are explored for obtaining very high energy electron-positron colliding beams. Separate abstracts were prepared for 35 papers in these conference proceedings. (LEW)

International nuclear fuel cycle fact book

Energy Technology Data Exchange (ETDEWEB)

Leigh, I.W.

1988-01-01

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source or information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained has been obtained from nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops; and so forth. Sources do not agree completely with each other, and the data listed herein does not reflect any one single source but frequently is consolidation/combination of information. Lack of space as well as the intent and purpose of the Fact Book limit the given information to that pertaining to the Nuclear Fuel Cycle and to data considered of primary interest or most helpful to the majority of users.

International nuclear fuel cycle fact book

International Nuclear Information System (INIS)

Leigh, I.W.

1988-01-01

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source or information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained has been obtained from nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops; and so forth. Sources do not agree completely with each other, and the data listed herein does not reflect any one single source but frequently is consolidation/combination of information. Lack of space as well as the intent and purpose of the Fact Book limit the given information to that pertaining to the Nuclear Fuel Cycle and to data considered of primary interest or most helpful to the majority of users

International nuclear fuel cycle fact book

International Nuclear Information System (INIS)

Leigh, I.W.; Lakey, L.T.; Schneider, K.J.; Silviera, D.J.

1987-01-01

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained has been obtained from nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops; and so forth. Sources do not agree completely with each other, and the data listed herein does not reflect any one single source but frequently is a consolidation/combination of information. Lack of space as well as the intent and purpose of the Fact Book limit the given information to that pertaining to the Nuclear Fuel Cycle and to data considered of primary interest or most helpful to the majority of users

Advanced fuel pellet materials and designs for water cooled reactors. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

2004-10-01

This meeting was the second IAEA meeting on this subject. The first was held in 1996 in Tokyo, Japan. They are all part of a cooperative effort through the Technical Working Group on Water Reactor Fuel Performance and Technology (TWGFPT) of IAEA, with a series of three further meetings organized by CEA, France and co-sponsored by the IAEA and OECD/NEA. In the seven years since the first meeting took place, the demands on fuel duties have increased, with higher burnup, longer fuel cycles and higher temperatures. This places additional demands on fuel performance to comply with safety requirements. Criteria relative to fuel components, i.e. pellets and fuel rod column, require limiting of fission gas release and pellet-cladding interaction (PCI). This means that fuel components should maintain the composite of rather contradictory properties from the beginning until the end of its in-pile operation. Fabrication and design tools are available to influence, and to some extent, to ensure desirable in-pile fuel properties. Discussion of these tools was one of the objectives of the meeting. The second objective was the analysis of fuel characteristics at high burnup and the third and last objective was the discussion of specific feature of MOX and urania gadolinia fuels. Sixty specialists in the field of fuel fabrication technology attended the meeting from 18 countries. Twenty-five papers were presented in five sessions covering all relevant topics from the practices and modelling of fuel fabrication technology to its optimization. Eight papers were presented in session 'Optimization of fuel fabrication technology' which all were devoted to fuel fabrication technology. They mostly treated methods for optimizing fuel manufacturing processes, but gave also a good overview on nuclear fabrication needs and capabilities in different countries. During Session 'UO 2 , MOX and UO 2 -Gd 2 O 3 pellets with additives', six papers were presented in this session, which dealt mainly

Methanol supply issues for alternative fuels demonstration programs

International Nuclear Information System (INIS)

Teague, J.M.; Koyama, K.K.

1995-01-01

This paper surveys issues affecting the supply of fuel-grade methanol for the California Energy Commission's alternative fuels demonstration programs and operations by other public agencies such as transit and school districts. Establishing stable and reasonably priced sources of methanol (in particular) and of alternative fuels generally is essential to their demonstration and commercialization. Development both of vehicle technologies and of fuel supply and distribution are complementary and must proceed in parallel. However, the sequence of scaling up supply and distribution is not necessarily smooth; achievement of volume thresholds in demand and through-put of alternative fuels are marked by different kinds of challenges. Four basic conditions should be met in establishing a fuel supply: (1) it must be price competitive with petroleum-based fuels, at least when accounting for environmental and performance benefits; (2) bulk supply must meet volumes required at each phase; necessitating resilience among suppliers and a means of designating priority for high value users; (3) distribution systems must be reliable, comporting with end users' operational schedules; (4) volatility in prices to the end user for the fuel must be minimal. Current and projected fuel volumes appear to be insufficient to induce necessary economies of scale in production and distribution for fuel use. Despite their benefits, existing programs will suffer absent measures to secure economical fuel supplies. One solution is to develop sources that are dedicated to fuel markets and located within the end-use region

Proceedings of the Canadian Nuclear Society 2. international conference on radioactive waste management

International Nuclear Information System (INIS)

1986-01-01

These proceedings contain 136 papers on waste management from 19 countries. An index of the delegates and their affiliations is included. Emphasis was laid on the Canadian program for geologic disposal in hard rock. Sessions dealt with the following: storage and disposal, hydrogeology and geochemistry, transportation, buffers and backfill, public attitudes, tailings, site investigations and geomechanics, concrete, economics, licensing, matrix materials and container design, durability of fuel, biosphere modelling, radioactive waste processing, and future options

Aquatic Species Program review: proceedings of principal investigators meeting

Energy Technology Data Exchange (ETDEWEB)

1985-06-01

The purpose of the Aquatic Species Program is to improve the productivity, conversion to fuels, and cost efficiency of aquatic plant culture technologies. The emphasis of the program is on developing a mass culture technology for cultivating oil-yielding microalgae in the American southwest. A technical and economic analysis indicated that such a concept would be feasible if (1) lipid yields from microalgae are improved, (2) there is sufficient saline water for large-scale development, and (3) microalgal lipids can be economically converted to conventional fuels. It was determined that fuels from microalgal lipids presented better options than converting the microalgal biomass to either alcohols or methane. All lipids can potentially be catalytically converted to gasoline, or the fatty acids can be converted to substitute diesel fuels. The Southwest has the necessary low, flat, underutilized lands, and carbon dioxide is available from either natural deposits or flue gas from industrial plants. The amount of saline water available will probably determine how much fuel can be produced from aquatic species, and this question should be answered during 1985. The largest constraint of this technology is the economical production of an oil-rich microalgal feedstock. The agenda for the review was divided into four sections: species selection and characterization, applied physiological studies, outdoor mass cultivation, and systems design and analysis. Papers from these presentations are included in these proceedings. Program advances were reported in the areas of species collection and selection, modulated light physiology, mass culture yields, harvesting of microalgae, mass culture facility design and analysis, and assessments on fuel options from microalgae. Separate abstracts have been prepared for each paper for inclusion in the Energy Data Base.

Implementation of burnup credit in spent fuel management systems. Proceedings of a technical committee meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-08-01

The purpose of this Technical Committee Meeting was to explore the status of international activities related to the use of burnup credit for spent fuel applications. This was the second major meeting on the issues of burnup credit for spent fuel management systems held since the IAEA began to monitor the uses of burnup credit in spent fuel management systems in 1997. Burnup credit for wet and dry storage systems is needed in many Member States to allow for increased initial fuel enrichment, and to increase the storage capacity and thus to avoid the need for extensive modifications of the spent fuel management systems involved. This document contains 31 individual papers presented at the Meeting; each of the papers was indexed separately.

Implementation of burnup credit in spent fuel management systems. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

2001-08-01

The purpose of this Technical Committee Meeting was to explore the status of international activities related to the use of burnup credit for spent fuel applications. This was the second major meeting on the issues of burnup credit for spent fuel management systems held since the IAEA began to monitor the uses of burnup credit in spent fuel management systems in 1997. Burnup credit for wet and dry storage systems is needed in many Member States to allow for increased initial fuel enrichment, and to increase the storage capacity and thus to avoid the need for extensive modifications of the spent fuel management systems involved. This document contains 31 individual papers presented at the Meeting; each of the papers was indexed separately

Ignition! Fueling the Education Explosion: Proceedings of Conference 1 (Cleveland, Ohio, May 5-6, 1983).

Science.gov (United States)

Gardner, Mary, Ed.; Reed-Mundell, Charlene, Ed.

These proceedings contain four presentations and other materials from a conference to provide public schools with information about change so they can take a leadership role in educating for the future. The opening address (Richard Berendzen) discusses changes affecting education and changes in education. "Megatrends: Implications for Education…

BNFL pushes fuel production into the 21st century

International Nuclear Information System (INIS)

Odell, Mark.

1992-01-01

When the New Oxide Fuels Complex (NOFC) begins commercial production in May 1995, its operators will have one of the world's most advanced fuel production facilities, designed to compete on international markets by using the latest technology and exploiting economies of scale. British Nuclear Fuels (BNFL's) multi-million pound investment in its Springfields fuel operation is a bold move, aimed at gaining a greater share of the oxide fuel business worldwide. The complex is designed to achieve fuel cost savings and increase the site's manufacturing capacity. The building itself will bring all current fuel production operations at Springfields under one roof, merging five plants into one. Automation will ensure further economies through the use of automated guided vehicles (AGVs) for product transfer, walking beam furnaces for pellet sintering and on-line inspection and handling of pellets and pins. The use of a binderless route for AGR (advanced gas-cooled reactor) fuel means much of the manufacturing process for both AGR and PWR (pressurised water reactor) fuels will proceed on a single line, thereby reducing the fixed costs of both fuels. Two other features which contribute to cost savings are production flexibility which allows both non-irradiated and oxide reprocessed materials to follow the same route and longer kilns which increase the throughput. It is estimated that overall NOFC will reduce fuel manufacturing costs by some 40%. (author)

Advanced methods of process/quality control in nuclear reactor fuel manufacture. Proceedings of a technical committee meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

Nuclear fuel plays an essential role in ensuring the competitiveness of nuclear energy and its acceptance by the public. The economic and market situation is not favorable at present for nuclear fuel designers and suppliers. The reduction in fuel prices (mainly to compete with fossil fuels) and in the number of fuel assemblies to be delivered to customers (mainly due to burnup increase) has been offset by the rising number of safety and other requirements, e.g. the choice of fuel and structural materials and the qualification of equipment. In this respect, higher burnup and thermal rates, longer fuel cycles and the use of MOX fuels are the real means to improve the economics of the nuclear fuel cycle as a whole. Therefore, utilities and fuel vendors have recently initiated new research and development programmes aimed at improving fuel quality, design and materials to produce robust and reliable fuel for safe and reliable reactor operation more demanding conditions. In this connection, improvement of fuel quality occupies an important place and this requires continuous effort on the part of fuel researchers, designers and producers. In the early years of commercial fuel fabrication, emphasis was given to advancements in quality control/quality assurance related mainly to the product itself. Now, the emphasis is transferred to improvements in process control and to implementation of overall total quality management (TQM) programmes. In the area of fuel quality control, statistical methods are now widely implemented, replacing 100% inspection. The IAEA, recognizing the importance of obtaining and maintaining high standards in fuel fabrication, has paid particular attention to this subject. In response to the rapid progress in development and implementation of advanced methods of process/quality control in nuclear fuel manufacture and on the recommendation of the International Working Group on Water Reactor Fuel Performance and Technology, the IAEA conducted a

Advanced methods of process/quality control in nuclear reactor fuel manufacture. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

2000-07-01

Nuclear fuel plays an essential role in ensuring the competitiveness of nuclear energy and its acceptance by the public. The economic and market situation is not favorable at present for nuclear fuel designers and suppliers. The reduction in fuel prices (mainly to compete with fossil fuels) and in the number of fuel assemblies to be delivered to customers (mainly due to burnup increase) has been offset by the rising number of safety and other requirements, e.g. the choice of fuel and structural materials and the qualification of equipment. In this respect, higher burnup and thermal rates, longer fuel cycles and the use of MOX fuels are the real means to improve the economics of the nuclear fuel cycle as a whole. Therefore, utilities and fuel vendors have recently initiated new research and development programmes aimed at improving fuel quality, design and materials to produce robust and reliable fuel for safe and reliable reactor operation more demanding conditions. In this connection, improvement of fuel quality occupies an important place and this requires continuous effort on the part of fuel researchers, designers and producers. In the early years of commercial fuel fabrication, emphasis was given to advancements in quality control/quality assurance related mainly to the product itself. Now, the emphasis is transferred to improvements in process control and to implementation of overall total quality management (TQM) programmes. In the area of fuel quality control, statistical methods are now widely implemented, replacing 100% inspection. The IAEA, recognizing the importance of obtaining and maintaining high standards in fuel fabrication, has paid particular attention to this subject. In response to the rapid progress in development and implementation of advanced methods of process/quality control in nuclear fuel manufacture and on the recommendation of the International Working Group on Water Reactor Fuel Performance and Technology, the IAEA conducted a

Technology and use of lignite. Proceedings of the tenth biennial lignite symposium

Energy Technology Data Exchange (ETDEWEB)

Kube, W. R.; Gronhovd, G. H. [comps.

1979-01-01

The symposium on the technology and use of lignite was sponsored by the US Department of Energy and the University of North Dakota, and held at Grand Forks, North Dakota, May 30-31, 1979. Twenty-one papers from the proceedings of this tenth biennial lignite symposium have been entered into EDB and ERA and three also into EAPA. The papers discuss lignite deposits in the USA, mining plans, gasification and in-situ gasification, and combustion in fossil-fuel power plants. (LTN)

State of the art: Multi-fuel reformers for automotive fuel cell applications. Problem identification and research needs

Energy Technology Data Exchange (ETDEWEB)

Westerholm, R. [Stockholm Univ. (Sweden). Dept. of Analytical Chemistry; Pettersson, L.J. [Royal Inst. of Tech., Stockholm (Sweden). Dept. of Chemical Engineering and Technology

1999-12-01

On an assignment from the Transport and Communications Research Board (KFB) a literature study and a study trip to the USA and Great Britain have been performed. The literature study and the study trip was made during late spring and autumn 1999.The purpose of the project was to collect available information about the chemical composition of the product gas from a multi-fuel reformer for a fuel cell vehicle. It was furthermore to identify problems and research needs. The report recommends directions for future major research efforts. The results of the literature study and the study trip led to the following general conclusions: With the technology available today it does not seem feasible to develop a highly efficient and reliable multi-fuel reformer for automotive applications, i. e. for applications where all types of fuels ranging from natural gas to heavy diesel fuels can be used. The potential for developing a durable and reliable system is considerably higher if dedicated fuel reformers are used.The authors propose that petroleum-derived fuels should be designed for potential use in mobile fuel cell applications. In the present literature survey and the site visit discussions we found that there are relatively low emissions from fuel cell engines compared to internal combustion engines. However, the major research work on reformers/fuel cells have been performed during steady-state operation. Emissions during start-up, shutdown and transient operation are basically unknown and must be investigated in more detail. The conclusions and findings in this report are based on open/available information, such as discussions at site visits, reports, scientific publications and symposium proceedings.

Fuel cycle cost comparisons with oxide and silicide fuels

Energy Technology Data Exchange (ETDEWEB)

Matos, J E; Freese, K E [RERTR Program, Argonne National Laboratory (United States)

1983-09-01

This paper addresses fuel cycle cost comparisons for a generic 10 MW reactor with HEU aluminide fuel and with LEU oxide and silicide fuels in several fuel element geometries. The intention of this study is to provide a consistent assessment of various design options from a cost point of view. The status of the development and demonstration of the oxide and silicide fuels are presented in several papers in these proceedings. Routine utilization of these fuels with the uranium densities considered here requires that they are successfully demonstrated and licensed. Thermal-hydraulic safety margins, shutdown margins, mixed cores, and transient analyses are not addressed here, but analyses of these safety issues are in progress for a limited number of the most promising design options. Fuel cycle cost benefits could result if a number of reactors were to utilize fuel elements with the same number or different numbers of the same standard fuel plate. Data is presented to quantify these potential cost benefits. This analysis shows that there are a number of fuel element designs using LEU oxide or silicide fuels that have either the same or lower total fuel cycle costs than the HEU design. Use of these fuels with the uranium densities considered requires that they are successfully demonstrated and licensed. All safety criteria for the reactor with these fuel element designs need to be satisfied as well. With LEU oxide fuel, 31 g U/cm{sup 3} 1 and 0.76 mm--thick fuel meat, elements with 18-22 plates 320-391 g {sup 235}U) result in the same or lower total costs than with the HEU element 23 plates, 280 g {sup 235}U). Higher LEU loadings (more plates per element) are needed for larger excess reactivity requirements. However, there is little cost advantage to using more than 20 of these plates per element. Increasing the fuel meat thickness from 0.76 mm to 1.0 mm with 3.1 g U/cm{sup 3} in the design with 20 plates per element could result in significant cost reductions if the

FAILED FUEL DISPOSITION STUDY

International Nuclear Information System (INIS)

THIELGES, J.R.

2004-01-01

In May 2004 alpha contamination was found on the lid of the pre-filter housing in the Sodium Removal Ion Exchange System during routine filter change. Subsequent investigation determined that the alpha contamination likely came from a fuel pin(s) contained in an Ident-69 (ID-69) type pin storage container serial number 9 (ID-69-9) that was washed in the Sodium Removal System (SRS) in January 2004. Because all evidence indicated that the wash water interacted with the fuel, this ID49 is designated as containing a failed fuel pin with gross cladding defect and was set aside in the Interim Examination and Maintenance (IEM) Cell until it could be determined how to proceed for long term dry storage of the fuel pin container. This ID49 contained fuel pins from the driver fuel assembly (DFA) 16392, which was identified as a Delayed Neutron Monitor (DNM) leaker assembly. However, this DFA was disassembled and the fuel pin that was thought to be the failed pin was encapsulated and was not located in this ID49 container. This failed fuel disposition study discusses two alternatives that could be used to address long term storage for the contents of ID-69-9. The first alternative evaluated utilizes the current method of identifying and storing DNM leaker fuel pin(s) in tubes and thus, verifying that the alpha contamination found in the SRS came from a failed pin in this pin container. This approach will require unloading selected fuel pins from the ID-69, visually examining and possibly weighing suspect fuel pins to identify the failed pin(s), inserting the failed pin(s) in storage tubes, and reloading the fuel pins into ID49 containers. Safety analysis must be performed to revise the 200 Area Interim Storage Area (ISA) Final Safety Analysis Report (FSAR) (Reference 1) for this fuel configuration. The second alternative considered is to store the failed fuel as-is in the ID-69. This was evaluated to determine if this approach would comply with storage requirements. This

FAILED FUEL DISPOSITION STUDY

Energy Technology Data Exchange (ETDEWEB)

THIELGES, J.R.

2004-12-20

In May 2004 alpha contamination was found on the lid of the pre-filter housing in the Sodium Removal Ion Exchange System during routine filter change. Subsequent investigation determined that the alpha contamination likely came from a fuel pin(s) contained in an Ident-69 (ID-69) type pin storage container serial number 9 (ID-69-9) that was washed in the Sodium Removal System (SRS) in January 2004. Because all evidence indicated that the wash water interacted with the fuel, this ID49 is designated as containing a failed fuel pin with gross cladding defect and was set aside in the Interim Examination and Maintenance (IEM) Cell until it could be determined how to proceed for long term dry storage of the fuel pin container. This ID49 contained fuel pins from the driver fuel assembly (DFA) 16392, which was identified as a Delayed Neutron Monitor (DNM) leaker assembly. However, this DFA was disassembled and the fuel pin that was thought to be the failed pin was encapsulated and was not located in this ID49 container. This failed fuel disposition study discusses two alternatives that could be used to address long term storage for the contents of ID-69-9. The first alternative evaluated utilizes the current method of identifying and storing DNM leaker fuel pin(s) in tubes and thus, verifying that the alpha contamination found in the SRS came from a failed pin in this pin container. This approach will require unloading selected fuel pins from the ID-69, visually examining and possibly weighing suspect fuel pins to identify the failed pin(s), inserting the failed pin(s) in storage tubes, and reloading the fuel pins into ID49 containers. Safety analysis must be performed to revise the 200 Area Interim Storage Area (ISA) Final Safety Analysis Report (FSAR) (Reference 1) for this fuel configuration. The second alternative considered is to store the failed fuel as-is in the ID-69. This was evaluated to determine if this approach would comply with storage requirements. This

Materials for advanced power engineering 2010. Proceedings

Energy Technology Data Exchange (ETDEWEB)

Lecomte-Beckers, Jacqueline; Contrepois, Quentin; Beck, Tilmann; Kuhn, Bernd (eds.)

2010-07-01

The 9th Liege Conference on ''Materials for Advanced Power Engineering'' presents the results of the materials related COST Actions 536 ''Alloy Development for Critical Components of Environmentally Friendly Power Plants'' and 538 ''High Temperature Plant Lifetime Extension''. In addition, the broad field of current materials research perspectives for high efficiency, low- and zero- emission power plants and new energy technologies for the next decades are reported. The Conference proceedings are structured as follows: 1. Materials for advanced steam power plants; 2. Gas turbine materials; 3. Materials for nuclear fission and fusion; 4. Solid oxide fuel cells; 5. Corrosion, thermomechanical fatigue and modelling; 6. Zero emission power plants.

Development of Melting Crucible Materials of Metallic Fuel Slug for SFR

International Nuclear Information System (INIS)

Kim, K. H.; Lee, C. T.; Oh, S. J.; Kim, S. K.; Lee, C. B.; Ko, Y. M.; Woo, W. M.

2010-01-01

The fabrication process of metallic fuel for SFR(sodium fast reactor) of Generation-IV candidate reactors is composed of the fabrication of fuel pin, fuel rod, and fuel assembly. The key technology of the fabrication process for SFR can be referred to the fabrication technology of fuel pin. As SFR fuel contains MA(minor actinide) elements proceeding the recycling of actinide elements, it is so important to extinguish MA during irradiation in SFR, included in nuclear fuel through collection of volatile MA elements during fabrication of fuel pin. Hence, it is an imminent circumstance to develop the fabrication process of fuel pin. This report is an state-of art report related to the characteristics of irradiation performance for U-Zr-Pu metallic fuel, and the apparatus and the technology of conventional injection casting process. In addition, to overcome the drawbacks of the conventional injection casting and the U-Zr-Pu fuel, new fabrication technologies such as the gravity casting process, the casting of fuel pin to metal-barrier mold, the fabrication of particulate metallic fuel utilizing centrifugal atomization is surveyed and summarized. The development of new U-10Mo-X metallic fuel as nuclear fuel having a single phase in the temperature range between 550 and 950 .deg. C, reducing the re-distribution of the fuel elements and improving the compatibility between fuel and cladding, is also surveyed and summarized

Proceedings of the Topical Meeting on the safety of nuclear fuel cycle intermediate storage facilities

International Nuclear Information System (INIS)

1998-01-01

The CSNI Working Group on Fuel Cycle Safety held an International Topical Meeting on safety aspects of Intermediate Storage Facilities in Newby Bridge, England, from 28 to 30 October 1997. The main purpose of the meeting was to provide a forum for the exchange of information on the technical issues on the safety of nuclear fuel cycle facilities (intermediate storage). Titles of the papers are: An international view on the safety challenges to interim storage of spent fuel. Interim storage of intermediate and high-level waste in Belgium: a description and safety aspects. Encapsulated intermediate level waste product stores at Sellafield. Safety of interim storage facilities of spent fuel: the international dimension and the IAEA's activities. Reprocessing of irradiated fuel and radwaste conditioning at Belgoprocess site: an overview. Retrieval of wastes from interim storage silos at Sellafield. Outline of the fire and explosion of the bituminization facility and the activities of the investigation committee (STAIJAERI). The fire and explosion incident of the bituminization facility and the lessons learned from the incident. Study on the scenario of the fire incident and related analysis. Study on the scenario of the explosion incident and related analysis. Accident investigation board report on the May 14, 1997 chemical explosion at the plutonium reclamation facility, Hanford site, Richland, Washington. Dry interim storage of spent nuclear fuel elements in Germany. Safe and effective system for the bulk receipt and storage of light water reactor fuel prior to reprocessing. Receiving and storage of glass canisters at vitrified waste storage center of Japan Nuclear Fuel Ltd. Design and operational experience of dry cask storage systems. Sellafield MOX plant; Plant safety design (BNFL). The assessment of fault studies for intermediate term waste storage facilities within the UK nuclear regulatory regime. Non-active and active commissioning of the thermal oxide

Demonstration of a transportable storage system for spent nuclear fuel

International Nuclear Information System (INIS)

Shetler, J.R.; Miller, K.R.; Jones, R.E.

1993-01-01

The purpose of this paper is to discuss the joint demonstration project between the Sacramento Municipal Utility District (SMUD) and the US Department of Energy (DOE) regarding the use of a transportable storage system for the long-term storage and subsequent transport of spent nuclear fuel. SMUD's Rancho Seco nuclear generating station was shut down permanently in June 1989. After the shutdown, SMUD began planning the decommissioning process, including the disposition of the spent nuclear fuel. Concurrently, Congress had directed the Secretary of Energy to develop a plan for the use of dual-purpose casks. Licensing and demonstrating a dual-purpose cask, or transportable storage system, would be a step toward achieving Congress's goal of demonstrating a technology that can be used to minimize the handling of spent nuclear fuel from the time the fuel is permanently removed from the reactor through to its ultimate disposal at a DOE facility. For SMUD, using a transportable storage system at the Rancho Seco Independent Spent-Fuel Storage Installation supports the goal of abandoning Rancho Seco's spent-fuel pool as decommissioning proceeds

Proceedings of international conference on peaceful uses of atomic energy - 2009. V. 2

International Nuclear Information System (INIS)

Reddy, A.V.R.; Venugopal, V.; Sinha, R.K.; Banerjee, S.

2009-01-01

The proceedings contains 330 contributed papers from scientists, technologists and policy makers from India and abroad. These papers are categorized into nine themes: Resources, Reactor Systems, Advance Reactors, Fuel Cycle, Reactor Materials, Fast Reactors and Accelerator Driven Subcritical Systems, Food and Agriculture, Radiotherapy and Medicine, and Nuclear Instrumentation.This volume covers papers on the topics like reactor materials, fast reactor and ADSS (FRA), food and agriculture, radiotherapy and medicine and nuclear instrumentation. Papers relevant to INIS are indexed separately

Fabrication and Testing of CERMET Fuel Materials for Nuclear Thermal Propulsion

Science.gov (United States)

Hickman, Robert; Broadway, Jeramie; Mireles, Omar

2012-01-01

A first generation Nuclear Cryogenic Propulsion Stage (NCPS) based on Nuclear Thermal Propulsion (NTP) is currently being developed for Advanced Space Exploration Systems. The overall goal of the project is to address critical NTP technology challenges and programmatic issues to establish confidence in the affordability and viability of NTP systems. The current technology roadmap for NTP identifies the development of a robust fuel form as a critical near term need. The lack of a qualified nuclear fuel is a significant technical risk that will require a considerable fraction of program resources to mitigate. Due to these risks and the cost for qualification, the development and selection of a primary fuel must begin prior to Authority to Proceed (ATP) for a specific mission. The fuel development is a progressive approach to incrementally reduce risk, converge the fuel materials, and mature the design and fabrication process of the fuel element. A key objective of the current project is to advance the maturity of CERMET fuels. The work includes fuel processing development and characterization, fuel specimen hot hydrogen screening, and prototypic fuel element testing. Early fuel materials development is critical to help validate requirements and fuel performance. The purpose of this paper is to provide an overview and status of the work at Marshall Space Flight Center (MSFC).

Assessment of nitrogen as an atmosphere for dry storage of spent LWR fuel

International Nuclear Information System (INIS)

Gilbert, E.R.; Knox, C.A.; White, G.D.

1985-09-01

Interim dry storage of spent light-water reactor (LWR) fuel is being developed as a licensed technology in the United States. Because it is anticipated that license agreements will specify dry storage atmospheres, the behavior of spent LWR fuel in a nitrogen atmosphere during dry storage was investigated. In particular, the thermodynamics of reaction of nitrogen compounds (expected to form in the cover gas during dry storage) and residual impurities (such as moisture and oxygen) with Zircaloy cladding and with spent fuel at sites of cladding breaches were examined. The kinetics of reaction were not considered it was assumed that the 20 to 40 years of interim dry storage would be sufficient for reactions to proceed to completion. The primary thermodynamics reactants were found to be NO 2 , N 2 O, H 2 O 2 , and O 2 . The evaluation revealed that the limited inventories of these reactants produced by the source terms in hermetically sealed dry storage systems would be too low to cause significant spent fuel degradation. Furthermore, the oxidation of spent fuel to degrading O/U ratios is unlikely because the oxidation potential in moist nitrogen limits O/U ratios to values less than UO/sub 2.006/ (the equilibrium stoichiometric form in equilibrium with moist nitrogen). Tests were performed with bare spent UO 2 fuel and nonirradiated UO 2 pellets (with no Zircaloy cladding) in a nitrogen atmosphere containing moisture concentrations greater than encountered under dry storage conditions. These tests were performed for at least 1100 h at temperatures as high as 380 0 C, where oxidation reactions proceed in a matter of minutes. No visible degradation was detected, and weight changes were negligible

Recycling of plutonium and uranium in water reactor fuel. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

1997-05-01

The Technical Committee Meeting on Recycling of Plutonium and Uranium in Water Reactor Fuel was recommended by the International Working Group on Fuel Performance and Technology (IWGFPT). Its aim was to obtain an overall picture of MOX fabrication capacity and technology, actual performance of this kind of fuel, and ways explored to dispose of the weapons grade plutonium. The subject of this meeting had been reviewed by the International Atomic Energy Agency every 5 to 6 years and for the first time the problem of weapons grade plutonium disposal was included. The papers presented provide a summary of experience on MOX fuel and ongoing research in this field in the participating countries. The meeting was hosted by British Nuclear Fuels plc, at Newby Bridge, United Kingdom, from 3 to 7 July 1995. Fifty-six participants from twelve countries or international organizations took part. Refs, figs, tabs

Proceedings of the eleventh annual conference on fossil energy materials

Energy Technology Data Exchange (ETDEWEB)

Judkins, R.R. [comp.

1997-12-01

The objective of the Advanced Research and Technology Development (AR and TD) Materials Program is to conduct research and development on materials for longer-term fossil energy applications as well as for generic needs of various fossil fuel technologies. These proceedings contain 34 papers organized under the following topical sections: Ceramic composites and functional materials; Ceramics, new alloys, and functional materials; and New alloys. Also included is a summary of a workshop on materials issues in low emission boilers and in high efficiency coal-fired cycles. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

Proceedings of the second US Department of Energy environmental control symposium. Volume 1. Fossil energy

Energy Technology Data Exchange (ETDEWEB)

None

1980-06-01

These proceedings document the presentations given at the Second Environmental Control Symposium. Symposium presentations highlighted environmental control activities which span the entire DOE. Volume I contains papers relating to coal preparation, oil shales, coal combustion, advanced coal utilization (fluidized bed combustion, MHD generators, OCGT, fuel cells), coal gasification, coal liquefaction, and fossil resource extraction (enhanced recovery). Separate abstracts for individual papers are prepared for inclusion in the Energy Data Base. (DMC)

Rokkashomura: debut of the nuclear fuel cycle business

International Nuclear Information System (INIS)

Anon.

1991-01-01

Japan Nuclear Fuel Industries and local governments signed the safety agreement, and the work began to initiate the operation of a uranium enrichment plant. In this way, the national Rokkashomura project to be constructed with the total cost of 1.2 trillion yen marked the debut of nuclear fuel cycle business in Japan. The public hearing concerning the low level radioactive waste storage facility was finished. However, a fuel reprocessing plant has not advanced since the national government did not clarify the policy for the management of high level rad-waste from the plant. Gubernatorial election was the best thing to happen for the public acceptance, and the local opposition movement lost steam. The operation of the uranium enrichment plant is to begin next January, and the construction of the low level waste storage facility proceeds on schedule. Regarding the fuel reprocessing plant, the public hearing is to be held in autumn, but it faces difficulties. The siting of nuclear fuel cycle facilities has already produced benefits for the local economy. 18 business establishments representing 15 firms have so far decided to open in Aomori Prefecture. JNFI and JNFS began the specific study for merger. (K.I.)

Proceedings of the sixteenth biennial low-rank fuels symposium

International Nuclear Information System (INIS)

1991-01-01

Low-rank coals represent a major energy resource for the world. The Low-Rank Fuels Symposium, building on the traditions established by the Lignite Symposium, focuses on the key opportunities for this resource. This conference offers a forum for leaders from industry, government, and academia to gather to share current information on the opportunities represented by low-rank coals. In the United States and throughout the world, the utility industry is the primary user of low-rank coals. As such, current experiences and future opportunities for new technologies in this industry were the primary focuses of the symposium

Proceedings of the sixteenth biennial low-rank fuels symposium

Energy Technology Data Exchange (ETDEWEB)

1991-01-01

Low-rank coals represent a major energy resource for the world. The Low-Rank Fuels Symposium, building on the traditions established by the Lignite Symposium, focuses on the key opportunities for this resource. This conference offers a forum for leaders from industry, government, and academia to gather to share current information on the opportunities represented by low-rank coals. In the United States and throughout the world, the utility industry is the primary user of low-rank coals. As such, current experiences and future opportunities for new technologies in this industry were the primary focuses of the symposium.

Biogas and Fuel Cells Workshop Summary Report: Proceedings from the Biogas and Fuel Cells Workshop, Golden, Colorado, June 11-13, 2012

Energy Technology Data Exchange (ETDEWEB)

2013-01-01

The U.S. Department of Energy (DOE) National Renewable Energy Laboratory (NREL) held a Biogas and Fuel Cells Workshop June 11-13, 2012, in Golden, Colorado, to discuss biogas and waste-to-energy technologies for fuel cell applications. The overall objective was to identify opportunities for coupling renewable biomethane with highly efficient fuel cells to produce electricity; heat; combined heat and power (CHP); or combined heat, hydrogen and power (CHHP) for stationary or motive applications. The workshop focused on biogas sourced from wastewater treatment plants (WWTPs), landfills, and industrial facilities that generate or process large amounts of organic waste, including large biofuel production facilities (biorefineries).

Advanced post-irradiation examination techniques for water reactor fuel. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

2002-03-01

The purpose of the meeting was to provide and overview of the status of post-irradiation examination (PIE) techniques for water cooled reactor fuel assemblies and their components with emphasis given to advanced PIE techniques applied to high burnup fuel. Papers presented at the meeting described progress obtained in non-destructive (e.g. dimensional measurements, oxide layer thickness measurements, gamma scanning and tomography, neutron and X-ray radiography, etc.) and destructive PIE techniques (e.g. microstructural studies, elemental and isotopic analysis, measurement of physical and mechanical properties, etc.) used for investigation of water reactor fuel. Recent practice in high burnup fuel investigation revealed the importance of advanced PIE techniques, such as 3-D tomography, secondary ion mass spectrometry, laser flash, high resolution transmission and scanning electron microscopy, image analysis in microstructural studies, for understanding mechanisms of fuel behaviour under irradiation. Importance and needs for in-pile irradiation of samples and rodlets in instrumented rigs were also discussed. This TECDOC contains 20 individual papers presented at the meeting; each of the papers has been indexed separately

Towards a Swedish repository for spent fuel

International Nuclear Information System (INIS)

Ahlstroem, P.-E.

1997-01-01

Nuclear power is producing electricity for the benefit of society but is also leaving radioactive residues behind. It is our responsibility to handle these residues in a safe and proper manner. The development of a system for handling spent fuel from nuclear power plants has proceeded in steps. The same is true for the actual construction of facilities and will continue to be the case for the final repository for spent fuel and other types of long-lived wastes. The primary objective in constructing the repository will be to isolate and contain the radioactive waste. In case the isolation fails for some reason the multibarrier system should retain and retard the radionuclides that might come into contact with the groundwater. A repository is now planned to be built in two steps where the first step will include deposition of about 400 canisters with spent fuel. This first step should be finished in about 20 years from now and be followed by an extensive evaluation of the results from not only this particular step but also from the development of alternative routes before deciding on how to proceed. A special facility to encapsulate the spent fuel is also required. Such an encapsulation plant is proposed to be constructed as an extension of the existing interim storage CLAB. Finding a site for the repository is a critical issue in the implementation of any repository. The siting process started a few years ago and made some progress but is by no means yet completed. It will go on at least into the early part of the next decade. When the present nuclear power plants begin to be due for retirement there should also be some facilities in place to take permanent care of the long-lived radioactive residues. Progress in siting will be a prerequisite for success in our responsibility to make progress towards a safe permanent solution of the waste issue. (orig.)

Development and validation of the ENIGMA code for MOX fuel performance modelling

International Nuclear Information System (INIS)

Palmer, I.; Rossiter, G.; White, R.J.

2000-01-01

The ENIGMA fuel performance code has been under development in the UK since the mid-1980s with contributions made by both the fuel vendor (BNFL) and the utility (British Energy). In recent years it has become the principal code for UO 2 fuel licensing for both PWR and AGR reactor systems in the UK and has also been used by BNFL in support of overseas UO 2 and MOX fuel business. A significant new programme of work has recently been initiated by BNFL to further develop the code specifically for MOX fuel application. Model development is proceeding hand in hand with a major programme of MOX fuel testing and PIE studies, with the objective of producing a fuel modelling code suitable for mechanistic analysis, as well as for licensing applications. This paper gives an overview of the model developments being undertaken and of the experimental data being used to underpin and to validate the code. The paper provides a summary of the code development programme together with specific examples of new models produced. (author)

Proceedings of ISEC 2008, International Solvent Extraction Conference - Solvent Extraction: Fundamentals to Industrial Applications

International Nuclear Information System (INIS)

Moyer, Bruce A.

2008-01-01

The North American industry has employed major solvent-extraction processes to support a wide range of separations including but not limited to chemical, metallurgical, nuclear, biochemical, pharmaceutical, and petroleum applications. The knowledge enabling these separations has been obtained through fundamental studies in academe, government and industry. The International Solvent Extraction Conferences have been and continue to be a major gathering of scientists, engineers, operators, and vendors from around the world, who present new findings since the last meeting, exchange ideas, make business contacts, and conduct collegial discussions. The ISEC 2008 program emphasizes fundamentals to industrial applications of solvent extraction, particularly how this broad spectrum of activities is interconnected and has led to the implementation of novel processes. The oral and poster sessions have been organized into seven topics: Fundamentals; Novel Reagents, Materials and Techniques; Nuclear Fuel Reprocessing; Hydrometallurgy and Metals Extraction; Analytical and Preparative Applications; Biotechnology, Pharmaceuticals, Life-Science Products, and Organic Products; and Process Chemistry and Engineering. Over 350 abstracts were received, resulting in more than 260 manuscripts published in these proceedings. Five outstanding plenary presentations have been identified, with five parallel sessions for oral presentations and posters. In recognition of the major role solvent extraction (SX) plays in the hydrometallurgical and nuclear industries, these proceedings begin with sections focusing on hydrometallurgy, process chemistry, and engineering. More fundamental topics follow, including sections on novel reagents, materials, and techniques, featuring novel applications in analytical and biotechnology areas. Despite the diversity of topics and ideas represented, however, the primary focus of the ISEC community continues to be metals extraction. Four papers from these

Proceedings of the symposium Actinides 2006 - Basic Science, Applications and Technology

International Nuclear Information System (INIS)

Blobaum, Kerri J.M.; Chandler, Elaine A.; Havela, Ladislav; Maple, M. Brian; Neu, Mary P.

2007-01-01

These proceedings from the September 2006 symposium includes papers presented on experimental and modeling work with the intention of broadening understanding of the field of actinide research. Actinides have gained attention recently because of their roles in the threat of nuclear terrorism (e.g., 'dirty bombs') and the use of nuclear power to offset fossil fuel consumption. Actinide science is the study of the elements with atomic numbers in the range of 90 to 103, which includes uranium and plutonium. Beyond the well-known nuclear reactions of these heavy radioactive metals, the large electron clouds with 5f electrons in the outer shell yield fascinating and complex chemistries, crystal structures, and physical properties. Traditionally, actinide research has been divided among three scientific disciplines: chemistry (nuclear chemistry and radiochemistry); physics (condensed matter physics and electronic structure); and materials science (metallurgy). Modern actinide research, however, has become an interdisciplinary blend of these traditional fields, and it also incorporates developing fields such as environmental chemistry and superconductivity. Improved scientific understanding of actinides is needed for development of materials for actinide detection and nuclear fuels, and for safer management of nuclear waste. Recently, there has been a resurgence of actinide science at national laboratories and universities. The current multidisciplinary approach to actinide science lays the groundwork for understanding the connection between the 5f electronic structure and observed chemical reactions and physical properties such as structural phase transformations and novel ground states. This work provides many opportunities for new researchers in actinide science. These proceedings gather 25 selected papers among the 53 presentations given at this symposium

Nuclear Fuel Behaviour during Reactivity Initiated Accidents. Workshop Proceedings

International Nuclear Information System (INIS)

2010-01-01

A reactivity initiated accident (RIA) is a nuclear reactor accident that involves an unwanted increase in fission rate and reactor power. The power increase may damage the reactor core. The main objective of the workshop was to review the current status of the experimental and analytical studies of the fuel behavior during the RIA transients in PWR and BWR reactors and the acceptance criteria for RIA in use and under consideration. The workshop was organized in an opening session and 5 technical sessions: 1) Recent experimental results and experimental techniques used; 2) Modelling and Data Interpretation; 3) Code Assessment; 4) RIA Core Analysis and 5) Revision and application of safety criteria

Solid state protonic conductors II for fuel cells and sensors. Proceedings of the European workshop on solid state materials for low to medium temperature fuel cells and monitors, with special emphasis on proton conductors

Energy Technology Data Exchange (ETDEWEB)

Goodenough, J B; Jensen, J; Kleitz, M [eds.

1983-01-01

Solid electrolytes for chemical sensing, energy storage and conversion have been actively researched and developed since the early sixties. The zirconia fuel-cell electrolyser, the sodium-sulphur rechargeable battery, the oxygen sensor and lithium batteries can all be cited as significant developments from the field. Although of great potential the solid protonic conductors have somehow been ignored by comparison to the great interest that has been shown in, e.g., the lithium conductors. The long absence of any good, stable protonic conductors could easily explain this. The presence of water in the protonic conductors eliminates the possibility of high-temperature preparation and hence of conventional ceramic processing. Since solid electrolytes are used as dense ceramic membranes, difficulties with the fabrication of protonic electrilytes has been a strong disincentive. However, techniques have been developed for fabricating dense composite membranes; these contain free, but immobilized water that is lost at relatively low temperatures. Framework hydrates hold their water to higher temperatures. Although low-temperature ion-exchange preparations are possible, they yield weak ceramics. Nevertheless, their support on strong substrates, as reported in this conference, may provide an alternate way forward. A second workshop was organised on this theme at Hindsgavl Castle, Denmark, 1982. The aim was to compare the progress made in laboratories in Denmark, France and U.K. and also to review present and and future applications of fuel cells in a broader sense. Thirty scientists and representatives from the Commission of the European Communities, European Space Agency and the Daish Ministry of Energy participated. The proceedings cover all the papers of the workshop and the main comments and suggestions proposed during the discussions.

EPA/IFP EUROPEAN WORKSHOP ON THE EMISSION ON NITROUS OXIDE FROM FOSSIL FUEL COMBUSTION

Science.gov (United States)

The report summarizes the proceedings of an EPA/Institut Francais du Petrole (IFP) cosponsored workshop addressing direct nitrous oxide (N2O) emission from fossil fuel combustion. The third in a series, it was held at the IFP in Rueil-Malmaison, France, on June 1-2, 1988. Increas...

International nuclear fuel cycle fact book. [Contains glossary

Energy Technology Data Exchange (ETDEWEB)

Leigh, I.W.; Lakey, L.T.; Schneider, K.J.; Silviera, D.J.

1987-01-01

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained has been obtained from nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops; and so forth. Sources do not agree completely with each other, and the data listed herein does not reflect any one single source but frequently is a consolidation/combination of information. Lack of space as well as the intent and purpose of the Fact Book limit the given information to that pertaining to the Nuclear Fuel Cycle and to data considered of primary interest or most helpful to the majority of users.

Proceedings of DAE-BRNS third international symposium on materials chemistry

International Nuclear Information System (INIS)

Tyagi, Deepak; Banerjee, Atindra Mohan; Nigam, Sandeep; Varma, Salil; Tripathi, Arvind Kumar; Bharadwaj, Shyamala Rajkumar; Das, Dasarathi

2010-12-01

The present volume consists of the proceedings of the DAE-BRNS Third International Symposium on Materials Chemistry. In order to keep pace with the advancements made in the area of materials chemistry, new topics like materials for energy conversion, biomaterials, carbon based materials, soft condensed materials, thin films, surface chemistry, polymer based materials, organic and organometallics, magnetic materials and high purity materials have been included in this symposium while topics like nuclear materials, nanomaterials and clusters, catalysis, chemical sensors, fuel cell materials and computational research in materials chemistry have been continued as important features of the symposium. Papers relevant to INIS are indexed separately

Water Chemistry and Clad Corrosion/Deposition Including Fuel Failures. Proceedings of a Technical Meeting

International Nuclear Information System (INIS)

2013-03-01

Corrosion is a principal life limiting degradation mechanism in nuclear steam supply systems, particularly taking into account the trends in increasing fuel burnup, thermal ratings and cycle length. Further, many plants have been operating with varying water chemistry regimes for many years, and issues of crud (deposition of corrosion products on other surfaces in the primary coolant circuit) are of significant concern for operators. At the meeting of the Technical Working Group on Fuel Performance and Technology (TWGFPT) in 2007, it was recommended that a technical meeting be held on the subject of water chemistry and clad corrosion and deposition, including the potential consequences for fuel failures. This proposal was supported by both the Technical Working Group on Advanced Technologies for Light Water Reactors (TWG-LWR) and the Technical Working Group on Advanced Technologies for Heavy Water Reactors (TWG-HWR), with a recommendation to hold the meeting at the National Nuclear Energy Generating Company ENERGOATOM, Ukraine. This technical meeting was part of the IAEA activities on water chemistry, which have included a series of coordinated research projects, the most recent of which, Optimisation of Water Chemistry to Ensure Reliable Water Reactor Fuel Performance at High Burnup and in Ageing Plant (FUWAC) (IAEATECDOC-1666), concluded in 2010. Previous technical meetings were held in Cadarache, France (1985), Portland, Oregon, USA (1989), Rez, Czech Republic (1993), and Hluboka nad Vltavou, Czech Republic (1998). This meeting focused on issues associated with the corrosion of fuel cladding and the deposition of corrosion products from the primary circuit onto the fuel assembly, which can cause overheating and cladding failure or lead to unplanned power shifts due to boron deposition in the clad deposits. Crud deposition on other surfaces increases radiation fields and operator dose and the meeting considered ways to minimize the generation of crud to avoid

Proceedings of the Second OECD/NEA Organisation Meeting on Increased Accident Tolerance of Fuels for LWRs

International Nuclear Information System (INIS)

Massara, Simone; ); Bragg-Sitton, Shannon; Braase, Lori; Merrill, Brad; Teague, Melissa; Stanek, Chris R.; Montgomery, Robert H.; Ott, Larry J.; Robb, Kevin; Snead, Lance; Farmer, Mitch; Billone, Michael C.; Todosow, Michael; Brown, Nicholas; Brachet, J.C.; Le Flem, M.; Sauder, C.; Idarraga-Trujillo, I.; Michaux, A.; Lorrette, C.; Le Saux, M.; Blanpain, P.; Park, Jeong-Yong; Yang, Jae-Ho; Kim, Weon-Ju; Koo, Yang-Hyun; Liu, T.; Hallstadius, Lars; Lahoda, Ed; Waeckel, N.; Bonnet, J.M.; Vitanza, Carlo; Ohta, Hirokazu; Ogata, Takanari; Nakamura, Kinya; Dyck, Gary; Inozemtsev, Victor; )

2013-01-01

Under the guidance of the OECD-NEA Nuclear Science Committee, the expert group acts as a forum for scientific and technical information exchange on advanced light water reactor (LWR) fuels with enhanced accident tolerance. The expert group focusses on the fundamental properties and behaviour under normal operations and accident conditions for advanced core materials and components (fuels, cladding, control rods, etc.). The materials considered are applicable to Gen II and Gen III Light Water Reactors, as well as Gen III+ reactors under construction. The objective of the expert group is to define and coordinate a programme of work to help advance the scientific knowledge needed to provide the technical underpinning for the development of advanced LWR fuels with enhanced accident tolerance compared to currently used zircaloy/UO 2 fuel systems, as well as other non-fuel core components with important roles in LWR performance under accident conditions. This document brings together the available presentations (slides) given at the 2. Meeting on Increased Accident Tolerance of Fuels for LWRs. Content: 1 - Overview of the exchanges after the December-2012 Workshop through the discussion forum established at the OECD-NEA (S. Massara, NEA); 2 - Metrics Development for Enhanced Accident Tolerant LWR Fuels (S. Bragg-Sitton, INL); 3 - Candidate ATF Clad Technologies and Key Feasibility Issues (L. Snead, ORNL); 4 - CEA studies on nuclear fuel claddings for LWRs enhanced accident tolerant fuel. Some recent results, pending issues and prospects (J.C. Brachet, CEA); 5 - Current status on the accident tolerant fuel development in the Republic of Korea (J.Y. Park, J.H. Chang, KAERI); 6 - The current status of fuel R and D in the P.R. of China (T. Liu, CGN). Session 2: Key elements for a work programme on ATF: 7 - Beneficial characteristics of ATF (metrics) (L. Hallstadius, Westinghouse); 8 - Reactor types of interest (applicability) (L. Ott, ORNL); 9 - Impact on normal operations

16 CFR 3.2 - Nature of adjudicative proceedings.

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 1 2010-01-01 2010-01-01 false Nature of adjudicative proceedings. 3.2... RULES OF PRACTICE FOR ADJUDICATIVE PROCEEDINGS Scope of Rules; Nature of Adjudicative Proceedings § 3.2 Nature of adjudicative proceedings. Adjudicative proceedings are those formal proceedings conducted under...

A mathematical model of an automatic assembler to stack fuel pellets

International Nuclear Information System (INIS)

Jarvis, R.G.; Joynes, R.; Bretzlaff, C.I.

1980-11-01

Fuel elements for CANDU reactors are assembled from stacks of cylindrical UO 2 pellets, with close tolerances on lengths and diameters. Present stacking techniques involve extensive manual operations and they can be speeded up and reduced in cost by an automated device. If gamma-active fuel is handled such a device is essential. An automatic fuel pellet assembly process was modelled mathematically. The model indicated a suitable sequence of pellet manipulations to arrive at a stack length that was always within tolerance. This sequence was used as the inital input for the design of mechanical hardware. The mechanical design and the refinement of the mathematical model proceeded simultaneously. Mechanical constraints were allowed for in the model, and its optimized sequence of operations was incorporated in a microcomputer program to control the mechanical hardware. (auth)

Intelligence and Schooling. Fueling the Education Explosion: Proceedings of Conference 2 (Cleveland, Ohio, November 17-18, 1983).

Science.gov (United States)

Gardner, Mary, Ed.; Reed-Mundell, Charlene, Ed.

These proceedings contain presentations from a conference whose major topics were real-world intelligence, artificial intelligence, and linkage between the education and corporate sectors. "People, Perspectives...Potential and Possibilities" (Elyse S. Fleming), which was the conference's closing speech, briefly summarizes the information…

Proceedings of the specialist meeting on nuclear fuel and control rods: operating experience, design evolution and safety aspects

International Nuclear Information System (INIS)

1997-01-01

Design and management of nuclear fuel has undergone a strong evolution process during past years. The increase of the operating cycle length and of the discharge burnup has led to the use of more advanced fuel designs, as well as to the adoption of fuel efficient operational strategies. The analysis of recent operational experience highlighted a number of issues related to nuclear fuel and control rod events raising concerns about the safety aspects of these new designs and operational strategies, which led to the organisation of this Specialists Meeting on fuel and control rod issues. The meeting was intended to provide a forum for the exchange of information on lessons learned and safety concern related to operating experience with fuel and control rods (degradation, reliability, experience with high burnup fuel, and others). After an opening session 6 papers), this meeting was subdivided into four sessions: Operating experience and safety concern (technical session I - 6 papers), Fuel performance and operational issues (technical session II - 7 papers), Control rod issues (technical session III - 9 papers), Improvement of fuel design (technical session IV.A - 4 papers), Improvement on fuel fabrication and core management (technical session IV.B - 6 papers)

Fuel Cycle Services The Heart of Nuclear Energy

International Nuclear Information System (INIS)

Soedyartomo-Soentono

2007-01-01

Fuel is essential for development whether for survival and or wealth creation purposes. In this century the utilization of fuels need to be improved although energy mix is still to be the most rational choice. The large amount utilization of un-renewable fossil has some disadvantages since its low energy content requires massive extraction, transport, and processing while emitting CO 2 resulting degradation of the environment. In the mean time the advancement of nuclear science and technology has improved significantly the performance of nuclear power plant management of radioactive waste, enhancement of proliferation resistance, and more economic competitiveness. Ever since the last decade of the last century the nuclear renaissance has taken place. This is also due to the fact that nuclear energy does not emit GHG. Although the nuclear fuel offers a virtually limitless source of economic energy, it is only so if the nuclear fuel is reprocessed and recycled. Consequently, the fuel cycle is to be even more of paramount important in the future. The infrastructure of the fuel cycle services world wide has been adequately available. Various International Initiatives to access the fuel cycle services are also offered. However, it is required to put in place the International Arrangements to guaranty secured sustainable supply of services and its peaceful use. Relevant international cooperations are central for proceeding with the utilization of nuclear energy, while this advantagous nuclear energy utilization relies on the fuel cycle services. It is therefore concluded that the fuel cycle services are the heart of nuclear energy, and the international nuclear community should work together to maintain the availability of this nuclear fuel cycle services timely, sufficiently, and economically. (author)

Fuel Cycle Services the Heart of Nuclear Energy

Directory of Open Access Journals (Sweden)

S. Soentono

2007-01-01

Full Text Available Fuel is essential for development whether for survival and or wealth creation purposes. In this century the utilization of fuels need to be improved although energy mix is still to be the most rational choice. The large amount utilization of un-renewable fossil has some disadvantages since its low energy content requires massive extraction, transport, and processing while emitting CO2 resulting degradation of the environment. In the mean time the advancement of nuclear science and technology has improved significantly the performance of nuclear power plant, management of radioactive waste, enhancement of proliferation resistance, and more economic competitiveness. Ever since the last decade of the last century the nuclear renaissance has taken place. This is also due to the fact that nuclear energy does not emit GHG. Although the nuclear fuel offers a virtually limitless source of economic energy, it is only so if the nuclear fuel is reprocessed and recycled. Consequently, the fuel cycle is to be even more of paramount important in the future. The infrastructure of the fuel cycle services worldwide has been adequately available. Various International Initiatives to access the fuel cycle services are also offered. However, it is required to put in place the International Arrangements to guaranty secured sustainable supply of services and its peaceful use. Relevant international co-operations are central for proceeding with the utilization of nuclear energy, while this advantageous nuclear energy utilization relies on the fuel cycle services. It is therefore concluded that the fuel cycle services are the heart of nuclear energy, and the international nuclear community should work together to maintain the availability of this nuclear fuel cycle services timely, sufficiently, and economically.

Proceedings of the second US Department of Energy environmental control symposium. Volume 2. Nuclear energy, conservation, and solar energy

International Nuclear Information System (INIS)

1980-06-01

These proceedings document the presentations given at the Second Environmental Control Symposium. Symposium presentations highlighted environmental control activities which span the entire DOE. Volume II contains papers relating to: environmental control aspects of nuclear energy use and development; nuclear waste management; renewable energy sources; transportation and building conservation (fuel economy, gasohol, building standards, and industry); and geothermal energy, power transmission, and energy storage

The conversion of NRU from HEU to LEU fuel

International Nuclear Information System (INIS)

Sears, D.F.; Atfield, M.D.; Kennedy, I.C.

1990-01-01

The program at Chalk River Nuclear Laboratories (CRNL) to develop and test low-enriched uranium fuel (LEU, 3 Si, USiAl, USi Al and U 3 Si 2 (U-3.96 wt% Si; U-3.5 wt% Si-1.5 wt% AL; U-3.2 wt%; Si-3 wt% Al; U-7.3 wt% Si, respectively). Fuel elements were fabricated with uranium loadings suitable for NRU, 3.15 gU/cm 3 , and for NRX, 4.5 gU/cm 3 , and were irradiated under normal fuel-operating conditions. Eight experimental irradiations involving 100 mini-elements and 84 full-length elements (7X12-element rods) were completed to qualify the LEU fuel and the fabrication technology. Post irradiation examinations confirmed that the performance of the LEU fuel, and that of a medium enrichment uranium (MEU, 45% U-235) alloy fuel tested as a back-up, was comparable to the HEU fuel. The uranium silicide dispersion fuel swelling was approximately linear up to burnups exceeding NRU's design terminal burnup (80 at%). NRU was partially converted to LEU fuel when the first 31 prototype fuel rods manufactured with industrial scale production equipment were installed in the reactor. The rods were loaded in NRU at a fuelling rate of about two rods per week over the period 1988 September to December. This partial LEU core (one third of a full NRU core) has allowed the reactor engineers and physicists to evaluate the bulk effects of the LEU conversion on NRU operations. As expected, the irradiation is proceeding without incident

In-Pile Testing and Instrumentation for Development of Generation-IV Fuels and Materials. Proceedings of a Technical Meeting

International Nuclear Information System (INIS)

2013-12-01

For many years, the increase in efficiency in the production of nuclear electricity has been an economic challenge in many countries which have developed this kind of energy. The increase in fuel burnup and fuel residence time leads to a reduction in the volume of fresh fuel loaded and spent fuel discharged, respectively. More demanding nuclear fuel cycle parameters are combined with a need to operate nuclear power plants with maximal availability and load factors, in load-follow mode and with longer fuel cycles. In meeting these requirements, fuel has to operate in a demanding environment of high radiation fields, high temperatures, high mechanical stresses and high coolant flow. Requirements of increased fuel reliability and minimal fuel failures also remain in force. Under such circumstances, continuous development of more radiation resistant fuel materials, especially advanced cladding, careful and incremental examinations, and improved understanding and modelling of high burnup fuel behaviour are required. Following a recommendation of the IAEA Technical Working Group on Fuel Performance and Technology, the Technical Meeting on In-pile Testing and Instrumentation for Development of Generation-IV Fuels and Materials was held in Halden, Norway, on 21-24 August 2012. The purpose of the meeting was to review the current status and the progress in methods and technologies used for the in-pile testing of nuclear fuel achieved since the previous IAEA meeting on In-core Instrumentation and Reactor Core Assessment, also held in Halden in 2007. Emphasis was placed on advanced techniques applied for the understanding of high burnup fuel behaviour of water cooled power reactors that represent the vast majority of the current nuclear reactor fleet. However, the meeting also included papers and discussion on testing techniques applied or developed specifically for new fuel and structural materials considered for Generation-IV systems. The meeting was attended by 43

The Effect of Diethylene Glycol Monomethyl Ether (DiEGME) on Microbial Contamination of Jet Fuel: A Minimum Concentration Study

Science.gov (United States)

2010-03-01

Prescott , L. M.; Harley, J. P.; Klein, D. A. Microbiology . Fifth edition. McGraw Hill: New York, 2002. 26. Amman, R. I., Ludwig, W., Schleifer, K. H...Recent advances in petroleum microbiology . Microbiology and molecular biology reviews 2003, 67, 503-49. 6. Langer, G. JP-4 Fuel System Icing. Armour...Wright Air Development Center. 8. Elderfield, R. C. Proceedings on Jet Fuel Microbiology and Corrosion Conference. Prevention of Deterioration Center

Remote, under-sodium fuel handling experience at EBR-II

International Nuclear Information System (INIS)

King, R.W.; Planchon, H.P.

1995-01-01

The EBR-II is a pool-type design; the reactor fuel handling components and entire primary-sodium coolant system are submerged in the primary tank, which is 26 feet in diameter, 26 feet high, and contains 86,000 gallons of sodium. Since the reactor is submerged in sodium, fuel handling operations must be performed blind, making exact positioning and precision control of the fuel handling system components essential. EBR-II operated for 30 years, and the fuel handling system has performed approximately 25,000 fuel transfer operations in that time. Due to termination of the IFR program, EBR-II was shut down on September 30, 1994. In preparation for decommissioning, all fuel in the reactor will be transferred out of EBR-II to interim storage. This intensive fuel handling campaign will last approximately two years, and the number of transfers will be equivalent to the fuel handling done over about nine years of normal reactor operation. With this demand on the system, system reliability will be extremely important. Because of this increased demand, and considering that the system has been operating for about 32 years, system upgrades to increase reliability and efficiency are proceeding. Upgrades to the system to install new digital, solid state controls, and to take advantage of new visualization technology, are underway. Future reactor designs using liquid metal coolant will be able to incorporate imaging technology now being investigated, such as ultraviolet laser imaging and ultrasonic imaging

Materials accountancy and control for power reactors and associated spent-fuel storage

International Nuclear Information System (INIS)

Ek, P.

1982-01-01

Materials accountancy and control at power reactors is an integrated part of the Swedish National System of Accuntancy and Control of Nuclear Materials. The nuclear material is stratified on the basis of measurement accuracy. The physical form of the material makes item accountability applicable on the rod level. Consequently, fuel assembly dismantling and fuel rod exchanges present special problems. Both physical inventory verification and the shipment of irradiated fuel are extensive operations involving inspections and controls on inventory records and fuel elements. A method for nondestructive measurement of irradiated fuel is under development in cooperation with the IAEA. The method has been tested at a reactor station with encouraging results. An away from reactor storage facility for spent fuel is under construction in Sweden. Optical verificationof each fuel element at all times is one of the basic facility control requirements. The receiving/shipping area of the storage facility is being designed and equipped to make NDA-measurements feasible. The overlal cooperation with the IAEA in matters related to safeguarding power reactors is proceeding smoothly. There are, however, some differences of opinion, for example, as regards material stratification (Key Measurement Points) and verification procedures

Proceedings of the 2004 symposium on nuclear data

International Nuclear Information System (INIS)

Tahara, Yoshihisa; Fukahori, Tokio

2005-03-01

The 2004 Symposium on Nuclear Data was held at Tokai Research Establishment, Japan Atomic Energy Research Institute (JAERI), on 11th and 12th of November 2004. Japanese Nuclear Data Committee and Nuclear Data Center, JAERI organized this symposium. In the oral sessions, presented were 19 papers on topics of nuclear data for LWR and nuclear fuel cycle, nuclear data for ADS development, experiences from use of JENDL-3.3 and requests to JENDL-4, recent cross section measurements, nuclear data for life and material sciences, and nuclear data needs and activities in the World. In the poster session, presented were 21 papers concerning experiments, evaluations, benchmark tests, applications and so on. Those presented papers are compiled in the proceedings. The 40 of the presented papers are indexed individually. (J.P.N.)

Nuclear fuel behaviour modelling at high burnup and its experimental support. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

2001-07-01

The Technical Committee Meeting (TCM) included separate sessions on the specific topics of fuel thermal performance and fission product retention. On thermal performance, it is apparent that the capability exists to measure conductivity in high burnup fuel either by out-of-pile measurement or by instrumentation of test reactor rods. State-of-the-art modelling codes contain models for the conductivity degradation process, and hence adequate predictions of fuel temperature are achievable. Concerning fission product release, it is clear that many groups around the world are actively investigating the subject, with experimental and modelling programmes being pursued. However, a general consensus on the exact mechanisms of gas release and related gas bubble swelling has yet to emerge, even at medium burnup levels. Fission gas phenomena, not only the release to open volumes, but the whole sequence of processes taking place prior to this, need to be modelled in any modern fuel performance code. The presence of gaseous fission products may generate rapid fuel swelling during power transients, and this can cause PCI and rod failure. At high burnups, the quantity of released gases could give rise to pressures exceeding the safe limits. Modelling of pellet-cladding interaction (PCI) effects during transient operation is also an active area of study for many groups. In some situations a purely empirical approach to failure modelling can be justified, while for other applications a more detailed mechanistic approach is required. Another aspect of cladding modelling which was featured at the TCM concerned corrosion and hydriding. Although this issue can be the main life-limiting factor on fuel duty, it is apparent that modelling methods, and the experimental measurement techniques that underpin them, are adequate. A session was included on MOX fuel modelling. Substantial programmes of work, especially by the MOX vendors, appear to be underway to bring the level of understanding

Implementation of burnup credit in spent fuel management systems. Proceedings of an advisory group meeting

International Nuclear Information System (INIS)

1998-04-01

The criticality safety analysis of spent fuel systems has traditionally assumed that the fuel is fresh. This results in significant conservatism in the calculated value of the system's reactivity. Improved calculational methods allows one to take credit for the reactivity reduction associated with fuel burnup, hence reducing the analysis conservatism while maintaining an adequate criticality safety margin. Motivation for using burnup credit in criticality safety applications is generally based on economic considerations. Although economics may be a primary factor in deciding to use burnup credit, other benefits may be realized. Many of the additional benefits of burnup credit that are not strictly economic, may be considered to contribute to public health and safety, and resource conservation and environmental quality. Interest in the implementation of burnup credit has been shown by many countries. A summary of the information gathered by the IAEA about ongoing activities and regulatory status of burnup credit in different countries is included. Burnup credit implementation introduces new parameters and effects that should be addressed in the criticality analysis (e.g., axial and radial burnup shapes, fuel irradiation history, and others). Analysis of these parameters introduces new variations as well as the uncertainties, that should be considered in the safety assessment of the system. Also, the need arises to validate the isotopic composition that results from a depletion calculation, as well as to extend the current validation range of criticality codes to cover spent fuel. The use of burnup credit implies a verification of the fuel burnup before loading for transport, storage, disposal, or reprocessing each assembly, to make sure that the burnup level achieved complies with the criteria established. Methods and procedures used in different countries are described in this report

Implementation of burnup credit in spent fuel management systems. Proceedings of an advisory group meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-04-01

The criticality safety analysis of spent fuel systems has traditionally assumed that the fuel is fresh. This results in significant conservatism in the calculated value of the system`s reactivity. Improved calculational methods allows one to take credit for the reactivity reduction associated with fuel burnup, hence reducing the analysis conservatism while maintaining an adequate criticality safety margin. Motivation for using burnup credit in criticality safety applications is generally based on economic considerations. Although economics may be a primary factor in deciding to use burnup credit, other benefits may be realized. Many of the additional benefits of burnup credit that are not strictly economic, may be considered to contribute to public health and safety, and resource conservation and environmental quality. Interest in the implementation of burnup credit has been shown by many countries. A summary of the information gathered by the IAEA about ongoing activities and regulatory status of burnup credit in different countries is included. Burnup credit implementation introduces new parameters and effects that should be addressed in the criticality analysis (e.g., axial and radial burnup shapes, fuel irradiation history, and others). Analysis of these parameters introduces new variations as well as the uncertainties, that should be considered in the safety assessment of the system. Also, the need arises to validate the isotopic composition that results from a depletion calculation, as well as to extend the current validation range of criticality codes to cover spent fuel. The use of burnup credit implies a verification of the fuel burnup before loading for transport, storage, disposal, or reprocessing each assembly, to make sure that the burnup level achieved complies with the criteria established. Methods and procedures used in different countries are described in this report. Refs, figs, tabs.

Symposium proceedings: environmental aspects of fuel conversion technology, II, December 1975, Hollywood, Florida. [34 papers

Energy Technology Data Exchange (ETDEWEB)

Ayer, F.A. (comp.)

1976-06-01

The report covers EPA's second symposium on the environmental aspects of fuel conversion technology. Its main objective was to review and discuss environmentally related information in the field of fuel conversion technology. Specific topics were environmental problem definition, process technology, control technology, and process measurements. Thirty-four papers were abstracted and indexed separately.

Application of adjoint sensitivity analysis to nuclear reactor fuel rod performance

International Nuclear Information System (INIS)

Wilderman, S.J.; Was, G.S.

1984-01-01

Adjoint sensitivity analysis in nuclear fuel behavior modeling is extended to operate on the entire power history for both Zircaloy and stainless steel cladding via the computer codes FCODE-ALPHA/SS and SCODE/SS. The sensitivities of key variables to input parameters are found to be highly non-intuitive and strongly dependent on the fuel-clad gap status and the history of the fuel during the cycle. The sensitivities of five key variables, clad circumferential stress and strain, fission gas release, fuel centerline temperature and fuel-clad gap, to eleven input parameters are studied. The most important input parameters (yielding significances between 1 and 100) are fabricated clad inner and outer radii and fuel radius. The least important significances (less than 0.01) are the time since reactor start-up and fuel-burnup densification rate. Intermediate to these are fabricated fuel porosity, linear heat generation rate, the power history scale factor, clad outer temperature, fill gas pressure and coolant pressure. Stainless steel and Zircaloy have similar sensitivities at start-up but these diverges a burnup proceeds due to the effect of the higher creep rate of Zircaloy which causes the system to be more responsive to changes in input parameters. The value of adjoint sensitivity analysis lies in its capability of uncovering dependencies of fuel variables on input parameters that cannot be determined by a sequential thought process. (orig.)

Energy systems and technologies for the coming century. Proceedings

Energy Technology Data Exchange (ETDEWEB)

Soenderberg Petersen, L; Larsen, Hans [eds.

2011-05-15

Risoe International Energy Conference 2011 took place 10 - 12 May 2011. The conference focused on: 1) Future global energy development options, scenarios and policy issues. 2) Intelligent energy systems of the future, including the interaction between supply and end-use. 3) New and emerging technologies for the extended utilisation of sustainable energy. 4) Distributed energy production technologies such as fuel cells, hydrogen, bioenergy, wind, hydro, wave, solar and geothermal. 5) Centralised energy production technologies such as clean coal technologies, CCS and nuclear. 6) Renewable energy for the transport sector and its integration in the energy system The proceedings are prepared from papers presented at the conference and received with corrections, if any, until the final deadline on 20-04-2011. (Author)

Proceedings of the American power conference: Volume 61-1

International Nuclear Information System (INIS)

McBride, A.E.

1999-01-01

This is volume one of the proceedings of the American Power Conference of 1999. The topics of the papers include multi-skilled work forces for the next century; global climate change and mitigation; distributed generation prospects in an open market; US DOE--EPRI wind turbine verification program; operations and maintenance cost reduction strategies; surviving deregulation and competition; power markets risk management and trading; interconnected operations; commercializing reliability; utility automation; electrical impacts of facilities operation; training for the future; SOX/PM2.5/air toxic; turbine-generator plant advances; codes and standards -- competing globally; business opportunities; the changing regulatory environment; advanced fuel design and engineering analysis: mandate for competing under regulation; unit commitment and dispatch; strategies for the open market; outage management; distribution reliability; and NOX control

Laser Interaction and Related Plasma Phenomena: 13th International Conference. Proceedings

International Nuclear Information System (INIS)

Miley, G.H.; Campbell, E.M.; Hogan, W.J.; Maille-Petersen, C.; Coppedge, H.; Montoya, E.

1997-01-01

These proceedings contain papers presented at the Thirteenth International Conference on Laser Interaction and Related Plasma Phenomena held in Monterey, California in April, 1997. Topics covered in the conference included laser design, alternate concepts in volume ignition and advance fuels, beam/plasma interactions, nuclear-pumped lasers, alternate fast ignitors, heavy ion fusions, laser-ion beam interactions, extreme short-pulse interactions, high-energy-density plasma physics, and hydrodynamic instabilities. The conference was sponsored in part by the Lawrence Livermore National Laboratory of the United States Department of Energy. There were 80 papers presented and 23 have been abstracted for the Energy Science and Technology database

Proceedings of the second US Department of Energy environmental control symposium. Volume 2. Nuclear energy, conservation, and solar energy

Energy Technology Data Exchange (ETDEWEB)

None

1980-06-01

These proceedings document the presentations given at the Second Environmental Control Symposium. Symposium presentations highlighted environmental control activities which span the entire DOE. Volume II contains papers relating to: environmental control aspects of nuclear energy use and development; nuclear waste management; renewable energy sources; transportation and building conservation (fuel economy, gasohol, building standards, and industry); and geothermal energy, power transmission, and energy storage. (DMC)

17 CFR 12.24 - Parallel proceedings.

Science.gov (United States)

2010-04-01

...) Definition. For purposes of this section, a parallel proceeding shall include: (1) An arbitration proceeding... the receivership includes the resolution of claims made by customers; or (3) A petition filed under... any of the foregoing with knowledge of a parallel proceeding shall promptly notify the Commission, by...

Proceedings of the 2. SIPEN: Integration week from IPEN - Brazilian Institute for Energy and Nuclear Researches, CNEN/SP

International Nuclear Information System (INIS)

1994-01-01

The technical-scientific activities of IPEN (Instituto de Pesquisas Energeticas e Nucleares), Brazilian CNEN, has been presented in these proceedings. It includes the following topics: management and logistics, infra-structure and support, application of nuclear techniques, fuel cycle, materials, reactor research, development of products and services, radiation protection and monitoring. Nuclear medicine and application of radiation in biological assays are studied. Environmental impacts and management of radioactive wastes are also presented

Used mixed oxide fuel reprocessing at RT-1 plant

Energy Technology Data Exchange (ETDEWEB)

Kolupaev, D.; Logunov, M.; Mashkin, A.; Bugrov, K.; Korchenkin, K. [FSUE PA ' Mayak' , 30, Lenins str, Ozersk, 460065 (Russian Federation); Shadrin, A.; Dvoeglazov, K. [ITCP ' PRORYV' , 2/8 Malaya Krasmoselskay str, Moscow, 107140 (Russian Federation)

2016-07-01

Reprocessing of the mixed uranium-plutonium spent nuclear fuel of the BN-600 reactor was performed at the RT-1 plant twice, in 2012 and 2014. In total, 8 fuel assemblies with a burn-up from 73 to 89 GW day/t and the cooling time from 17 to 21 years were reprocessed. The reprocessing included the stages of dissolution, clarification, extraction separation of U and Pu with purification from the fission products, refining of uranium and plutonium at the relevant refining cycles. Dissolution of the fuel composition of MOX used nuclear fuel (UNF) in nitric acid solutions in the presence of fluoride ion has occurred with the full transfer of actinides into solution. Due to the high content of Pu extraction separation of U and Pu was carried out on a nuclear-safe equipment designed for the reprocessing of highly enriched U spent nuclear fuel and Pu refining. Technological processes of extraction, separation and refining of actinides proceeded without deviations from the normal mode. The output flow of the extraction outlets in their compositions corresponded to the regulatory norms and remained at the level of the compositions of the streams resulting from the reprocessing of fuel types typical for the RT-1 plant. No increased losses of Pu into waste have been registered during the reprocessing of BN-600 MOX UNF an compare with VVER-440 uranium UNF reprocessing. (authors)

Simplified proceeding as a civil procedure model

Directory of Open Access Journals (Sweden)

Олексій Юрійович Зуб

2016-01-01

Full Text Available Currently the directions for the development of modern civil procedural law such as optimization, facilitation, forwarding proceedings promoting the increase of the civil procedure efficiency factor are of peculiar importance. Their results are occurrence and functionality of simplified proceedings system designed to facilitate significantly hearing some categories of cases, promotion of their consideration within reasonable time and reduce legal expenses so far as it is possible. The category “simplified proceedings” in the native science of the procedural law is underexamined. A good deal of scientists-processualists were limited to studying summary (in the context of optimization as a way to improve the civil procedural form, summary proceedings and procedures functioning in terms of the mentioned proceedings, consideration of case in absentia as well as their modification. Among the Ukrainian scientist who studied some aspects of the simplified proceedings are: E. A. Belyanevych, V. I. Bobrik, S. V. Vasilyev, M. V. Verbitska, S. I. Zapara, A. A. Zgama, V. V. Komarov, D. D. Luspenuk, U. V. Navrotska, V. V. Protsenko, T. V. Stepanova, E. A. Talukin, S. Y. Fursa, M. Y. Shtefan others. The problems of the simplified proceedings were studied by the foreign scientists as well, such as: N. Andrews, Y. Y. Grubanon, N. A. Gromoshina, E. P. Kochanenko, J. Kohler, D. I. Krumskiy, E. M. Muradjan, I. V. Reshetnikova, U. Seidel, N. V. Sivak, M. Z. Shvarts, V. V. Yarkov and others. The paper objective is to develop theoretically supported, practically reasonable notion of simplified proceedings in the civil process, and also basing on the notion of simplified proceedings, international experience of the legislative regulation of simplified proceedings, native and foreign doctrine, to distinguish essential features of simplified proceedings in the civil process and to describe them. In the paper we generated the notion of simplified proceedings that

Third international spent fuel stroage technology symposium/workshop: proceedings. Volume 1

International Nuclear Information System (INIS)

1986-01-01

The scope of this meeting comprised dry storage and rod consolidation, emphasizing programs on water reactor fuel with zirconium alloy cladding. Volume 1 contains the symposium papers, together with the question/answer sessions that followed the presentations. Four sessions were held: Dry Storage System Tests, Demonstrations and Analyses; At-Reactor and Central Storage Facilities; Dry Storage Integrity; and Rod Consolidation Technology and Demonstrations. Individual papers were processed for inclusion in the Energy Data Base

New Nuclear Materials Including Non Metallic Fuel Elements. Vol. I. Proceedings of the Conference on New Nuclear Materials Technology, Including Non Metallic Fuel Elements

International Nuclear Information System (INIS)

1963-01-01

One of the major aims of the International Atomic Energy Agency in furthering the peaceful uses of atomic energy is to encourage the development of economical nuclear power. Certainly, one of the more obvious methods of producing economical nuclear power is the development of economical fuels that can be used at high temperatures for long periods of time, and which have sufficient strength and integrity to operate under these conditions without permitting the release of fission products. In addition it is desirable that after irradiation these new fuels be economically reprocessed to reduce further the cost of the fuel cycle. As nuclear power becomes more and more competitive with conventional power the interest in new and more efficient higher-temperature fuels naturally increases rapidly. For these reasons, the Agency organized a Conference on New Nuclear Materials Technology, Including Non-Metallic Fuel Elements, which was held from 1 to 5 July 1963 at the International Hotel, Prague, with the assistance and co-operation of the Government of the Czechoslovak Socialist Republic. A total of 151 scientists attended, from 23 countries and 4 international organizations. The participants heard and discussed more than 60 scientific papers

Canada's directory of ethanol-blended fuel retailers (December 1998)

International Nuclear Information System (INIS)

1998-12-01

This publication serves as a directory of ethanol-blended gasoline retailers in Quebec, Ontario, Manitoba, Saskatchewan, Alberta, British Columbia, and the Yukon. The listings include the name and address of the retailer. The listing is organized by province and cities, beginning with the Yukon in the west and proceeding east to Quebec. A list of bulk purchase facilities of ethanol-blended fuels is also included. As of December 1998, there were a total of 929 retail outlets for ethanol blended gasoline in Canada

Proceedings of a workshop on the use of burnup credit in spent fuel transport casks

International Nuclear Information System (INIS)

Sanders, T.L.

1989-10-01

The Department of Energy sponsored a workshop on the use of burnup credit in the criticality design of spent fuel shipping casks on February 21 and 22, 1988. Twenty-five different presentations on many related topics were conducted, including the effects of burnup credit on the design and operation of spent fuel storage pools, casks and modules, and shipping casks; analysis and physics issues related to burnup credit; regulatory issues and criticality safety; economic incentives and risks associated with burnup credit; and methods for verifying spent fuel characteristics. An abbreviated version of the DOE workshop was repeated as a special session at the November 1988 American Nuclear Society Meeting in Washington, DC. Each of the invited speakers prepared detailed papers on his or her respective topic. The individual papers have been cataloged separately

Small molten-salt reactors with a rational thorium fuel-cycle

International Nuclear Information System (INIS)

Furukawa, Kazuo; Mitachi, Kohshi; Kato, Yoshio

1992-01-01

In the fission-energy utilization for solving global social and environmental problems including the 'Greenhouse Effect' in the next century, a new strategy should be introduced considering high safety and economy, simplicity, size-flexibility, anti-nuclear proliferation and terrorism, high temperature heat supply, etc., aiming to establish a rational breeding fuelcycle. Thorium Molten-Salt Nuclear Energy Synergetics based on [I] Th utilization, [II] fluid-fuel concept and [III] separation of fissile breeding and power generation functions would be one of the most promising approach. A design study of a standard Molten-Salt Reactor: FUJI-II (350 MWth, 155-161 MWe) ensuring fuel self-sustaining nature (conversion-ratio ∝ 1.0) in spite of small-size, and pilot-plant miniFUJI-II has been proceeded. (orig.)

Proceedings of the CSNI specialists meeting on fuel-coolant interactions

Energy Technology Data Exchange (ETDEWEB)

None

1994-03-01

A specialists meeting on fuel-coolant interactions was held in Santa Barbara, CA from January 5-7, 1993. The meeting was sponsored by the United States Nuclear Regulatory Commission in collaboration with the Committee on the Safety of Nuclear Installation (CSNI) of the OECD Nuclear Energy Agency (NEA) and the University of California at Santa Barbara. The objectives of the meeting are to cross-fertilize on-going work, provide opportunities for mutual check points, seek to focus the technical issues on matters of practical significance and re-evaluate both the objectives as well as path of future research. Individual papers have been cataloged separately.

Proceedings of the CSNI specialists meeting on fuel-coolant interactions

International Nuclear Information System (INIS)

1994-03-01

A specialists meeting on fuel-coolant interactions was held in Santa Barbara, CA from January 5--7, 1993. The meeting was sponsored by the United States Nuclear Regulatory Commission in collaboration with the Committee on the Safety of Nuclear Installation (CSNI) of the OECD Nuclear Energy Agency (NEA) and the University of California at Santa Barbara. The objectives of the meeting are to cross-fertilize on-going work, provide opportunities for mutual check points, seek to focus the technical issues on matters of practical significance and re-evaluate both the objectives as well as path of future research. Individual papers have been cataloged separately

The 11th International ICIT Conference Progress in Cryogenics and Isotopes Separation. Proceedings

International Nuclear Information System (INIS)

Stefanescu, Ioan

2005-01-01

The proceedings of the 11th International ICIT Conference Progress in Cryogenics and Isotopes Separation held in Caciulata, Romania on 12-14 October 2005 contain plenary lectures (6 papers) and 6 sections addressing the following subject matters: Section 1. Stable Isotopes Physics. Technologies and Applications (5 papers); Section 2. Science and Materials Engineering (11 papers); Section 3. Nuclear Power (21 papers); Section 4. Hydrogen and Fuel Cells (7 papers); Section 5. Environmental Protection. Industrial Risk (10 papers); Section 6. Laboratory Analysis Methods (10 papers). Twenty two papers are available in abstract form only and full text entered the corresponding records

49 CFR 511.2 - Nature of adjudicative proceedings.

Science.gov (United States)

2010-10-01

... 49 Transportation 6 2010-10-01 2010-10-01 false Nature of adjudicative proceedings. 511.2 Section... SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION ADJUDICATIVE PROCEDURES Scope of Rules; Nature of Adjudicative Proceedings, Definitions § 511.2 Nature of adjudicative proceedings. Adjudicative proceedings...

Integration of the AVLIS (atomic vapor laser isotopic separation) process into the nuclear fuel cycle. [Effect of AVLIS feed requirements on overall fuel cycle

Energy Technology Data Exchange (ETDEWEB)

Hargrove, R.S.; Knighton, J.B.; Eby, R.S.; Pashley, J.H.; Norman, R.E.

1986-08-01

AVLIS RD and D efforts are currently proceeding toward full-scale integrated enrichment demonstrations in the late 1980's and potential plant deployment in the mid 1990's. Since AVLIS requires a uranium metal feed and produces an enriched uranium metal product, some change in current uranium processing practices are necessitated. AVLIS could operate with a UF/sub 6/-in UF/sub 6/-out interface with little effect to the remainder of the fuel cycle. This path, however, does not allow electric utility customers to realize the full potential of low cost AVLIS enrichment. Several alternative processing methods have been identified and evaluated which appear to provide opportunities to make substantial cost savings in the overall fuel cycle. These alternatives involve varying levels of RD and D resources, calendar time, and technical risk to implement and provide these cost reduction opportunities. Both feed conversion contracts and fuel fabricator contracts are long-term entities. Because of these factors, it is not too early to start planning and making decisions on the most advantageous options so that AVLIS can be integrated cost effectively into the fuel cycle. This should offer economic opportunity to all parties involved including DOE, utilities, feed converters, and fuel fabricators. 10 refs., 11 figs., 2 tabs.

46 CFR 502.61 - Proceedings.

Science.gov (United States)

2010-10-01

...; Pleadings; Motions; Replies § 502.61 Proceedings. (a) Proceedings are commenced by the filing of a complaint... documents, or that the nature of the matter in issue is such that an oral hearing and cross-examination are...

Nuclear and radiological safety nuclear power nuclear fuel cycle and waste management

International Nuclear Information System (INIS)

1997-05-01

This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Nuclear and Radiological Safety, Nuclear Power and Nuclear Fuel Cycle and Waste Management and issued during the period of 1995-1996. Most publications are in English. Proceedings of conferences, symposia and panels of experts may contain some papers in languages other than English (Arabic, Chinese, French, Russian or Spanish), but all these papers have abstracts in English

The Spent Fuel Management in Finland and Modifications of Spent Fuel Storages

International Nuclear Information System (INIS)

Maaranen, Paeivi

2014-01-01

The objective of this presentation is to share the Finnish regulator's (STUK) experiences on regulatory oversight of the enlargement of a spent fuel interim storage. An overview of the current situation of spent fuel management in Finland will also be given. In addition, the planned modifications and requirements set for spent fuel storages due to the Fukushima accident are discussed. In Finland, there are four operating reactors, one under construction and two reactors that have a Council of State's Decision-in-Principle to proceed with the planning and licensing of a new reactor. In Olkiluoto, the two operating ASEA-Atom BWR units and the Areva EPR under construction have a shared interim storage for the spent fuel. The storage was designed and constructed in 1980's. The option for enlarging the storage was foreseen in the original design. Considering three operating units to produce their spent fuel and the final disposal to begin in 2022, extra space in the spent fuel storage is estimated to be needed in around 2014. The operator decided to double the number of the spent fuel pools of the storage and the construction began in 2010. The capacity of the enlarged spent fuel storage is considered to be sufficient for the three Olkiluoto units. The enlargement of the interim storage was included in Olkiluoto NPP 1 and 2 operating license. The licensing of the enlargement was conducted as a major plant modification. The operator needed the approval from STUK to conduct the enlargement. Prior to the construction of this modification, the operator was required to submit the similar documentation as needed for applying for the construction license of a nuclear facility. When conducting changes in an old nuclear facility, the new safety requirements have to be followed. The major challenge in the designing the enlargement of the spent fuel storage was to modify it to withstand a large airplane crash. The operator chose to cover the pools with protecting slabs and also to

High Technology and Education. Proceedings of Fueling the Education Explosion Conference 4 (Cleveland, Ohio, September 20-21, 1984).

Science.gov (United States)

Gardner, Mary, Ed.; Reed-Mundell, Charlene, Ed.

This document provides nine papers presented at a 2-day conference where representatives of the National Aeronautics and Space Administration (NASA) described the future of space exploration and discussed the implications of that future for educators. The proceedings begins with an introduction by Ralph Winrich, NASA Aerospace Education…

Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

1997-08-01

The Technical Committee Meeting on Fuel Element Modelling at High Burnup and its Experimental Support was recommended by the International Working Group on Fuel Performance and Technology (IWGFPT). Its subject had been touched on in many of the IAEA's activities; however for the first time modellers and experimentalists were brought together to have an exchange of views on the research under way and to identify areas where new knowledge is necessary to improve the safety, reliability and/or economics of nuclear fuel. The timely organization of this meeting in conjunction with the second meeting of the Co-ordinated Research Programme on Fuel Modelling at Extended Burnup, in short ''FUMEX'', allowed fruitful participation of representatives of developing countries which are only rarely exposed to such a scientific event. The thirty-nine papers presented covered the status of codes and experimental facilities and the main phenomena affecting the fuel during irradiation, namely: thermal fuel performance, clad corrosion and pellet-cladding interaction (PCI) and fission gas release (FGR). Refs, figs, tabs

Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-08-01

The Technical Committee Meeting on Fuel Element Modelling at High Burnup and its Experimental Support was recommended by the International Working Group on Fuel Performance and Technology (IWGFPT). Its subject had been touched on in many of the IAEA`s activities; however for the first time modellers and experimentalists were brought together to have an exchange of views on the research under way and to identify areas where new knowledge is necessary to improve the safety, reliability and/or economics of nuclear fuel. The timely organization of this meeting in conjunction with the second meeting of the Co-ordinated Research Programme on Fuel Modelling at Extended Burnup, in short ``FUMEX``, allowed fruitful participation of representatives of developing countries which are only rarely exposed to such a scientific event. The thirty-nine papers presented covered the status of codes and experimental facilities and the main phenomena affecting the fuel during irradiation, namely: thermal fuel performance, clad corrosion and pellet-cladding interaction (PCI) and fission gas release (FGR). Refs, figs, tabs.

On material and energy sources of formation of fuel-containing materials during Chernobyl NPP UNIT 4 accident

Directory of Open Access Journals (Sweden)

O. V. Mikhailov

2016-12-01

Full Text Available Results of detailed analysis of material substance of lava-like fuel-containing materials sources (FCM and clusters with high uranium concentration were presented. Material and energy balance are aggregated in a process model for optimal composition of sacrificial materials and FCM. Quantitative estimate is given for spent nuclear fuel’ afterheat in a number of other heat energy sources in reactor vault. Conclusion was made that upon condition of 50 % heat loss, remained amount of “useful” heat would be sufficient for proceeding of blast furnace version of fuel-containing materials.

Ignition and burn in inertially confined magnetized fuel

International Nuclear Information System (INIS)

Kirkpatrick, R.C.; Lindemuth, I.R.

1991-01-01

At the third International Conference on Emerging Nuclear Energy Systems, we presented computational results which suggested that ''breakeven'' experiments in inertial confinement fusion (ICF) may be possible with existing driver technology. We recently used the ICF simulation code LASNEX to calculate the performance of an idealized magnetized fuel target. The parameter space in which magnetized fuel operates is remote from that of both ''conventional'' ICF and magnetic confinement fusion devices. In particular, the plasma has a very high β and is wall confined, not magnetically confined. The role of the field is to reduce the electron thermal conductivity and to partially trap the DT alphas. The plasma is contained in a pusher which is imploded to compress and adiabatically heat the plasma from an initial condition of preheat and pre-magnetization to the conditions necessary for fusion ignition. The initial density must be quite low by ICF standards in order to insure that the electron thermal conductivity is suppressed and to minimize the generation of radiation from the plasma. Because the energy loss terms are effectively suppressed, the implosion may proceed at a relatively slow rate of about 1 to 3 cm/μs. Also, the need for low density fuel dictates a much larger target, so that magnetized fuel can use drivers with much lower power and power density. Therefore, magnetized fuel allows the use of efficient drivers that are not suitable for laser or particle beam fusion due to insufficient focus or too long pulse length. The ignition and burn of magnetized fuel involves very different dominant physical processes than does ''conventional'' ICF. The fusion time scale becomes comparable to the hydrodynamic time scale, but other processes that limit the burn in unmagnetized fuel are of no consequence. The idealized low gain magnetized fuel target presented here is large and requires a very low implosion velocity. 11 refs

Advanced fuels with reduced actinide generation. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

1996-11-01

Nuclear energy can play an important future role in supplying the world population with energy. However, this form of energy will be successful only under certain conditions: it must meet very strict safety requirements, it must be economically competitive, and it must be acceptable to the public. Nuclear power produces radioactive wastes and in several countries the public raises concern about safety. Much development work on advanced nuclear power systems is going on in several countries, with participation of both governmental and private industries to meet these conditions. In the framework of this IAEA activity the Technical Committee Meeting on Advanced Fuels with Reduced Actinide Generation was organized. The aim of the meeting was to highlight current research activities and to identify new research areas and fields of possible co-operation. The scope of the meeting included advanced fuels for all types of nuclear reactors: light water reactors, heavy water reactors, high temperature reactors, fast reactors, molten salt reactors and for accelerator driven systems. Other topics covered a wide range of investigations made, or to be made in the Member States. Refs, figs, tabs

Effects of low dose ionizing radiation in childhood and youth, in medicine, industry and environment, at the working place. Proceedings

International Nuclear Information System (INIS)

Koehnlein, W.; Nussbaum, R.H.

2001-01-01

These proceedings contain the full texts of all lectures and posters presented at the meeting. The topics are as follows: Occupational radiation exposure, environmental radiation exposure due to radon and neutron radiation from Castor fuel casks, cancer resulting from radiation exposure, diseases other than cancer resulting from radiation exposure, epidemiological studies, mechanisms of biological radiation effects, benefits and risks of medical radiation exposure, radiation monitoring and ambient radiation monitoring. (MG)

Procedural Justice in Dutch Administrative Court Proceedings

Directory of Open Access Journals (Sweden)

André Verburg

2014-11-01

Full Text Available In this paper we discuss recent developments in administrative court proceedings in the Netherlands, called the New Approach. Along with developments leading to the New Approach, it became clear that the insights from research on procedural justice deserve particular attention. The goals of the judge's actions in this respect are both that the proceedings are fair and just and that parties perceive the way they are being treated during proceedings as fair and just.Within the New Approach we discern five procedural justice elements: (1 respect, (2 voice and due consideration, (3 some influence on how proceedings will continue, (4 an explanation of how the proceedings will continue and (5 direct interpersonal contact.The introduction of the New Approach shows two important bottlenecks in Dutch administrative court proceedings, which are (i the possible or supposed collision between legally right outcomes and  procedural justice and (ii the lack of uniformity and predictability.Although what we describe and discuss in this paper focuses on the Dutch situation, many of these considerations apply to administrative court proceedings in other countries. The themes and difficulties that face the administrative law judge seem to be common to many countries.

Burnup effect on nuclear fuel cycle cost using an equilibrium model

International Nuclear Information System (INIS)

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

2014-01-01

The degree of fuel burnup is an important technical parameter to the nuclear fuel cycle, being sensitive and progressive to reduce the total volume of process flow materials and eventually cut the nuclear fuel cycle costs. This paper performed the sensitivity analysis of the total nuclear fuel cycle costs to changes in the technical parameter by varying the degree of burnups in each of the three nuclear fuel cycles using an equilibrium model. Important as burnup does, burnup effect was used among the cost drivers of fuel cycle, as the technical parameter. The fuel cycle options analyzed in this paper are three different fuel cycle options as follows: PWR-Once Through Cycle(PWR-OT), PWR-MOX Recycle, Pyro-SFR Recycle. These fuel cycles are most likely to be adopted in the foreseeable future. As a result of the sensitivity analysis on burnup effect of each three different nuclear fuel cycle costs, PWR-MOX turned out to be the most influenced by burnup changes. Next to PWR-MOX cycle, in the order of Pyro-SFR and PWR-OT cycle turned out to be influenced by the degree of burnup. In conclusion, the degree of burnup in the three nuclear fuel cycles can act as the controlling driver of nuclear fuel cycle costs due to a reduction in the volume of spent fuel leading better availability and capacity factors. However, the equilibrium model used in this paper has a limit that time-dependent material flow and cost calculation is impossible. Hence, comparative analysis of the results calculated by dynamic model hereafter and the calculation results using an equilibrium model should be proceed. Moving forward to the foreseeable future with increasing burnups, further studies regarding alternative material of high corrosion resistance fuel cladding for the overall

Advanced materials for alternative fuel capable directly fired heat engines

Energy Technology Data Exchange (ETDEWEB)

Fairbanks, J.W.; Stringer, J. (eds.)

1979-12-01

The first conference on advanced materials for alternative fuel capable directly fired heat engines was held at the Maine Maritime Academy, Castine, Maine. It was sponsored by the US Department of Energy, (Assistant Secretary for Fossil Energy) and the Electric Power Research Institute, (Division of Fossil Fuel and Advanced Systems). Forty-four papers from the proceedings have been entered into EDB and ERA and one also into EAPA; three had been entered previously from other sources. The papers are concerned with US DOE research programs in this area, coal gasification, coal liquefaction, gas turbines, fluidized-bed combustion and the materials used in these processes or equipments. The materials papers involve alloys, ceramics, coatings, cladding, etc., and the fabrication and materials listing of such materials and studies involving corrosion, erosion, deposition, etc. (LTN)

Management and storage of spent nuclear fuel at research and test reactors. Proceedings of an advisory group meeting

International Nuclear Information System (INIS)

1996-08-01

Irradiated fuel from research and test reactors has been stored at various facilities for several decades. As these facilities age and approach or exceed their original design lifetimes, there is mounting concern about closure of the fuel cycle and about the integrity of ageing fuels from the materials point of view as well as some concern about the loss of self-protection of the fuels as their activity decays. It is clear that an international effort is necessary to give these problems sufficient exposure and to ensure that work continues on appropriate solutions. The future of nuclear research, with its many benefits to mankind, is in jeopardy in some countries, especially countries without nuclear power programmes, because effective solutions for extended interim storage and final disposition of spent research reactor fuels are not yet available. An advisory Group meeting was convened in Vienna to consider a Database on the Management and Storage of Spent Nuclear Fuel from Research and Test Reactors. Sixteen experts from sixteen different countries participated in the Advisory Group meeting and presented country reports, which together represent an overview of the technologies used in spent fuel management and storage at research and test reactors world-wide. The sixteen country reports together with the database summary are presented in this publication. Refs, figs, tabs

Proceedings of 14th international workshop on Asian network for accelerator-driven system and nuclear transmutation technology (ADS-NTT 2016)

International Nuclear Information System (INIS)

Pyeon, Cheol Ho

2016-09-01

The proceedings describe the current status on research and development (R and D) of accelerator-driven system (ADS) and nuclear transmutation techniques (NTT), including nuclear data, accelerator techniques, Pb-Bi target, fuel technologies and reactor physics, in East Asian countries: China, Korea and Japan. The proceedings also include all presentation materials presented in 'the 14th International Workshop on Asian Network for ADS and NTT (ADS-NTT2016)' held at Mito, Japan on 5th September, 2016. The objective of this workshop is to make actual progress of ADS R and D especially in East Asian countries, as well as in European countries, through sharing mutual interests and conducting the information exchange each other. The report is composed of these following items: Presentation materials: ADS-NTT 2016. (author)

IGORR-IV: Proceedings of the fourth meeting of the International Group On Research Reactors

International Nuclear Information System (INIS)

Rosenbalm, K.F.

1995-01-01

The fourth meeting of the International Group on Research Reactors (IGORR-IV) was attended by was good 55 registered participants from 28 organizations in 13 countries, which compares well with the previous meetings. Twenty-nine papers were presented in five sessions over the two-day meeting. Session subjects were: Operating Research Reactors and Facility Upgrades; Research Reactors in Desin and Construction; Research, Development, and Analysis Results of Thermal Hydraulic Calculations, U 3 Si 2 Fuel Performance and Faibrication; Structural Materials Performance; Neutronics; Severe Accident analysis. Written versions of the papers or hard copies of the viewgraphs used are published in these Proceedings

Fuels from biomass. Potentials, concepts, competitive situation with regard to combustion; Kraftstoffe aus Biomassen. Potentiale, Konzepte, Konkurrenzsituationen zur Verbrennung

Energy Technology Data Exchange (ETDEWEB)

Behrendt, F.; Neubauer, Y. [Technische Univ. Berlin (Germany). Fachgebiet Energieverfahrenstechnik

2006-07-01

Liquid fuels are today something of an elixir of life for the industrialised societies and will continue to be so for the foreseeable future. Mobility is dependent on the availability of petrol, diesel and kerosine. Whereas the introduction of alternative vehicle drives is expected to proceed only stepwise over a period of decades, the origin of liquid fuels will change fundamentally. This will involve a shift away from crude oil towards the synthesis of fuels from natural gas, coal and biomass. It will also lead to a revival of long-known technical concepts such as Fischer-Tropsch synthesis or the direct liquefaction of source materials, albeit using significantly refined techniques.

Uranium Resource Availability Analysis of Four Nuclear Fuel Cycle Options

International Nuclear Information System (INIS)

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

2013-01-01

Making the national policy regarding nuclear fuel cycle option, the policy should be established in ways that nuclear power generation can be maintained through the evaluation on the basis of the following aspects. To establish the national policy regarding nuclear fuel cycle option, that must begin with identification of a fuel cycle option that can be best suited for the country, and the evaluation work for that should be proceeded. Like all the policy decision, however, a certain nuclear fuel cycle option cannot be superior in all aspects of sustain ability, environment-friendliness, proliferation-resistance, economics, technologies, which make the comparison of the fuel cycle options very complicated. For such a purpose, this paper set up four different fuel cycle of nuclear power generation considering 2nd Comprehensive Nuclear Energy Promotion Plan(CNEPP), and analyzed material flow and features in steady state of all four of the fuel cycle options. As a result of an analysis on material flow of each nuclear fuel cycle, it was analyzed that Pyro-SFR recycling is most effective on U resource availability among four fuel cycle option. As shown in Figure 3, OT cycle required the most amount of U and Pyro-SFR recycle consumed the least amount of U. DUPIC recycling, PWR-MOX recycling, and Pyro-SFR recycling fuel cycle appeared to consumed 8.2%, 12.4%, 39.6% decreased amount of uranium respectively compared to OT cycle. Considering spent fuel can be recycled as potential energy resources, U and TRU taken up to be 96% is efficiently used. That is, application period of limited uranium natural resources can be extended, and it brings a great influence on stable use of nuclear energy

Remote technology related to the handling, storage and disposal of spent fuel. Proceedings of a technical committee meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-11-01

Reduced radiation exposure, greater reliability and cost savings are all potential benefits of the application of remote technologies to the handling of spent nuclear fuel. Remote equipment and technologies are used to some extent in all facilities handling fuel and high-level wastes whether they are for interim storage, processing/repacking, reprocessing or disposal. In view of the use and benefits of remote technologies, as well as recent technical and economic developments in the area, the IAEA organized the Technical Committee Meeting (TCM) on Remote Technology Related to the Handling, Storage and/or Disposal of Spent Fuel. Twenty-one papers were presented at the TCM, divided into five general areas: 1. Choice of technologies; 2. Use of remote technologies in fuel handling; 3. Use of remote technologies for fuel inspection and characterization; 4. Remote maintenance of facilities; and 5. Current and future developments. Refs, figs and tabs.

Turning Perspective in Photoelectrocatalytic Cells for Solar Fuels.

Science.gov (United States)

Perathoner, Siglinda; Centi, Gabriele; Su, Dangsheng

2016-02-19

The development of new devices for the use and storage of solar energy is a key step to enable a new sustainable energy scenario. The route for direct solar-to-chemical energy transformation, especially to produce liquid fuels, represents a necessary element to realize transition from the actual energy infrastructure. Photoelectrocatalytic (PECa) devices for the production of solar fuels are a key element to enable this sustainable scenario. The development of PECa devices and related materials is of increasing scientific and applied interest. This concept paper introduces the need to turn the viewpoint of research in terms of PECa cell design and related materials with respect to mainstream activities in the field of artificial photosynthesis and leaves. As an example of a new possible direction, the concept of electrolyte-less cell design for PECa cells to produce solar fuels by reduction of CO2 is presented. The fundamental and applied development of new materials and electrodes for these cells should proceed fully integrated with PECa cell design and systematic analysis. A new possible approach to develop semiconductors with improved performances by using visible light is also shortly presented. © 2016 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Proceedings of the international meeting on development, fabrication and application of reduced enrichment fuels for research and test reactors

International Nuclear Information System (INIS)

1983-08-01

Separate abstracts were prepared for each of the papers presented in the following areas: (1) Reduced Enrichment Fuels for Research and Test Reactors (RERTR) Program Status; (2) Fuel Development; (3) Fuel Demonstrations; (4) General Topics; and (5) Specific Reactor Applications

The 12th International ICIT Conference Progress in Cryogenics and Isotopes Separation. Proceedings

International Nuclear Information System (INIS)

Stefanescu, Ioan

2006-01-01

The proceedings of the 12th International ICIT Conference Progress in Cryogenics and Isotopes Separation held in Caciulata, Romania on 25-27 October 2006 contain plenary lectures (11 papers) and 7 sections addressing the following subject matters: Section 1. Stable Isotopes Physics. Technologies and Applications (6 papers); Section 2. Cryogenics Technologies and Equipment (6 papers); Section 3. Science and Materials Engineering (18 papers); Section 4. Nuclear Power (17 papers); Section 5. Hydrogen and Fuel Cells (14 papers); Section 6. Environmental Protection. Industrial Risk (14 papers); Section 7. Laboratory Analysis Methods (13 papers). A number of 40 papers are available in abstract form only and accordingly full text entered the corresponding records

DESIGNING AN OPPORTUNITY FUEL WITH BIOMASS AND TIRE-DERIVED FUEL FOR COFIRING AT WILLOW ISLAND GENERATING STATION

International Nuclear Information System (INIS)

K. Payette; D. Tillman

2001-01-01

During the period October 1, 2000 - December 31, 2000, Allegheny Energy Supply Co., LLC (Allegheny) executed a Cooperative Agreement with the National Energy Technology Laboratory to implement a major cofiring demonstration at the Willow Island Generating Station Boiler No.2. Willow Island Boiler No.2 is a cyclone boiler. Allegheny also will demonstrate separate injection cofiring at the Albright Generating Station Boiler No.3, a tangentially fired boiler. The Allegheny team includes Foster Wheeler as its primary subcontractor. Additional subcontractors are Cofiring Alternatives and N.S. Harding and Associates. This report summarizes the activities associated with the Designer Opportunity Fuel program, and demonstrations at Willow Island and Albright Generating Stations. The second quarter of the project involved completing the designs for each location. Further, geotechnical investigations proceeded at each site. Preparations were made to perform demolition on two small buildings at the Willow Island site. Fuels strategies were initiated for each site. Test planning commenced for each site. A groundbreaking ceremony was held at the Willow Island site on October 18, with Governor C. Underwood being the featured speaker

Proceedings of the international meeting on research and test reactor core conversions from HEU to LEU fuels

International Nuclear Information System (INIS)

1983-09-01

Separate abstracts have been prepared for each paper presented in the following areas of interest: (1) fuel development; (2) post-irradiation examinations; (3) reprocessing; (4) thermite reaction; (5) fuel fabrication; (6) element tests; (7) core tests; (8) criticals; (9) shipping; and (10) reactors and methods

Solid State Energy Conversion Alliance 2nd Annual Workshop Proceedings

International Nuclear Information System (INIS)

National Energy Technology Laboratory

2001-01-01

The National Energy Technology Laboratory (NETL) and the Pacific Northwest National Laboratory (PNNL) are pleased to provide the proceedings of the second annual Solid State Energy Conversion Alliance (SECA) Workshop held on March 29-30, 2001 in Arlington. The package includes the presentations made during the workshop, a list of participants, and the results of the breakout sessions. Those sessions covered stack materials and processes, power electronics, balance of plant and thermal integration, fuel processing technologies, and stack and system performance modeling. The breakout sessions have been reported as accurately as possible; however, due to the recording and transcription process errors may have occurred. If you note any significant omissions or wish to provide additional information, we welcome your comments and hope that all stakeholder groups will use the enclosed information in their planning endeavors

Solid State Energy Conversion Alliance 2nd Annual Workshop Proceedings

Energy Technology Data Exchange (ETDEWEB)

National Energy Technology Laboratory

2001-03-30

The National Energy Technology Laboratory (NETL) and the Pacific Northwest National Laboratory (PNNL) are pleased to provide the proceedings of the second annual Solid State Energy Conversion Alliance (SECA) Workshop held on March 29-30, 2001 in Arlington. The package includes the presentations made during the workshop, a list of participants, and the results of the breakout sessions. Those sessions covered stack materials and processes, power electronics, balance of plant and thermal integration, fuel processing technologies, and stack and system performance modeling. The breakout sessions have been reported as accurately as possible; however, due to the recording and transcription process errors may have occurred. If you note any significant omissions or wish to provide additional information, we welcome your comments and hope that all stakeholder groups will use the enclosed information in their planning endeavors.

A new criterion for defective used nuclear fuel in dry storage condition

Energy Technology Data Exchange (ETDEWEB)

Desgranges, Lionel [CEA Cadarache Bat 316 13108Saint-Paul lez Durance (France); Poulesquen, Arnaud; Ferry, Cecile [CEA Saclay Bat. 450 point courrier no 40 - 91191 Gif-sur-Yvette cedex (France)

2008-07-01

In the frame of the PRECCI program, the mechanisms associated to the oxidation of used nuclear fuel were studied. Experiments on un-irradiated UO{sub 2}, evidenced that the oxidation proceeded in three stages (namely UO{sub 2} {yields} U{sub 4}O{sub 9}, U{sub 4}O{sub 9} {yields} U{sub 3}O{sub 7} and U{sub 3}O{sub 7} {yields} U{sub 3}O{sub 8}) instead of 2 as previously proposed in literature. Experiments on irradiated fuel fragments evidenced the existence of an oxidation front inside the fuel fragment associated to some fission gas release. The degradation of a fuel rod slice was simulated in situ with CROCODILE experiment, and shown to be due to the fuel swelling. Finally a new criterion was proposed defining a safe duration for defective used fuel in a dry air facility in the case of an accident scenario where a breach in a container would put a defective fuel rod in contact with atmosphere. The criterion is related to the time needed to form a given thickness of U{sub 4}O{sub 9{gamma}}{sub +{psi}} with a higher stoichiometry than a given value, in irradiated grains. This U{sub 4}O{sub 9{gamma}}{sub +{psi}} layer thickness is assumed to simulate the onset of the ceramic fragmentation. This safety duration was calculated thanks to a new modeling of fuel fragment oxidation.

The roles of industry for internationalization of nuclear fuel cycle

International Nuclear Information System (INIS)

Choi, Jor-Shan; Oda, Takuji; Tanaka, Satoru; Kuno, Yusuke

2011-01-01

To meet increasing energy demand and counter climate change, nuclear energy is expected to expand during the next decades in both developed and developing countries. The Fukushima accident in Japan in March 2011 may dampen the expansion, but it would proceed and continue when the Fukushima lessons are learned. This expansion, most visibly in Asian would be accompanied with complex and intractable challenges to global stability and nuclear security, notably, on 'how to reduce security and proliferation concerns if nuclear power is introduce and when used fuel is generated in less stable regions of the world?' The answers to the question may lie in the possibility of multilateral control of nuclear materials and technologies in the nuclear fuel cycle, including the provision of a 'cradle-to-grave' fuel cycle service, presumably by the nuclear industries and their respective governments. This paper evaluates the importance of such industry-government cooperative initiative and explores into the roles which the nuclear industry should play to ensure that the world would not be 'creating proliferation when expanding the application of nuclear power to emerging nuclear countries'. (author)

Panorama 2007: Potential biomass mobilization for bio-fuel production worldwide, in Europe and in France

International Nuclear Information System (INIS)

Lorne, D.

2007-01-01

One key factor in ensuring the success of bio-fuel technologies, which are expected to see high growth, is the availability of biomass resources. Although the targets set in Europe and France for the replacement of petroleum products in the transport sector by 2010 can be met by converting farm surpluses into biofuels, in order to proceed further, it will be necessary to mobilize a resource that is more abundant and potentially less costly: ligno-cellulosic materials, i.e. wood or straw. The future of biofuels depends on establishing the much-awaited 'second generation' bio-fuel pathways able to convert ligno-cellulosic materials to ethanol, bio-diesel and bio-kerosene. (author)

Interactions of hydrazine, ferrous sulfamate, sodium nitrite, and nitric acid in nuclear fuel processing solutions

International Nuclear Information System (INIS)

Gray, L.W.

1977-03-01

Hydrazine and ferrous sulfamate are used as reductants in a variety of nuclear fuel processing solutions. An oxidant, normally sodium nitrite, must frequently be added to these nitric acid solutions before additional processing can proceed. The interactions of these four chemicals have been studied under a wide variety of conditions using a 2/sup p/ factorial experimental design to determine relative reaction rates for desired reactions and side reactions. Evidence for a hydrazine-stabilized, sulfamic acid--nitrous acid intermediate was obtained; this intermediate can hydrolyze to ammonia or decompose to nitrogen. The oxidation of Fe 2+ by NO 2 - was shown to proceed at about the same rate as the scavenging of NO 2 - by sulfamic acid. Various side reactions are discussed

Proceedings of 11th international workshop on Asian network for accelerator-driven system and nuclear transmutation technology (ADS+NTT 2013)

International Nuclear Information System (INIS)

Pyeon, Cheol Ho

2014-01-01

The proceedings describe the current status on research and development (R and D) of accelerator-driven system (ADS) and nuclear transmutation techniques (NTT), including nuclear data, accelerator techniques, Pb-Bi target, fuel technologies and reactor physics, in East Asian countries: Korea, China and Japan. The proceedings also include all presentation materials presented in 'the 11th International Workshop on Asian Network for ADS and NTT (ADS+NTT 2013)' held at the Seoul National University, Seoul, Korea on 12th and 13th December, 2013. The objective of this workshop is to make actual progress of ADS R and D especially in East Asian countries, as well as in European countries, through sharing mutual interests and conducting the information exchange each other. The report is composed of these following items: Presentation materials: ADS+NTT 2013. (author)

Influence of high dose irradiation on core structural and fuel materials in advanced reactors

International Nuclear Information System (INIS)

1998-08-01

The IAEA International Working Group on Fast Reactors (IWGFR) periodically organizes meeting to discuss and review important aspects of fast reactor technology. The fifth meeting held in Obninsk, Russian Federation, 16-19 June 1997, was devoted to the influence of high dose irradiation on the mechanical properties of reactor core structural and fuel materials. The proceedings includes the papers submitted at this meeting each with a separate abstract

Procedures and techniques for the management of experimental fuels from research and test reactors. Proceedings of an advisory group meeting

International Nuclear Information System (INIS)

1999-04-01

Almost all countries that have undertaken fuel development programs for power, research or military reactors have experimental and exotic fuels, either stored at the original research reactors where they have been tested or at some away-from-reactor storage facility. These spent fuel liabilities cannot follow the standard treatment recognized for modern power reactor fuels. They include experimental and exotic fuels ranging from liquids to coated spheres and in configurations ranging from full test assemblies to post irradiation examination specimens set in resin. This document contains an overview of the extent of the problem of managing experimental and exotic fuels from research and test reactors and an expert evaluation of the overall situation in countries which participated in the meeting

Sixth meeting of the International Working Group on Water Reactor Fuel Performance and Technology, Vienna, 14-15 May 1984

International Nuclear Information System (INIS)

1984-10-01

The summary report of the 6th meeting of the IWGFPT had been approved. The review of IWGFPT activities since the last meeting are given in Appendix 3, which is a list of meetings and proceedings publications for that period. Co-ordinated research programmes were discussed in the fields of fuel element cladding interaction with water coolant in power reactors and examination and documentation methodology for water reactor fuel. The main activities for the next three years were settled. The next Working Group meeting will be held at the VIC, November 1985

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences; Search. Search. Proceedings – Mathematical Sciences. Title. Author. Keywords. Fulltext. Submit. Proceedings – Mathematical Sciences. Current Issue : Vol. 128, Issue 2. Current Issue Volume 128 | Issue 2. April 2018. Home · Volumes & Issues · Special Issues ...

CAPRICORN subchannel code for sodium boiling in LMFBR fuel bundles

International Nuclear Information System (INIS)

Padilla, A. Jr.; Smith, D.E.; O'Dell, L.D.

1983-01-01

The CAPRICORN computer code analyzes steady-state and transient, single-phase and boiling problems in LMFBR fuel bundles. CAPRICORN uses the same type of subchannel geometry as the COBRA family of codes and solves a similar system of conservation equations for mass, momentum, and energy. However, CAPRICORN uses a different numerical solution method which allows it to handle the full liquid-to-vapor density change for sodium boiling. Results of the initial comparison with data (the W-1 SLSF pipe rupture experiment) are very promising and provide an optimistic basis for proceeding with further development

4 CFR 28.133 - Stay proceedings.

Science.gov (United States)

2010-01-01

... GOVERNMENT ACCOUNTABILITY OFFICE GENERAL PROCEDURES GOVERNMENT ACCOUNTABILITY OFFICE PERSONNEL APPEALS BOARD; PROCEDURES APPLICABLE TO CLAIMS CONCERNING EMPLOYMENT PRACTICES AT THE GOVERNMENT ACCOUNTABILITY OFFICE Corrective Action, Disciplinary and Stay Proceedings § 28.133 Stay proceedings. (a) Prior to the effective...

IGORR-IV: Proceedings of the fourth meeting of the International Group On Research Reactors

Energy Technology Data Exchange (ETDEWEB)

Rosenbalm, K F [comp.

1995-07-01

The fourth meeting of the International Group on Research Reactors (IGORR-IV) was attended by was good 55 registered participants from 28 organizations in 13 countries, which compares well with the previous meetings. Twenty-nine papers were presented in five sessions over the two-day meeting. Session subjects were: Operating Research Reactors and Facility Upgrades; Research Reactors in Desin and Construction; Research, Development, and Analysis Results of Thermal Hydraulic Calculations, U{sub 3}Si{sub 2} Fuel Performance and Faibrication; Structural Materials Performance; Neutronics; Severe Accident analysis. Written versions of the papers or hard copies of the viewgraphs used are published in these Proceedings.

Proceedings of the first analysis meeting on JUPITER Program. Report SN-241-80-14

Energy Technology Data Exchange (ETDEWEB)

NONE

1980-09-01

These proceedings provide an analysis of the JUPITER Experiment in ZPPR-9. A general description of data and methods is provided along with discussions of criticality, reaction rate ratio and reaction rate, Doppler and sample reactivity worth, sodium void worth, and control rod worth. Topics provided are: Considerations on a Critical Experiment Program for a Large Fast Breeder Reactor; Analysis of Sodium Void Worths in ZPPR-3 Modified Phase 3 Core; Fuel Pin and Subassembly Heterogeneity Effect on Neutronics Properties of a Fast Power Reactor; and An Evaluation Method for Mesh Size Effects in Neutron Diffusion Calculations. The individual topics have been cataloged separately.

34 CFR 303.423 - Convenience of proceedings; timelines.

Science.gov (United States)

2010-07-01

... 34 Education 2 2010-07-01 2010-07-01 false Convenience of proceedings; timelines. 303.423 Section 303.423 Education Regulations of the Offices of the Department of Education (Continued) OFFICE OF... Parents and Children § 303.423 Convenience of proceedings; timelines. (a) Any proceeding for implementing...

‘Re-defining’ the conference proceedings – let’s add some music and create a singing proceedings

DEFF Research Database (Denmark)

Darula, Radoslav

2015-01-01

Nowadays the conference proceedings provide only a static content in a form of a book, which may be supplemented with a CD or an additional content on a web-server of the conference. However why not to try to create a ‘multimedial’ paper version of the proceedings? As for animations, the concept...... processing elements, sound was added to the book of proceedings. At the day of submission the first working prototype was assembled and tested. It is not perfect, so some of possible improvements identified are listed in the paper as well....

Workshop on development of radionuclide getters for the Yucca Mountain waste repository: proceedings.

Energy Technology Data Exchange (ETDEWEB)

Moore, Robert Charles; Lukens, Wayne W. (Lawrence Berkeley National Laboratory)

2006-03-01

The proposed Yucca Mountain repository, located in southern Nevada, is to be the first facility for permanent disposal of spent reactor fuel and high-level radioactive waste in the United States. Total Systems Performance Assessment (TSPA) analysis has indicated that among the major radionuclides contributing to dose are technetium, iodine, and neptunium, all of which are highly mobile in the environment. Containment of these radionuclides within the repository is a priority for the Yucca Mountain Project (YMP). These proceedings review current research and technology efforts for sequestration of the radionuclides with a focus on technetium, iodine, and neptunium. This workshop also covered issues concerning the Yucca Mountain environment and getter characteristics required for potential placement into the repository.

Career Opportunities for the Future. Fueling the Education Explosion: Proceedings of Conference 3 (Cleveland, Ohio, March 29-30, 1984).

Science.gov (United States)

Gardner, Mary, Ed.; Reed-Mundell, Charlene, Ed.

These proceedings contain 12 presentations from a conference which focused on forecasts of jobs in the 1990s and into the 21st century. The keynote address (Marvin Cetron) shows the need for reform in the American education system with illustrations drawn from the economic and employment situations in foreign countries. He makes predictions of…

RERTR program activities related to the development and application of new LEU fuels

International Nuclear Information System (INIS)

Travelli, A.

1983-01-01

The statue of the U.S. Reduced Enrichment Research and Test Reactor (RERTR) Program is reviewed. After a brief outline of RERTR Program objectives and goals, program accomplishments are discussed with emphasis on the development, demonstration and application of new LEU fuels. Most program activities have proceeded as planned, and a combination of two silicide fuels (U 3 Si 2 -Al and U 3 Si-Al) holds excellent promise for achieving the long-term program goals. Current plans and schedules project the uranium density of qualified RERTR fuels for plate-type reactors to grow by approximately 1 g U/cm 3 each year, from the current 1.7 g U/cm 3 to the 7.0 g U/cm 3 which will be reached in late 1988. The technical needs of research and test reactors for HEU exports are also forecasted to undergo a gradual but dramatic decline in the coming years

Preparation of a data bank system for isotope correlation on spent nuclear fuels

International Nuclear Information System (INIS)

Nakahara, Yoshinori; Umezawa, Hirokazu

1981-11-01

For the purposes of studying isotope correlation on spent nuclear fuels and its applicability to safeguards technology of nuclear material, a data bank system has been prepared on the basis of a FACOM M200 computer in JAERI. Spent fuels data of fabrication, irradiation history, reactor operator's burnup calculation, and reprocessing are stored in four kinds of data files: (1) Fuel assembly data file, (2) reprocessing batch data file, (3) plutonium product data file, and (4) uranium product data file. Corrections for decay and for mixing from adjoining batches are made and the corrected data are also kept in the files. A wide variety of variables may be derived from the isotopic and other data stored and subjected to optional statistical treatments such as regression analysis and paired comparison. Computer language used for the system was FORTRAN-IV. The system can be operated in a conversational mode with graphic indication, so that one may proceed such a statistical analysis immediately under various conditions of calculation. (author)

Study on performance of blended fuel PPO - Diesel at generator

Science.gov (United States)

Prasetyo, Joni; Prasetyo, Dwi Husodo; Murti, S. D. Sumbogo; Adiarso, Priyanto, Unggul

2018-02-01

Bio-energy is renewable energy made from plant. Biomass-based energy sources are potentially CO2 neutral and recycle the same carbon atoms. In order to reduce pollution caused by fossil fuel combustion either for mechanical or electrical energy generation, the performance characteristic of purified palm oil blends are analyzed at various ratios. Bio-energy, Pure Plant Oil, represent a sustainable solution.A generator has been modified due to adapt the viscosity ofblended fuel, PPO - diesel, by pre-heating. Several PPO - diesel composition and injection timing were tested in order to investigate the characteristic of mixed fuel with and without pre-heating. The term biofuel refers to liquid or gaseous fuels for the internal combustion engines that are predominantly produced fro m biomass. Surprising result showed that BSFC of blended PPO - diesel was more efficient when injection timing set more than 15° BTDC. The mixed fuel produced power with less mixed fuel even though the calorie content of diesel is higher than PPO. The most efficient was 20% PPO in diesel with BSFC 296 gr fuel / kwh rather than 100% diesel with BSFC 309 gr fuel / kwh at the same injection timing 18° BTDC with pre-heating. The improvement of BSFC is caused by heating up of mixed fuel which it added calorie in the mixed fuel. Therefore, the heating up of blended PPO - diesel is not only to adapt the viscosity but also improving the efficiency of fuel usage representing by lower BSFC. In addition, torque of the 20% PPO was also as smooth as 100% diesel representing by almost the same torqueat injection timing 15° BTDC. The AIP Proceedings article template has many predefined paragraph styles for you to use/apply as you write your paper. To format your abstract, use the Microsoft Word template style: Abstract. Each paper must include an abstract. Begin the abstract with the word "Abstract" followed by a period in bold font, and then continue with a normal 9 point font.

9th Pacific Basin Nuclear Conference. Nuclear energy, science and technology - Pacific partnership. Proceedings Volume 2

International Nuclear Information System (INIS)

1994-04-01

The theme of the 9th Pacific Basin Nuclear Conference held in Sydney from 1-6 May 1994, embraced the use of atom in energy production and in science and technology. The focus was on selected topics of current and on-going interest to countries around the Pacific Basin. The two-volume proceedings include both invited and contributed papers which have been indexed separately. This document, Volume 2 covers the following topics: education and training in Nuclear Science, public acceptance, nuclear safety and radiation protection, nuclear fuel resources and their utilisation, research reactors, cyclotrons and accelerators. refs., tabs., figs., ills

Proceedings of 2005 JAEA-KAERI joint seminar on advanced irradiation and PIE technologies

International Nuclear Information System (INIS)

2006-05-01

In this seminar, total participants of over 100 were jointed from JAEA, KAERI, Hanyang University, Chungnam National University, Kyung Hee University, Oarai Branch of Institute for Materials Research (IMR) of Tohoku University, Nippon Nuclear Fuel Development Co., Ltd., Nuclear Development Corporation and others. The technical development and experimental data on the irradiation test and PIE were aggressively discussed in this seminar. Contributed presentations were 35 in three sessions; Current status and future program on irradiation test and PIE (10 presentations), Development of irradiation and PIE technologies (15 presentations) and Evaluation of irradiation and PIE data (10 presentations). Development of instrumented capsule technologies for HANARO irradiation, current PIE activities in each hot laboratory of both countries, development of irradiation capsules in JMTR for the Irradiation Assisted Stress Corrosion Cracking (IASCC) study, development of irradiation and PIE techniques for the safety research on the high burnup fuel, utilization plan of JOYO and development of MOX fuel containing americium have been widely noticed as topic items on irradiation and PIE technologies. This proceedings is containing papers presented in the 2005 JAEA-KAERI Joint Seminar. It also indicates the current status of the aggressive information exchange activity on two fields of irradiation test and PIE technologies between JAEA and KAERI under the Arrangement for the Implementation of Cooperative Research Program mentioned above. The 35 of the presented papers are indexed individually. (J.P.N.)

An overview on the nuclear spent fuel management in Romania

International Nuclear Information System (INIS)

Radu, M.

2001-01-01

The sources of radioactive waste in Romania are users of radiation and radioactive materials in industry (including nuclear electricity generation), medicine, agriculture and research and also the processing of materials that are naturally radioactive, such as uranium ores. The different types of radioactive waste are classified into four categories of waste: excepted waste, low level waste, medium level waste and high level waste. A spent fuel management sub-programme as a part of the Radioactive Waste Management programme was initiated by the former Romanian Electricity Company (RENEL) in 1992. Within the frame of R and D of the Radioactive Waste and Spent Fuel Management Programme, the topics cover investigations, studies and research to identify the sites and the conceptual designs for a Spent Fuel Interim Storage Facility (SFISF) and also a Spent Fuel Disposal Facility (SFDF). Changes in the organization of the nuclear activities of RENEL, involving both responsibilities and financing aspects, led to interruption of the programme. The programme includes study of the main methods and the existing technologies for the design, operation and safety of an interim storage facility (including transport aspects). It also includes analysis of details on the site selection for this facility and for a spent fuel final disposal facility. The achievement of the spent fuel interim storage facility is proceeding. The results from the studies performed in the last years will permit us to prepare the feasibility study next year and the documentation required by our regulatory body for starting the process to obtain a license for a SFISF at Cernavoda. A second phase is the assessment of a long term strategy to select and adopt a proven disposal technology for spent fuel, corresponding with a selected site. The status of the work performed in the frame of this programme and also the situation of the spent fuel from research reactors are presented. (author)

Proceedings of 12th international workshop on Asian network for accelerator-driven system and nuclear transmutation technology (ADS+NTT 2014)

International Nuclear Information System (INIS)

Pyeon, Cheol Ho

2015-01-01

The proceedings describe the current status on research and development (R and D) of accelerator-driven system (ADS) and nuclear transmutation techniques (NTT), including nuclear data, accelerator techniques, Pb-Bi target, fuel technologies and reactor physics, in East Asian countries: China, Japan and Korea. The proceedings also include all presentation materials presented in 'the 12th International Workshop on Asian Network for ADS and NTT (ADS+NTT 2014)' held at the Institute of Nuclear Energy and Safety Technology, Chinese Academy of Sciences, Hefei, China on 15th and 16th December, 2014. The objective of this workshop is to make actual progress of ADS R and D especially in East Asian countries, as well as in European countries, through sharing mutual interests and conducting the information exchange each other. The report is composed of these following items: Presentation materials: ADS+NTT 2014. (author)

Conference proceedings ISES 2014

DEFF Research Database (Denmark)

Christensen, Janne Winther; Peerstrup Ahrendt, Line; Malmkvist, Jens

The 10th Internatinal Equitation Science Conference is held i Denmark from August 6th - 9th 2014. This book of proceedings contaions abstracts of 35 oral and 57 poster presentations within the conference themes Equine Stress, Learning and Training as well as free papers.......The 10th Internatinal Equitation Science Conference is held i Denmark from August 6th - 9th 2014. This book of proceedings contaions abstracts of 35 oral and 57 poster presentations within the conference themes Equine Stress, Learning and Training as well as free papers....

4 CFR 28.132 - Disciplinary proceedings.

Science.gov (United States)

2010-01-01

... Corrective Action, Disciplinary and Stay Proceedings § 28.132 Disciplinary proceedings. (a) If the General Counsel determines after any investigation under 31 U.S.C. 752(b) that disciplinary action should be... ordering disciplinary action. (d) A final order of the Board may order disciplinary action consisting of...

29 CFR 2204.104 - Proceedings covered.

Science.gov (United States)

2010-07-01

... Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH REVIEW COMMISSION IMPLEMENTATION OF THE EQUAL ACCESS TO JUSTICE ACT IN PROCEEDINGS BEFORE THE OCCUPATIONAL SAFETY AND HEALTH REVIEW... covered are the following proceedings under section 10(c), 29 U.S.C. 659(c), of the OSH Act: (a) Contests...

Fracture of Zircaloy cladding by interactions with uranium dioxide pellets in LWR fuel rods. Technical report 10

International Nuclear Information System (INIS)

Smith, E.; Ranjan, G.V.; Cipolla, R.C.

1976-11-01

Power reactor fuel rod failures can be caused by uranium dioxide fuel pellet-Zircaloy cladding interactions. The report summarizes the current position attained in a detailed theoretical study of Zircaloy cladding fracture caused by the growth of stress corrosion cracks which form near fuel pellet cracks as a consequence of a power increase after a sufficiently high burn-up. It is shown that stress corrosion crack growth in irradiated Zircaloy must be able to proceed at very low stress intensifications if uniform friction effects are operative at the fuel-cladding interface, when the interfacial friction coefficient is less than unity, when a symmetric distribution of fuel cracks exists, and when symmetric interfacial slippage occurs (i.e., ''uniform'' conditions). Otherwise, the observed fuel rod failures must be due to departures from ''uniform'' conditions, and a very high interfacial friction coefficient and particularly fuel-cladding bonding, are means of providing sufficient stess intensification at a cladding crack tip to explain the occurrence of cladding fractures. The results of the investigation focus attention on the necessity for reliable experimental data on the stress corrosion crack growth behavior of irradiated Zircaloy, and for further investigations on the correlation between local fuel-cladding bonding and stress corrosion cracking

13 CFR 120.347 - Use of proceeds.

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2010-01-01

... Loans International Trade Loans § 120.347 Use of proceeds. The Borrower may use loan proceeds to acquire... to produce goods or services involved in international trade, and to develop and penetrate foreign...

19 CFR 212.03 - Proceedings covered.

Science.gov (United States)

2010-04-01

... 19 Customs Duties 3 2010-04-01 2010-04-01 false Proceedings covered. 212.03 Section 212.03 Customs Duties UNITED STATES INTERNATIONAL TRADE COMMISSION INVESTIGATIONS OF UNFAIR PRACTICES IN IMPORT TRADE IMPLEMENTATION OF THE EQUAL ACCESS TO JUSTICE ACT General Provisions § 212.03 Proceedings covered. (a) The Act...

Proceedings of the 1978 international meeting on reduced enrichment for research and test reactors

Energy Technology Data Exchange (ETDEWEB)

Travelli, A [Argonne National Laboratory, Argonne, IL (United States)

1993-08-01

November 9-10, 1978, marked the first of what has become an annual event - the International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR). The RERTR Program had been started only three months earlier, and the meeting brought together for the first time many people who became major program participants in later years. This first meeting emphasized fuel development, and while it established the basis for all later meetings, it was unique in several respects. It was a time of feeling each other out, and of sharing new ideas, concerns, and hopes. In the absence of an established precedent, a number of participants came with written papers while others made only verbal presentations. Informality added spice and special importance to the discussions at the end of each presentation and, especially, to the panel discussion at the end of the meeting. An important achievement was a consensus on near-, medium-, and long-term density goals for the various fuels. This consensus resulted in a list written on the blackboard at the end of the panel discussion, and reproduced on page 216, which outlined the goals of each fabricator. Luckily, both presentations and discussions were recorded on audio tape. These recordings were transcribed and used to complete the informal presentations and to append the discussions at the end of each presentation. Considerable effort was expended in clearing the transcribed papers and key discussions with the participants. A few issues could not be resolved quickly, and in the frantic rush of those early years, these proceedings were set aside. Believing that the proceedings of this first meeting are important as a historical record of the beginning of the international RERTR effort, we have recently dusted off the manuscript and finished our editing job.

Proceedings of the 1978 international meeting on reduced enrichment for research and test reactors

International Nuclear Information System (INIS)

Travelli, A.

1993-08-01

November 9-10, 1978, marked the first of what has become an annual event - the International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR). The RERTR Program had been started only three months earlier, and the meeting brought together for the first time many people who became major program participants in later years. This first meeting emphasized fuel development, and while it established the basis for all later meetings, it was unique in several respects. It was a time of feeling each other out, and of sharing new ideas, concerns, and hopes. In the absence of an established precedent, a number of participants came with written papers while others made only verbal presentations. Informality added spice and special importance to the discussions at the end of each presentation and, especially, to the panel discussion at the end of the meeting. An important achievement was a consensus on near-, medium-, and long-term density goals for the various fuels. This consensus resulted in a list written on the blackboard at the end of the panel discussion, and reproduced on page 216, which outlined the goals of each fabricator. Luckily, both presentations and discussions were recorded on audio tape. These recordings were transcribed and used to complete the informal presentations and to append the discussions at the end of each presentation. Considerable effort was expended in clearing the transcribed papers and key discussions with the participants. A few issues could not be resolved quickly, and in the frantic rush of those early years, these proceedings were set aside. Believing that the proceedings of this first meeting are important as a historical record of the beginning of the international RERTR effort, we have recently dusted off the manuscript and finished our editing job

29 CFR 16.104 - Proceedings covered.

Science.gov (United States)

2010-07-01

... future rate or is primarily rule-making is not covered. Proceedings to grant or renew licenses are also... Administration: (i) Proceedings under the Workforce Investment Act at 29 U.S.C. 2936, where the Department... implementing regulations. (ii) Conformity and compliance under the Federal Unemployment Tax Act at 26 U.S.C...

OECD/NEA WGFCS Workshop: Safety Assessment of Fuel Cycle Facilities - Regulatory Approaches and Industry Perspectives

International Nuclear Information System (INIS)

2013-01-01

Nuclear fuel is produced, processed, and stored mainly in industrial-scale facilities. Uranium ores are processed and refined to produce a pure uranium salt stream, Uranium is converted and enriched, nuclear fuel is fabricated (U fuel and U/Pu fuel for the closed cycle option); and spent fuel is stored and reprocessed in some countries (close cycle option). Facilities dedicated to the research and development of new fuel or new processes are also considered as Fuel Cycle Facilities. The safety assessment of nuclear facilities has often been led by the methodology and techniques initially developed for Nuclear Power Plants. As FCFs cover a wide diversity of installations the various approaches of national regulators, and their technical support organizations, for the Safety Assessment of Fuel Cycle Facilities are also diverse, as are the approaches by their industries in providing safety justifications for their facilities. The objective of the Working Group on Fuel Cycle Safety is to advance the understanding for both regulators and operators of relevant aspects of nuclear fuel cycle safety in member countries. A large amount of experience is available in safety assessment of FCFs, which should be shared to develop ideas in this field. To contribute to this task, the Workshop on 'Safety Assessment of Fuel Cycle Facilities - Regulatory Approaches and Industry Perspectives' was held in Toronto, on 27 - 29 September 2011. The workshop was hosted by Canadian Nuclear Safety Commission. The current proceedings provide summary of the results of the workshop with the text of the papers given and presentations made

8 CFR 1240.16 - Application of new procedures or termination of proceedings in old proceedings pursuant to...

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2010-01-01

... termination of proceedings in old proceedings pursuant to section 309(c) of Public Law 104-208. 1240.16 Section 1240.16 Aliens and Nationality EXECUTIVE OFFICE FOR IMMIGRATION REVIEW, DEPARTMENT OF JUSTICE... to section 309(c) of Public Law 104-208. The Attorney General shall have the sole discretion to apply...

4 CFR 28.131 - Corrective action proceedings.

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2010-01-01

... Accounts GOVERNMENT ACCOUNTABILITY OFFICE GENERAL PROCEDURES GOVERNMENT ACCOUNTABILITY OFFICE PERSONNEL APPEALS BOARD; PROCEDURES APPLICABLE TO CLAIMS CONCERNING EMPLOYMENT PRACTICES AT THE GOVERNMENT ACCOUNTABILITY OFFICE Corrective Action, Disciplinary and Stay Proceedings § 28.131 Corrective action proceedings...

Dissolution flowsheet for high flux isotope reactor fuel

Energy Technology Data Exchange (ETDEWEB)

Foster, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2016-09-27

As part of the Spent Nuclear Fuel (SNF) processing campaign, H-Canyon is planning to begin dissolving High Flux Isotope Reactor (HFIR) fuel in late FY17 or early FY18. Each HFIR fuel core contains inner and outer fuel elements which were fabricated from uranium oxide (U₃O₈) dispersed in a continuous Al phase using traditional powder metallurgy techniques. Fuels fabricated in this manner, like other SNF’s processed in H-Canyon, dissolve by the same general mechanisms with similar gas generation rates and the production of H₂. The HFIR fuel cores will be dissolved and the recovered U will be down-blended into low-enriched U. HFIR fuel was previously processed in H-Canyon using a unique insert in both the 6.1D and 6.4D dissolvers. Multiple cores will be charged to the same dissolver solution maximizing the concentration of dissolved Al. The objective of this study was to identify flowsheet conditions through literature review and laboratory experimentation to safely and efficiently dissolve the HFIR fuel in H-Canyon. Laboratory-scale experiments were performed to evaluate the dissolution of HFIR fuel using both Al 1100 and Al 6061 T6 alloy coupons. The Al 1100 alloy was considered a representative surrogate which provided an upper bound on the generation of flammable (i.e., H₂) gas during the dissolution process. The dissolution of the Al 6061 T6 alloy proceeded at a slower rate than the Al 1100 alloy and was used to verify that the target Al concentration in solution could be achieved for the selected Hg concentration. Mass spectrometry and Raman spectroscopy were used to provide continuous monitoring of the concentration of H₂ and other permanent gases in the dissolution offgas allowing the development of H₂ generation rate profiles. The H₂ generation rates were subsequently used to evaluate if a full HFIR core could be dissolved in an H-Canyon dissolver without exceeding 60% of the

Creditors’ claims in bankruptcy proceedings - issues and concerns

Directory of Open Access Journals (Sweden)

Viktor Palić

2013-12-01

Full Text Available A generally accepted rule in the bankruptcy law is that a bankruptcy creditor can file a claim against the debtor only in bankruptcy proceedings. This rule has a legal effect. If the creditor’s claim in the bankruptcy proceeding has not been disputed, the creditor is not able to instigate legal and execution proceedings. Obviously, this applies to financial claims. However, it is not clear whether the above can be applied when the claim is not financial but when it concerns a request for the nullification of a contract. It is of particular interest whether such a request can be made by a counterclaim against the debtor in an ordinary judicial proceeding or only in bankruptcy proceedings. Using a practical example, the authors concluded that it is possible for a creditor to make a request for the nullification of a contract by a counterclaim in a civil lawsuit.

Fuel swelling and interaction layer formation in the SELENIUM Si and ZrN coated U(Mo) dispersion fuel plates irradiated at high power in BR2

Energy Technology Data Exchange (ETDEWEB)

Leenaers, A., E-mail: aleenaer@sckcen.be [Nuclear Materials Science Institute, SCK-CEN, Boeretang 200, 2400 Mol (Belgium); Van den Berghe, S.; Koonen, E.; Kuzminov, V. [Nuclear Materials Science Institute, SCK-CEN, Boeretang 200, 2400 Mol (Belgium); Detavernier, C. [Department of Solid State Sciences, Ghent University, Krijgslaan 281/S1, 9000 Ghent (Belgium)

2015-03-15

In the framework of the SELENIUM project two full size flat fuel plates were produced with respectively Si and ZrN coated U(Mo) particles and irradiated in the BR2 reactor at SCK• CEN. Non-destructive analysis of the plates showed that the fuel swelling profiles of both SELENIUM plates were very similar to each other and none of the plates showed signs of pillowing or excessive swelling at the end of irradiation at the highest power position (local maximum 70% {sup 235}U). The microstructural analysis showed that the Si coated fuel has less interaction phase formation at low burn-up but at the highest burn-ups, defects start to develop on the IL–matrix interface. The ZrN coated fuel, shows a virtual absence of reaction between the U(Mo) and the Al, up to high fission densities after which the interaction layer formation starts and defects develop in the matrix near the U(Mo) particles. It was found and is confirmed by the SELENIUM (Surface Engineering of Low ENrIched Uranium–Molybdenum) experiment that there are two phenomena at play that need to be controlled: the formation of an interaction layer and swelling of the fuel. As the interaction layer formation occurs at the U(Mo)–matrix interface, applying a diffusion barrier (coating) at that interface should prevent the interaction between U(Mo) and the matrix. The U(Mo) swelling, observed to proceed at an accelerating rate with respect to fission density accumulation, is governed by linear solid state swelling and fission gas bubble swelling due to recrystallization of the fuel. The examination of the SELENIUM fuel plates clearly show that for the U(Mo) dispersion fuel to be qualified, the swelling rate at high burn-up needs to be reduced.

Fuel swelling and interaction layer formation in the SELENIUM Si and ZrN coated U(Mo) dispersion fuel plates irradiated at high power in BR2

Science.gov (United States)

Leenaers, A.; Van den Berghe, S.; Koonen, E.; Kuzminov, V.; Detavernier, C.

2015-03-01

In the framework of the SELENIUM project two full size flat fuel plates were produced with respectively Si and ZrN coated U(Mo) particles and irradiated in the BR2 reactor at SCK•CEN. Non-destructive analysis of the plates showed that the fuel swelling profiles of both SELENIUM plates were very similar to each other and none of the plates showed signs of pillowing or excessive swelling at the end of irradiation at the highest power position (local maximum 70% 235U). The microstructural analysis showed that the Si coated fuel has less interaction phase formation at low burn-up but at the highest burn-ups, defects start to develop on the IL-matrix interface. The ZrN coated fuel, shows a virtual absence of reaction between the U(Mo) and the Al, up to high fission densities after which the interaction layer formation starts and defects develop in the matrix near the U(Mo) particles. It was found and is confirmed by the SELENIUM (Surface Engineering of Low ENrIched Uranium-Molybdenum) experiment that there are two phenomena at play that need to be controlled: the formation of an interaction layer and swelling of the fuel. As the interaction layer formation occurs at the U(Mo)-matrix interface, applying a diffusion barrier (coating) at that interface should prevent the interaction between U(Mo) and the matrix. The U(Mo) swelling, observed to proceed at an accelerating rate with respect to fission density accumulation, is governed by linear solid state swelling and fission gas bubble swelling due to recrystallization of the fuel. The examination of the SELENIUM fuel plates clearly show that for the U(Mo) dispersion fuel to be qualified, the swelling rate at high burn-up needs to be reduced.

The analysis of effect of gaseous fission products on service-ability of various types of fuel elements used in research reactors

International Nuclear Information System (INIS)

Vatulin, A.A.; Kulakov, G.V.; Kosaurov, A.A.; Dobrikova, I.V.; Morozov, A.A.

2005-01-01

The analysis of the work to license U-Mo dispersion fuel that has been carried out by program RERTR shows that at high burnups the U-Mo particles interacts with an Al matrix to form porosity in the central areas of the fuel meat. This results leads to change the loading of cladding due to the formation of long-length defects in the fuel meat. As a result, the pressure of gases leads to a larger shape change (pillowing) of fuels and in some instances to their failure. The paper presents the results of modeling pillowing process proceeding in Russia's research reactor fuels of different types (tubular and rod fuels) that is effected by the accumulation and pressure of fission gas in meat porosity. The problem has been resolved in the viscous-plasticity statement using the program MARC for finite element analysis. The behavior of fission gas (FG) in open porosity has been analyzed to reveal the influence of the fuel design on their resistance to the pressure of FG. (author)

Factors determining the long term back end nuclear fuel cycle strategy and future nuclear systems. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

2002-05-01

The Technical Committee Meeting (TCM) was held in Vienna on 8-10 November 1999; it was organized by the International Atomic Energy Agency and attended by 26 participants from 16 Member States. The purpose of the meeting was to exchange information among experts on the back end fuel cycle strategies adopted by Member States; to identify key factors determining the long-term back end fuel cycle strategies; and to assess the applicability of these factors to future nuclear systems. Issues associated with the back end fuel cycle supporting a country's nuclear power programme are technical, economic, institutional and political. This TCM provided an opportunity to address these issues and their impacts to the back end fuel cycles, as well as to identify and assess factors affecting the back end fuel cycle strategies. The discussion was organized ib the following topical sessions: the nuclear fuel cycle; spent fuel management; waste management and repository; plutonium management. This document contains a summary of the meeting and 22 individual papers presented by participants. Each of the papers was indexed separately

Factors determining the long term back end nuclear fuel cycle strategy and future nuclear systems. Proceedings of a technical committee meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-05-01

The Technical Committee Meeting (TCM) was held in Vienna on 8-10 November 1999; it was organized by the International Atomic Energy Agency and attended by 26 participants from 16 Member States. The purpose of the meeting was to exchange information among experts on the back end fuel cycle strategies adopted by Member States; to identify key factors determining the long-term back end fuel cycle strategies; and to assess the applicability of these factors to future nuclear systems. Issues associated with the back end fuel cycle supporting a country's nuclear power programme are technical, economic, institutional and political. This TCM provided an opportunity to address these issues and their impacts to the back end fuel cycles, as well as to identify and assess factors affecting the back end fuel cycle strategies. The discussion was organized ib the following topical sessions: the nuclear fuel cycle; spent fuel management; waste management and repository; plutonium management. This document contains a summary of the meeting and 22 individual papers presented by participants. Each of the papers was indexed separately.

24 CFR 201.51 - Proceeding against the loan security.

Science.gov (United States)

2010-04-01

....51 Proceeding against the loan security. (a) Property improvement loans. (1) After acceleration of maturity on a secured property improvement loan, the lender may either proceed against the loan security... proceeds against the loan security, it may submit an insurance claim only if it complies with the...

Proceedings of national seminar neutron activation analysis

International Nuclear Information System (INIS)

Agus Taftazani; Muhayatun Santoso; Budi Haryanto; Khatarina Oginawati

2010-11-01

Proceedings of national seminar neutron activation analysis in 2010 with the theme of the Role of Nuclear Analytical Techniques in the Field of Environment, Health and Industry. The seminar was organized by Indonesians Neutron Activation Analysis and BATAN Forum. These proceedings contain the result of environmental research in BATAN, universities and institutions associated with the application on neutron activation analysis technique. The purpose of these proceedings was as a useful source of information to spur research and development of activation analysis applications in various fields for the Indonesian welfare. There are 40 articles. (PPIKSN).

Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013

International Nuclear Information System (INIS)

2013-01-01

The Mathematics and Computation Division of the American Nuclear (ANS) and the Idaho Section of the ANS hosted the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M and C 2013). This proceedings contains over 250 full papers with topics ranging from reactor physics; radiation transport; materials science; nuclear fuels; core performance and optimization; reactor systems and safety; fluid dynamics; medical applications; analytical and numerical methods; algorithms for advanced architectures; and validation verification, and uncertainty quantification

Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-07-01

The Mathematics and Computation Division of the American Nuclear (ANS) and the Idaho Section of the ANS hosted the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M and C 2013). This proceedings contains over 250 full papers with topics ranging from reactor physics; radiation transport; materials science; nuclear fuels; core performance and optimization; reactor systems and safety; fluid dynamics; medical applications; analytical and numerical methods; algorithms for advanced architectures; and validation verification, and uncertainty quantification.

Letter of professional groups. Energies and fuel cells; La lettre des Groupe Professionnels, energies et piles a combustible

Energy Technology Data Exchange (ETDEWEB)

Meunier, M. [Supelec, 91 - Gif sur Yvette (France); Serre Combe, P. [CEA Grenoble, 38 (France); Sartorelli, G. [Maxwell Technologie, San Diego, CA (United States); Lafont, G. [PILLER France S.A., 92 - Nanterre (France); Green, A. [SAFT, 93170 Bagnolet (France); Perrin, M. [CEA Cadarache, 13 - Saint Paul lez Durance (France); Fregere, J.P.

2004-07-01

These proceedings of the 'Arts et Metiers' professional groups treats of energy storage solutions for delocalized power generation units. Four types of energy storage systems are presented with their operation principle, advantages and drawbacks: fuel cells and hydrogen, super-capacitors, flywheels, conventional batteries (lithium-ion, lead, redox, nickel-cadmium, zinc-air), and comparison between the different energy storage solutions including compressed air. (J.S.)

Digital sustainable publication of legacy parliamentary proceedings

NARCIS (Netherlands)

Marx, M.; Aders, N.; Schuth, A.

2010-01-01

We address the problem of publishing parliamentary proceedings in a digital sustainable manner. We give an extensive requirements analysis, and based on that propose a uniform XML format. We evaluated our approach by collecting and automatically processing proceedings from six parliaments spanning

Options for electric power generation and distribution in developing countries: proceedings of the GTDC symposium'95

International Nuclear Information System (INIS)

1995-01-01

This book contains the proceedings of the symposium on options for electric power generation and distribution in developing countries organised by Global Technology Development Centre (GTDC), Vienna in cooperation with Agency for Non-Conventional Energy and Rural Technology (ANERT), Thiruvananthapuram. The focus of the symposium was on problems of electricity generation and distribution mainly in the developing countries of the world and the issues addressed included : 1) an overview of existing electric power services; 2) options on fuel and technology; 3) options on operation of electricity utilities; 4) options on financing investments and planning of capacity extension or replacement. Papers relevant to INIS are indexed separately

Proceedings of the CTU seminar 94. Pt. A

International Nuclear Information System (INIS)

1994-01-01

The proceedings consist of 3 parts (A, B, C). Part A is divided into the following sections: Mathematics, Nuclear Engineering, Physics, Development of CTU Study, Fluid Mechanics, Theory of Constructions. Out of the 106 short communications contained in this part of the proceedings, 23 items were inputted to the INIS system. Out of 110 (96) short communications contained in parts B (C) of the proceedings, 2 (6) items were inputted to INIS. (Z.S.)

Proceedings of the American elm restoration workshop 2016

Science.gov (United States)

Cornelia C. Pinchot; Kathleen S. Knight; Linda M. Haugen; Charles E. Flower; James M. Slavicek

2017-01-01

Proceedings from the 2016 American Elm Restoration Workshop in Lewis Center, OH. The published proceedings include 16 papers pertaining to elm pathogens, American elm ecology, and American elm reintroduction.

Stages of proceedings in violation of customs regulations cases

Directory of Open Access Journals (Sweden)

С. А. Дуженко

2014-11-01

Full Text Available This article contains the analyze of scientific points of view regarding the structure of proceedings in administrative cases, particularly about determining the number of its stages. It has been proposed new criterion to determine the stages in proceedings in violation of customs regulations cases, as a kind of proceedings in administrative cases.

Concept of innovative water reactor for flexible fuel cycle (FLWR)

International Nuclear Information System (INIS)

Iwamura, T.; Uchikawa, S.; Okubo, T.; Kugo, T.; Akie, H.; Nakatsuka, T.

2005-01-01

In order to ensure sustainable energy supply in the future based on the matured Light Water Reactor (LWR) and coming LWR-Mixed Oxide (MOX) technologies, a concept of Innovative Water Reactor for Flexible Fuel Cycle (FLWR) has been investigated in Japan Atomic Energy Research Institute (JAERI). The concept consists of two parts in the chronological sequence. The first part realizes a high conversion type core concept, which is basically intended to keep the smooth technical continuity from current LWR and coming LWR-MOX technologies without significant gaps in technical point of view. The second part represents the Reduced-Moderation Water Reactor (RMWR) core concept, which realizes a high conversion ratio over 1.0 being useful for the long-term sustainable energy supply through plutonium multiple recycling based on the well-experienced LWR technologies. The key point is that the two core concepts utilize the compatible and the same size fuel assemblies, and hence, the former concept can proceed to the latter in the same reactor system, based flexibly on the fuel cycle circumstances during the reactor operation period around 60 years. At present, since the fuel cycle for the plutonium multiple recycling with MOX fuel reprocessing has not been realized yet, reprocessed plutonium from the LWR spent fuel is to be utilized in LWR-MOX. After this stage, the first part of FLWR, i.e. the high conversion type, can be introduced as a replacement of LWR or LWR-MOX. Since the plutonium inventory of FLWR is much larger, the number of the reactor with MOX fuel will be significantly reduced compared to the LWR-MOX utilization. The size of the fuel assembly for the first part is the same as in the RMWR concept, i.e. the hexagonal fuel assembly with the inner face-to-face distance of about 200 mm. Fuel rods are arranged in the triangular lattice with a relatively wide gap size around 3 mm between rods, and the effective MOX length is less than 1.5 m without using the blanket. When

Proceedings of Seminar on Nuclear Geology and Mining Resources

International Nuclear Information System (INIS)

Zulkarnain, Iskandar; Soeprapto; Soetarno, Djoko; H, Johan-Baratha; Effendi, Amir; Widiyanta; Arief, Erni-Rifandriah; Supriyadi; Yusron, Hari

2004-01-01

The proceedings contains the result research and development on nuclear geology and mining resources by the center for development of nuclear ore-National Nuclear Energy Agency, Indonesia. The proceedings consist of nuclear mining activity, exploration/exploitation mining mineral and processing, and environmental process. The proceedings consists of one article from keynote speaker and 22 articles from BATAN participants. (PPIN)

Constructive and manufactured proceedings for prevention of corrosion damages

International Nuclear Information System (INIS)

Buehler, H.E.

1982-01-01

A summary is given from the 12th design Symposium of the Dechema held at Frankfurt/M November 19/20 1981. The following topics are discussed: - Proceedings from the view of the types of corrosion; - Proceedings from the view of the state of fabrication and operation; - Corrosion preventive proceedings from the view of the applications. (RDE)

19 CFR 207.102 - Initiation of proceedings.

Science.gov (United States)

2010-04-01

... SUBSIDIZED EXPORTS TO THE UNITED STATES Implementing Regulations for the North American Free Trade Agreement... and Committee Proceedings § 207.102 Initiation of proceedings. (a) Upon completion of the inquiry, (1... charged is beyond the jurisdiction of the Commission and within the jurisdiction of another Free Trade...

Dry storage of MTR spent fuel from the Argentine radioisotope production reactor RA-3

International Nuclear Information System (INIS)

Di Marco, A.; Gillaume, E.J.; Ruggirello, G.; Zaweruchi, A.

1996-01-01

The nuclear fuel elements of the RA-3 reactor consist in 19 rectangular fuel plates held in position by two lateral structural plates. The whole assembly is coupled to the lower nozzles that fits in the reactor core grid. The inner plates are 1.5 mm thick, 70.5 mm wide and 655 mm long and the outer plates are 100 mm longer. The fuel plates are formed by a core of an AI-U alloy co-laminated between two plates of Al. Enrichment is 90% 235 U. After being extracted from the reactor, the fuel elements have been let to cool down in the reactor storage pool and finally moved to the storage facility. This facility is a grid of vertical underground channels connected by a piping system. The system is filled with processed and controlled water. At the present the storage capacity of the facility is near to be depleted and some indications of deterioration of the fuel elements has been detected. Due to the present status of the facility and the spent fuel stored there, a decision has been taken to proceed to modify the present underwater storage to dry storage. The project consist in: a) Decontamination and conditioning of the storage channels to prepare them for dry storage. b) Disassembly of the fuel elements in hot cells in order to can only the active fuel plates in an adequate tight canister. c) The remnant structural pieces will be treated as low level waste. (author). 10 figs

Fuel Handling Facility Description Document

International Nuclear Information System (INIS)

M.A. LaFountain

2005-01-01

The purpose of the facility description document (FDD) is to establish the requirements and their bases that drive the design of the Fuel Handling Facility (FHF) to allow the design effort to proceed to license application. This FDD is a living document that will be revised at strategic points as the design matures. It identifies the requirements and describes the facility design as it currently exists, with emphasis on design attributes provided to meet the requirements. This FDD was developed as an engineering tool for design control. Accordingly, the primary audience and users are design engineers. It leads the design process with regard to the flow down of upper tier requirements onto the facility. Knowledge of these requirements is essential to performing the design process. It trails the design with regard to the description of the facility. This description is a reflection of the results of the design process to date

CNA proceedings

International Nuclear Information System (INIS)

1996-01-01

The proceedings comprise keynote addresses, biographies, and 22 papers organized under the following headings: international CANDU operations, challenges in the uranium industry, public acceptance - gaining support, strategies for success in the nuclear business, nuclear power and the environment, initiatives in nuclear regulation, other opportunities. Individual papers published which come within the scope of INIS have been abstracted separately

CNA proceedings

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

The proceedings comprise keynote addresses, biographies, and 22 papers organized under the following headings: international CANDU operations, challenges in the uranium industry, public acceptance - gaining support, strategies for success in the nuclear business, nuclear power and the environment, initiatives in nuclear regulation, other opportunities. Individual papers published which come within the scope of INIS have been abstracted separately.

Proceedings of Asia congress on radiation protection

International Nuclear Information System (INIS)

1993-01-01

203 articles were collected in the proceedings. The contents of the proceedings included the principle and practices of radiation protection, biological effects of radiation, radiation monitoring, protection in medical and other fields, radiation dosimetry, nuclear energy and the environment, natural radiation, radioactive waste management, and other radiation protection issues

Proceedings 19th Central Hardwood Forest Conference

Science.gov (United States)

John W. Groninger; Eric J. Holzmueller; Clayton K. Nielsen; Daniel C., eds. Dey

2014-01-01

Proceedings from the 2014 Central Hardwood Forest Conference in Carbondale, IL. The published proceedings include 27 papers and 47 abstracts pertaining to research conducted on biofuels and bioenergy, forest biometrics, forest ecology and physiology, forest economics, forest health including invasive species, forest soils and hydrology, geographic information systems,...

7 CFR 765.352 - Use of proceeds.

Science.gov (United States)

2010-01-01

... proceeds. (a) Proceeds from transactions affecting the real estate security may only be used as follows: (1) Applied on liens in order of priority; (2) To pay customary costs appropriate to the transaction, which... priority, after deducting customary costs appropriate to the transaction. Such approval will not cancel or...

Fuel cycle options for light water reactors and heavy water reactors. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

1999-11-01

In the second half of the 20th century nuclear power has evolved from the research and development environment to an industry that supplies 16% of the world's electricity. By the end of 1997, over 8500 reactor-years of operating experience had been accumulated. Global environmental change, and the continuing increase in global energy supply required to provide increasing populations with an improving standard of living, make the contribution from nuclear energy even more important for the next century. For nuclear power to achieve its full potential and make its needed contribution, it must be safe, economical, reliable and sustainable. All of these factors can be enhanced by judicious choice and development of advanced fuel cycle options. The Technical Committee Meeting (TCM) on Fuel Cycle Options for Light Water Reactors and Heavy Water Reactors was hosted by Atomic Energy of Canada Limited (AECL) on behalf of the Canadian Government and was jointly conducted within the frame of activities of the IAEA International Working Group on Advanced Technologies for Light Water Reactors (IWG-LWR) and the IAEA International Working Group on Advanced Technologies for Heavy Water Reactors (IWG-HWR). The TCM provided the opportunity to have in-depth discussions on important technical topics which were highlighted in the International Symposium on Nuclear Fuel Cycle and Reactor Strategies: Adjusting to New Realities, held in Vienna, 3-6 June 1997. The main results and conclusions of the TCM were presented as input for discussion at the first meeting of the IAEA newly formed International Working Group on Fuel Cycle Options

37 CFR 251.71 - Commencement of proceedings.

Science.gov (United States)

2010-07-01

... PROCEDURE Royalty Fee Distribution Proceedings § 251.71 Commencement of proceedings. (a) Cable. In the case of royalty fees collected under the cable compulsory license (17 U.S.C. 111), any person claiming to... royalty fees collected under the satellite carrier compulsory license (17 U.S.C. 119), any person claiming...

17 CFR 1.60 - Pending legal proceedings.

Science.gov (United States)

2010-04-01

... 17 Commodity and Securities Exchanges 1 2010-04-01 2010-04-01 false Pending legal proceedings. 1... REGULATIONS UNDER THE COMMODITY EXCHANGE ACT Miscellaneous § 1.60 Pending legal proceedings. (a) Every... section to be submitted to the Commission as to matters pending on the effective date of the section (May...

Simulation of vibration modes of the fuel rod damaged due to the grid-to-rod fretting wear

International Nuclear Information System (INIS)

Kim, Kyu Tae; Kim, Kyeong Koo; Jang, Young Ki; Lee, Kyou Seok

1997-01-01

The flow-induced fuel fretting wear observed in some PWRs mainly proceeds in the grid-to-rod contact positions. The grid-to-rod fretting wear in the PWR fuel assembly depends on grid-to-rod gap size, its axial profile and flow-induced vibration. This paper describes the GRIDFORCE program which generates the axially dependent grid-to-rod gap size as a function of burnup. The axially dependent grid-to-rod gap profiles are employed to predict the fuel rod vibration mode shapes by the ANSYS code. With the help of the Paidousis empirical formula, this paper also calculates the fuel rod vibration amplitudes under various supporting conditions, which indicates that the increase of the number of unsupported mid-grids will increase the fuel rod vibration amplitude. On the other hand, the comparison of the predicted vibration mode shapes and the observed mid-grid fretting wear pattern indicates that the 1st and 6th vibration mode shapes under the supporting inactive condition at the mid-grids can simulate the observed mid-grid fretting wear profile. This paper also proposes design guidelines against the grid-to-rod fretting wear. (author). 3 refs., 8 figs

Integration of the AVLIS [atomic vapor laser isotopic separation] process into the nuclear fuel cycle

International Nuclear Information System (INIS)

Hargrove, R.S.; Knighton, J.B.; Eby, R.S.; Pashley, J.H.; Norman, R.E.

1986-08-01

AVLIS RD and D efforts are currently proceeding toward full-scale integrated enrichment demonstrations in the late 1980's and potential plant deployment in the mid 1990's. Since AVLIS requires a uranium metal feed and produces an enriched uranium metal product, some change in current uranium processing practices are necessitated. AVLIS could operate with a UF 6 -in UF 6 -out interface with little effect to the remainder of the fuel cycle. This path, however, does not allow electric utility customers to realize the full potential of low cost AVLIS enrichment. Several alternative processing methods have been identified and evaluated which appear to provide opportunities to make substantial cost savings in the overall fuel cycle. These alternatives involve varying levels of RD and D resources, calendar time, and technical risk to implement and provide these cost reduction opportunities. Both feed conversion contracts and fuel fabricator contracts are long-term entities. Because of these factors, it is not too early to start planning and making decisions on the most advantageous options so that AVLIS can be integrated cost effectively into the fuel cycle. This should offer economic opportunity to all parties involved including DOE, utilities, feed converters, and fuel fabricators. 10 refs., 11 figs., 2 tabs

Proceedings of the 16th International ECOS conference. Volume 1, 2, and 3

DEFF Research Database (Denmark)

Houbak, Niels; Elmegaard, Brian; Qvale, Einar Bjørn

The members of the Organizing and the Scientific Committees of ECOS 2003 are pleased to present these Proceedings of the Conference. This is the sixteenth in the series of international conferences that started in Rome in 1987. The slogan chosen for this years conference "Bridge to Our Energy...... in recent years. ECOS 2003 distinguishes itself through the quality and quantity of the papers submitted for presentation. Without the effort of dedicated researchers and authors from all over the world, this conference could not have taken place. We recognize and appreciate the creativity and work...... overall national planning to technological development, from government-initiated development of market forces to the completely liberalized market, from government-supported development to private investment opportunities, and from centralized generation of electricity from fossil fuels to distributed...

Effect of pressure on the transient swelling rate of oxide fuel

International Nuclear Information System (INIS)

Gruber, E.E.

1982-04-01

An analysis of the transient swelling rate of oxide fuel, based on fission-gas bubble conditions calculated with the FRAS3 code, has been developed and implemented in the code. The need for this capability arises in the coupling of the FRAS3 fission-gas analysis code to the FPIN fuel-pin mechanics code. An efficient means of closely coupling the calculations of swelling strains and stresses between the modules is required. The present analysis provides parameters that allow the FPIN calculation to proceed through a fairly large time step, using estimated swelling rates, to calculate the stresses. These stress values can then be applied in the FRAS3 detailed calculation to refine the swelling calculation, and to provide new values for the parameters to estimate the swelling in the next time step. The swelling rates were calculated for two representative transients and used to estimate swelling over a short time period for various stress levels

Proceedings of a workshop on corrosion of Nuclear fuel waste containers

International Nuclear Information System (INIS)

Shoesmith, D.W.

1990-01-01

The 23 papers presented at this conference review the technical merits, and particularly corrosion performance, of the three main materials used for nuclear fuel waste containers: titanium and its alloys, copper and its alloys, and iron and carbon steels. The specific questions posed to the Workshop were: 1) Can we predict the lifetime of container materials in a variety of vault environments? 2) Is there a limiting range of conditions beyond which a specific material cannot be used? 3) Do we have the necessary corrosion rate data and/or mechanistic models required to make predictions? 4) Can we justify the use of titanium on the basis of propagation rate measurements for crevice corrosion, or do we need to prove initiation cannot occur? 5) Will the pitting of copper be significant? 6) How thick a carbon steel container would be required, and can it be fabricated and stress-relieved? 7) Are radiation fields of any consequence at the dose rates expected?

34 CFR 81.9 - Location of proceedings.

Science.gov (United States)

2010-07-01

... 34 Education 1 2010-07-01 2010-07-01 false Location of proceedings. 81.9 Section 81.9 Education Office of the Secretary, Department of Education GENERAL EDUCATION PROVISIONS ACT-ENFORCEMENT General Provisions § 81.9 Location of proceedings. (a) An ALJ may hold conferences of the parties in person or by...

Impacts of a 32-billion-gallon bioenergy landscape on land and fossil fuel use in the US

Science.gov (United States)

Hudiburg, Tara W.; Wang, Weiwei; Khanna, Madhu; Long, Stephen P.; Dwivedi, Puneet; Parton, William J.; Hartman, Melannie; Delucia, Evan H.

2016-01-01

Sustainable transportation biofuels may require considerable changes in land use to meet mandated targets. Understanding the possible impact of different policies on land use and greenhouse gas emissions has typically proceeded by exploring either ecosystem or economic modelling. Here we integrate such models to assess the potential for the US Renewable Fuel Standard to reduce greenhouse gas emissions from the transportation sector through the use of cellulosic biofuels. We find that 2022 US emissions are decreased by 7.0 ± 2.5% largely through gasoline displacement and soil carbon storage by perennial grasses. If the Renewable Fuel Standard is accompanied by a cellulosic biofuel tax credit, these emissions could be reduced by 12.3 ± 3.4%. Our integrated approach indicates that transitioning to cellulosic biofuels can meet a 32-billion-gallon Renewable Fuel Standard target with negligible effects on food crop production, while reducing fossil fuel use and greenhouse gas emissions. However, emissions savings are lower than previous estimates that did not account for economic constraints.

Nuclear power, nuclear fuel cycle and waste management, 1986-1999. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

2000-04-01

This catalogue lists all sales publications of the International Atomic Energy Agency dealing with nuclear power and nuclear fuel cycle and waste management and issued during the period of 1986-1999. Some earlier titles which form part of an established series or are still considered of importance have been included. Most publications are in English. Proceedings of conferences, symposia and panels of experts may contain papers in languages other than English, but all of these papers have abstracts in English

XXVII. Days of Radiation Protection. Conference Proceedings

International Nuclear Information System (INIS)

2005-11-01

The publication has been set up as a proceedings of the conference dealing with health protection during work with ionizing radiation for different activities which involve the handling of ionizing radiation sources. The main conference topics are focused on current problems in radiation protection and radioecology. In this proceedings totally 83 papers are published

Commercialization of fuels from Pinyon-Juniper biomass in Nevada

International Nuclear Information System (INIS)

Morris, G.P.

1994-01-01

This study analyzes and defines energy applications and markets that could stimulate the commercial use of Eastern Nevada's Pinyon-Juniper resources. The commercialization potential for producing energy from Pinyon-Juniper biomass is analyzed by examining the resource base and resource availability for a commercial harvesting and processing operation. The study considered the spectrum of available equipment and technology for carrying out harvesting and processing operations, investigated the markets that might be able to use energy products derived from Pinyon-Juniper biomass, analyzed the costs of harvesting, processing, and transporting Pinyon-Juniper fuels, and set forth a plan for developing the commercial potential of these resources. The emerging residential pellet-fuels market is a promising entry market for the commercialization of an energy from Pinyon-Juniper biomass industry in Eastern Nevada, although there are serious technical issues that may render Pinyon-Juniper biomass an unsuitable feedstock for the manufacture of pellet fuels. These issues could be investigated at a moderate cost in order to determine whether to proceed with development efforts in this direction. In the longer term, one or two biomass-fired power plants in the size range of 5-10 MW could provide a stable and predictable market for the production and utilization of fuels derived from local Pinyon-Juniper biomass resources, and would provide valuable economic and environmental benefits to the region. Municipal utility ownership of such facilities could help to enhance the economic benefits of the investments by qualifying them for federal energy credits and tax-free financing

Fuels from microalgae: Technology status, potential, and research requirements

Energy Technology Data Exchange (ETDEWEB)

Neenan, B.; Feinberg, D.; Hill, A.; McIntosh, R.; Terry, K.

1986-08-01

Although numerous options for the production of fuels from microalgae have been proposed, our analysis indicates that only two qualify for extensive development - gasoline and ester fuel. In developing the comparisons that support this conclusion, we have identified the major areas of microalgae production and processing that require extensive development. Technology success requires developing and testing processes that fully utilize the polar and nonpolar lipids produced by microalgae. Process designs used in these analyses were derived from fragmented, preliminary laboratory data. These results must be substantiated and integrated processes proposed, tested, and refined to be able to evaluate the commercial feasibility from microalgae. The production of algal feedstocks for processing to gasoline or ester fuel requires algae of high productivity and high lipid content that efficiently utilize saline waters. Species screening and development suggest that algae can achieve required standards taken individually, but algae that can meet the integrated requirements still elude researchers. Effective development of fuels from microalgae technology requires that R and D be directed toward meeting the integrated standards set out in the analysis. As technology analysts, it is inappropriate for us to dictate how the R and D effort should proceed to meet these standards. We end our role by noting that alternative approaches to meeting the feasibility targets have been identified, and it is now the task of program managers and scientists to choose the appropriate approach to assure the greatest likelihood of realizing a commercially viable technology. 70 refs., 39 figs., 35 tabs.

Proceedings of the geosciences workshop

Energy Technology Data Exchange (ETDEWEB)

None

1991-01-01

The manuscripts in these proceedings represent current understanding of geologic issues associated with the Weldon Spring Site Remedial Action Project (WSSRAP). The Weldon Spring site is in St. Charles County, Missouri. The proceedings are the record of the information presented during the WSSRAP Geosciences Workshop conducted on February 21, 1991. The objective of the workshop and proceedings is to provide the public and scientific community with technical information that will facilitate a common understanding of the geology of the Weldon Spring site, of the studies that have been and will be conducted, and of the issues associated with current and planned activities at the site. This coverage of geologic topics is part of the US Department of Energy overall program to keep the public fully informed of the status of the project and to address public concerns as we clean up the site and work toward the eventual release of the property for use by this and future generations. Papers in these proceedings detail the geology and hydrology of the site. The mission of the WSSRAP derives from the US Department of Energy's Surplus Facilities Management Program. The WSSRAP will eliminate potential hazards to the public and the environment and make surplus real property available for other uses to the extent possible. This will be accomplished by conducting remedial actions which will place the quarry, the raffinate pits, the chemical plant, and the vicinity properties in a radiologically and chemically safe condition. The individual papers have been catalogued separately.

Material accountancy in an electrometallurgical Fuel Conditioning Facility

International Nuclear Information System (INIS)

Vaden, D.; Benedict, R.W.; Goff, K.M.; Keyes, R.W.; Mariani, R.D.; Bucher, R.G.; Yacout, A.M.

1996-01-01

The Fuel Conditioning Facility (FCF) treats spent nuclear fuel using an electrometallurgical process that separates the uranium from the fission products, sodium thermal bond and cladding materials. Material accountancy is necessary at FCF for two reasons: first, it provides a mechanism for detecting a potential loss of nuclear material for safeguards and security; second, it provides a periodic check of inventories to ensure that processes and material are under control. By weighing material entering and leaving a process, and using sampling results to determine composition, an inventory difference (ID) results when the measured inventory is compared to the predicted inventory. The ID and its uncertainty, based on error propagation, determines the degree of assurance that an operation proceeded according to expectations. FCF uses the ID calculation in two ways: closeout, which is the ID and uncertainty for a particular operational step, and material accountancy, which determines an ID and its associated uncertainty for a material balance area through several operational steps. Material accountancy over the whole facility for a specified time period assists in detecting diversion of nuclear material. Data from depleted uranium operations are presented to illustrate the method used in FCF

Nuclear Inter Jura '77 Proceedings

International Nuclear Information System (INIS)

1977-01-01

These Proceedings of the Third Congress of the International Nuclear Law Association reproduce the papers presented in their original language with an abstract in English as well as the ensuing discussions. A majority of the papers have been translated into English for the Proceedings. The subjects dealt with respectively concerned contractual aspects of nuclear activities, the impact of nuclear power on the environment and public acceptance, radiological protection, third party liability and insurance, harmonisation of licensing regulations, export of nuclear equipment in relation to the Non-Proliferation Treaty and finally, computerization of nuclear law. (NEA) [fr

Utilization of Used Nuclear Fuel in a Potential Future US Fuel Cycle Scenario - 13499

Energy Technology Data Exchange (ETDEWEB)

Worrall, Andrew [Oak Ridge National Laboratory, P.O. BOX 2008 MS6172, Oak Ridge, TN, 37831-6172 (United States)

2013-07-01

To date, the US reactor fleet has generated approximately 68,000 MTHM of used nuclear fuel (UNF) and even with no new nuclear build in the US, this stockpile will continue to grow at approximately 2,000 MTHM per year for several more decades. In the absence of reprocessing and recycle, this UNF is a liability and needs to be dealt with accordingly. However, with the development of future fuel cycle and reactor technologies in the decades ahead, there is potential for UNF to be used effectively and efficiently within a future US nuclear reactor fleet. Based on the detailed expected operating lifetimes, the future UNF discharges from the existing reactor fleet have been calculated on a yearly basis. Assuming a given electricity demand growth in the US and a corresponding growth demand for nuclear energy via new nuclear build, the future discharges of UNF have also been calculated on a yearly basis. Using realistic assumptions about reprocessing technologies and timescales and which future fuels are likely to be reprocessed, the amount of plutonium that could be separated and stored for future reactor technologies has been determined. With fast reactors (FRs) unlikely to be commercially available until 2050, any new nuclear build prior to then is assumed to be a light water reactor (LWR). If the decision is made for the US to proceed with reprocessing by 2030, the analysis shows that the UNF from future fuels discharged from 2025 onwards from the new and existing fleet of LWRs is sufficient to fuel a realistic future demand from FRs. The UNF arising from the existing LWR fleet prior to 2025 can be disposed of directly with no adverse effect on the potential to deploy a FR fleet from 2050 onwards. Furthermore, only a proportion of the UNF is required to be reprocessed from the existing fleet after 2025. All of the analyses and conclusions are based on realistic deployment timescales for reprocessing and reactor deployment. The impact of the delay in recycling the UNF

Utilization of Used Nuclear Fuel in a Potential Future US Fuel Cycle Scenario - 13499

International Nuclear Information System (INIS)

Worrall, Andrew

2013-01-01

To date, the US reactor fleet has generated approximately 68,000 MTHM of used nuclear fuel (UNF) and even with no new nuclear build in the US, this stockpile will continue to grow at approximately 2,000 MTHM per year for several more decades. In the absence of reprocessing and recycle, this UNF is a liability and needs to be dealt with accordingly. However, with the development of future fuel cycle and reactor technologies in the decades ahead, there is potential for UNF to be used effectively and efficiently within a future US nuclear reactor fleet. Based on the detailed expected operating lifetimes, the future UNF discharges from the existing reactor fleet have been calculated on a yearly basis. Assuming a given electricity demand growth in the US and a corresponding growth demand for nuclear energy via new nuclear build, the future discharges of UNF have also been calculated on a yearly basis. Using realistic assumptions about reprocessing technologies and timescales and which future fuels are likely to be reprocessed, the amount of plutonium that could be separated and stored for future reactor technologies has been determined. With fast reactors (FRs) unlikely to be commercially available until 2050, any new nuclear build prior to then is assumed to be a light water reactor (LWR). If the decision is made for the US to proceed with reprocessing by 2030, the analysis shows that the UNF from future fuels discharged from 2025 onwards from the new and existing fleet of LWRs is sufficient to fuel a realistic future demand from FRs. The UNF arising from the existing LWR fleet prior to 2025 can be disposed of directly with no adverse effect on the potential to deploy a FR fleet from 2050 onwards. Furthermore, only a proportion of the UNF is required to be reprocessed from the existing fleet after 2025. All of the analyses and conclusions are based on realistic deployment timescales for reprocessing and reactor deployment. The impact of the delay in recycling the UNF

Analysis of operational, institutional and international limitations for alternative fuel vehicles and technologies: Means/methods for implementing changes

Energy Technology Data Exchange (ETDEWEB)

1992-07-01

This project focused upon the development of an approach to assist public fleet managers in evaluating the characteristics and availability of alternative fuels (AF`s) and alternative fuel vehicles (AFV`s) that will serve as possible replacements for vehicles currently serving the needs of various public entities. Also of concern were the institutional/international limitations for alternative fuels and alternative fuel vehicles. The City of Detroit and other public agencies in the Detroit area were the particular focus for the activities. As the development and initial stages of use of alternative fuels and alternative fuel vehicles proceeds, there will be an increasing need to provide information and guidance to decision-makers regarding differences in requirements and features of these fuels and vehicles. There wig be true differences in requirements for servicing, managing, and regulating. There will also be misunderstanding and misperception. There have been volumes of data collected on AFV`S, and as technology is improved, new data is constantly added. There are not, however, condensed and effective sources of information for public vehicle fleet managers on vehicle and equipment sources, characteristics, performance, costs, and environmental benefits. While theoretical modeling of public fleet requirements has been done, there do not seem to be readily available ``practical``. There is a need to provide the best possible information and means to minimize the problems for introducing the effective use of alternative fuels and alternative fuel vehicles.

17 CFR 201.500 - Expedited consideration of proceedings.

Science.gov (United States)

2010-04-01

... 17 Commodity and Securities Exchanges 2 2010-04-01 2010-04-01 false Expedited consideration of proceedings. 201.500 Section 201.500 Commodity and Securities Exchanges SECURITIES AND EXCHANGE COMMISSION... Expedited consideration of proceedings. Consistent with the Commission's or the hearing officer's other...

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. A GHAFFARI. Articles written in Proceedings – Mathematical Sciences. Volume 127 Issue 4 September 2017 pp 689-705 Research Article. Involutions and trivolutions on second dual of algebras related to locally compact groups and topological semigroups.

Proceedings of the 1st LAK Data Challenge

NARCIS (Netherlands)

d'Aquin, Mathieu; Dietze, Stefan; Drachsler, Hendrik; Herder, Eelco; Taibi, Davide

2013-01-01

d'Aquin, M., Dietze, S., Drachsler, H., Herder, E., & Taibi, D. (Eds.) (2013, April). Proceedings of the 1st LAK Data Challenge, held at LAK 2013, the Third Conference on Learning Analytics and Knowledge. Published by CEUR Workshop Proceedings, 2013, Vol. 974.

19 CFR 210.8 - Commencement of preinstitution proceedings.

Science.gov (United States)

2010-04-01

... 19 Customs Duties 3 2010-04-01 2010-04-01 false Commencement of preinstitution proceedings. 210.8 Section 210.8 Customs Duties UNITED STATES INTERNATIONAL TRADE COMMISSION INVESTIGATIONS OF UNFAIR PRACTICES IN IMPORT TRADE ADJUDICATION AND ENFORCEMENT Commencement of Preinstitution Proceedings and...

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. Shobha Madan. Articles written in Proceedings – Mathematical Sciences. Volume 113 Issue 2 May 2003 pp 171-178. Wavelet Subspaces Invariant Under Groups of Translation Operators · Biswaranjan Behera Shobha Madan · More Details Abstract Fulltext PDF.

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. MOHAMED KHALIL ZGHAL. Articles written in Proceedings – Mathematical Sciences. Volume 128 Issue 1 March 2018 pp 13 Research Article. Sharp Adams-type inequality invoking Hardy inequalities · MOHAMED KHALIL ZGHAL · More Details Abstract Fulltext PDF.

Regulatory inspection practices on fuel elements and core lay-out at NPPs

International Nuclear Information System (INIS)

Van Binnebeek, J.J.; Liuhto, Pekka; Badel, D.; Klonk, H.; Seidel, F.; Fichtinger, G.; Manzella, P.; Koizumi, Hiroyoshi; Delgado, Jose Luis; Gutierrez Ruiz, Luis Miguel; Bouvrie, E. des; Gil, J.; Forsberg, Staffan; Wand, H.; Warren, Tom; Gallo, R.

1998-01-01

The basic description of the reactor core of a nuclear power plant (NPP) is an important part of the Safety Analysis Report in all countries. Due to increased interest by regulatory authorities in the Member countries, in 1996 WGIP proposed looking at inspection aspects on fuel elements and core lay-out at nuclear power plants. The CNRA subsequently approved proceeding with this report. The report deals primarily with inspection practices and inspection requirements during nuclear power plant (NPP) operation with special emphasis on refuelling procedures. All license related topics, such as fuel and core design (mechanical, neutronic, thermal-hydraulic), as well as inspection philosophy and practices on fuel fabrication are included as appropriate serving as background information and may not be completely described. WGIP members describe their country's inspection programme according to the structure of a questionnaire (appendix 1). The individual contributions are contained in the appendix 2 and are compiled within the main chapters (1 through 3). Report Structure: 1. Licensing and Quality Assurance (QA) requirements for nuclear fuel; 2. Regulatory inspection programme during NPP operation and refuelling outages; 3. Procedures for inspection practices and inspection programme. Appendix: Questionnaire and Country specific contributions. Contributions are presented by Belgium, Finland, France, Germany, Hungary, Italy, Japan, Mexico, The Netherlands, Spain, Sweden, Switzerland, United Kingdom, USA

Fuel Exhaling Fuel Cell.

Science.gov (United States)

Manzoor Bhat, Zahid; Thimmappa, Ravikumar; Devendrachari, Mruthyunjayachari Chattanahalli; Kottaichamy, Alagar Raja; Shafi, Shahid Pottachola; Varhade, Swapnil; Gautam, Manu; Thotiyl, Musthafa Ottakam

2018-01-18

State-of-the-art proton exchange membrane fuel cells (PEMFCs) anodically inhale H 2 fuel and cathodically expel water molecules. We show an unprecedented fuel cell concept exhibiting cathodic fuel exhalation capability of anodically inhaled fuel, driven by the neutralization energy on decoupling the direct acid-base chemistry. The fuel exhaling fuel cell delivered a peak power density of 70 mW/cm 2 at a peak current density of 160 mA/cm 2 with a cathodic H 2 output of ∼80 mL in 1 h. We illustrate that the energy benefits from the same fuel stream can at least be doubled by directing it through proposed neutralization electrochemical cell prior to PEMFC in a tandem configuration.

Coal, energy and environment: Proceedings

International Nuclear Information System (INIS)

Mead, J.S.; Hawse, M.L.

1994-01-01

This international conference held in Czechoslovakia was a bold attempt to establish working relationships among scientists and engineers from three world areas: Taiwan, the United States of America, and Czechoslovakia. The magic words unifying this gathering were ''clean coal utilization.'' For the ten nationalities represented, the common elements were the clean use of coal as a domestic fuel and as a source of carbon, the efficient and clean use of coal in power generation, and other uses of coal in environmentally acceptable processes. These three world areas have serious environmental problems, differing in extent and nature, but sufficiently close to create a working community for discussions. Beyond this, Czechoslovakia is emerging from the isolation imposed by control from Moscow. The need for each of these nations to meet and know one another was imperative. The environmental problems in Czechoslovakia are extensive and deep-seated. These proceedings contain 63 papers grouped into the following sections: The research university and its relationship with accrediting associations, government and private industry; Recent advances in coal utilization research; New methods of mining and reclamation; Coal-derived waste disposal and utilization; New applications of coal and environmental technologies; Mineral and trace elements in coal; Human and environmental impacts of coal production and utilization in the Silesian/Moravian region; and The interrelationships between fossil energy use and environmental objectives. Most papers have been processed separately for inclusion on the data base

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. Basudeb Datta. Articles written in Proceedings – Mathematical Sciences. Volume 112 Issue 2 May 2002 pp 257-281. Two-Dimensional Weak Pseudomanifolds on Eight Vertices · Basudeb Datta Nandini Nilakantan · More Details Abstract Fulltext PDF. We explicitly ...

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences; Forthcoming articles. Forthcoming articles. Proceedings – Mathematical Sciences. PMSC-D-14-00136. Combinatorics of tenth order mock theta functions. J K SAREEN M RANA. Abstract. In this paper we are providing the combinatorial interpretations of two tenth ...

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. SENJO SHIMIZU. Articles written in Proceedings – Mathematical Sciences. Volume 127 Issue 5 November 2017 pp 815-831 Special Issue. Qualitative behaviour of incompressible two-phase flows with phase transitions: The isothermal case · JAN PRÜSS SENJO ...

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. MIHAJA RAKOTOMALALA. Articles written in Proceedings – Mathematical Sciences. Volume 127 Issue 3 June 2017 pp 411-421 Research Article. On a problem of Pillai with Fibonacci numbers and powers of 2 · MAHADI DDAMULIRA FLORIAN LUCA MIHAJA ...

Intelligence as evidence in criminal proceedings

Directory of Open Access Journals (Sweden)

Lukić Tatjana

2011-01-01

Full Text Available The fight against modern forms of crime such as organized crime, terrorism and other very serious crimes caused not only modification of procedural principles and procedural rules, but also the necessity of re-examination of evidence in terms of introducing new evidence in criminal proceedings. Given that the prevention, detection and proving in cases of mentioned offenses represent the systemic issue and that the efficiency is caused by cohesion of preventive and repressive mechanisms in each strategy of preventing and combating serious crimes, the more often raised question, aroused from the practice, is the issue of the use of information gathered by the police or security services as evidence in criminal proceedings. In addition, there is the issue of use of illegal evidence, the ways in which these evidence are defined in some jurisdictions and which are the legal consequences of their use in judicial decision, whether it is based only on them, or on some other evidence beside them. The author addresses the issues of necessity and justification for use of information of security services as evidence in criminal proceedings, their definition and difference with respect to data, experiences and practices in other countries and of course their use as evidence in criminal proceedings of Serbia. Also, the paper addresses the Criminal Intelligence Analytics, exchange of information between the competent authorities at national and international level.

Fuel technology and performance of non-water cooled reactors. Proceedings of an advisory group meeting held in Vienna, 5-8 December 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-01

The IAEA Division of Nuclear Fuel Cycle and Waste Management has been closely involved for many years in the collection, analysis and exchange of information relating to the global development of advanced reactor fuel technology and performance. Meetings of experts in this field have been held in 1984 and 1989 and more recently in December 1994 as part of the IAEA`s programme. This publication reviews progress in advanced reactor fuel technology and performance over the past five years, principally related to non-water cooled reactors, namely high temperature gas reactors (HTGRs) and fast reactors (FRs), as well as developments pertaining to thorium fuels and the fuel fabrication technologies. It includes papers from the participants and provides recommendations in key areas where further global co-operation in this field might be usefully initiated or strengthened. The previous two Advisory Group Meetings on Advanced Fuel Technology and Performance, on which separate reports have been published (IAEA-TECDOC-352 (1985) and IAEA-TECDOC-577 (1990)), focused on all types of commercial nuclear reactors. Refs, figs and tabs.

Proceedings

International Nuclear Information System (INIS)

1997-01-01

The 14. annual meeting of BIOMINET (Mineral and Energy Applied Biotechnology Network) and NCUT (National Centre for Upgrading Technology) took place on June 9, 1997 in Calgary, as part of the CIM Petroleum Society's 48. annual technical meeting. Papers presented at the meeting focused on the application of biotechnology to the fossil fuel industry. There were two sessions, one devoted to application of biotechnology to environmental concerns of the fossil fuel industry, the other emphasizing bioupgrading of petroleum feedstocks

Proceedings of the Third Meeting of the OECD-NEA Expert Group on Accident Tolerant Fuels for LWRs, 3-5 March 2015, OECD-NEA HQ

International Nuclear Information System (INIS)

Bischoff, Jeremy; Gandrille, Pascal; Forgeron, Thierry; Brachet, Jean-Christophe; Lorrette, Christophe; Valot, C.; Freyss, M.; Braun, J.; Sauder, C.; Moatti, Marie; Waeckel, Nicolas; Ambard, Antoine; Pasamehmetoglu, Kemal; Johnston, Emma; Bragg-Sitton, Shannon M.; Kurata, M.; Hallstadius, Lars; Ohta, H.; Ogata, T.; Besmann, T.; Chauvin, Nathalie; Cornet, Stephanie; Massara, S.; Kohyama, Akira; Kishimoto, Hirotatsu; Park, Joon Soo; Nakazato, Naofumi; Hayasaka, Daisuke; Asakura, Yuuki; Kanda, Chisato; Kohyama, Akira; Terrani, Kurt; Katoh, Yutai; Yamamoto, Yukinori; Field, Kevin; Snead, Lance; Hu, Xunxiang; Dryepondt, Sebastien; Unocic, Kinga A.; Hoelzer, David T.; Pint, Bruce A.; Besmann, T.; Steinbrueck, M.; Grosse, M.; Jianu, A.; Weisenburger, A.; Avincola, V.; Ahmad, S.; Tang, C.; Heuser, Brent J.; Sickafus, Kurt; Kim, Hyun-Gil; Kim, Il-Hyun; Jung, Yang-Il; Park, Dong-Jun; Park, Jung-Hwan; Park, Jeong-Yong; Koo, Yang-Hyun; Lee, B.O.; Van Nieuwenhove, Rudi; Kim, Young; Rebak, Raul; Dolly, Evan; Dolley, E.J.; Rebak, R.B.; Maloy, Stu; Yang, Jae-Ho; Kim, Dong-Joo; Kim, Keon-Sik; Koo, Yang-Hyun; Lee, Won Jae; Tulenko, James S.; Puide, Mattias; Liu, T.; Gueneau, C.; Gosse, S.; Dupin, N.; Barber, D.; Corcoran, E.; Dumas, J.C.; Hania, R.; Kaye, M.; Turchi, P.

2015-03-01

Under the guidance of the OECD-NEA Nuclear Science Committee, the expert group acts as a forum for scientific and technical information exchange on advanced light water reactor (LWR) fuels with enhanced accident tolerance. The expert group focusses on the fundamental properties and behaviour under normal operations and accident conditions for advanced core materials and components (fuels, cladding, control rods, etc.). The materials considered are applicable to Gen II and Gen III Light Water Reactors, as well as Gen III+ reactors under construction. The objective of the expert group is to define and coordinate a programme of work to help advance the scientific knowledge needed to provide the technical underpinning for the development of advanced LWR fuels with enhanced accident tolerance compared to currently used zircaloy/UO 2 fuel systems, as well as other non-fuel core components with important roles in LWR performance under accident conditions. This document brings together the available presentations (slides) given at the Third Meeting of the OECD-NEA Expert Group on Accident Tolerant Fuels for LWRs. Content: 1 - Task Force 1 (Systems assessment) meeting, 3-4 March 2015: - French evaluation of ATF Concepts (J. Bischoff, AREVA); - Technology Readiness Levels - TRL - for Fuels (K. Pasamehmetoglu, INL); - TRL-definition for advanced fuel concept applied for commercial LWRs in Japan (M. Kurata, JAEA); - Application of TRLs in NNL (E. Johnston, NNL); - Technology Readiness Levels for Advanced Nuclear Fuel and Materials (S. Bragg-Sitton, INL); 1a - Definition of the illustrative scenarios: - AREVA's proposal concerning scenario for Accident Tolerant Fuel studies (P. Gandrille); - A Simplified Accident Scenario (L. Hallstadius); - Accident Scenarios for ATF Performance Evaluation of BWR and PWR in Japan (H. Ohta, CRIEPI); 1b - Related NEA activities: - Working Party on Multi-scale Modelling of Fuels and Structural Materials for Nuclear Systems - WPMM, Expert

Contribution and influence of proceedings papers to citation impact in seven conference and journal-driven sub-fields of energy research 2005-11

DEFF Research Database (Denmark)

Ingwersen, Peter; Larsen, Birger; Garcia-Zorita, J. Carlos

2013-01-01

and Wave Energy, Geo-thermal, Bio-fuel and Bio-mass energy sub-fields. The analyses cover research and review articles as well as conference proceeding papers excluding meeting abstracts published 2005-09 and cited 2005-11 through Web of Science. Central findings are: The distribution across document types......This paper analyses the following seven sub-fields of Sustainable Energy Research with respect to the influence of conference paper dominance on citation patterns across citing and cited document types, overall sub-field and document type impacts and citedness: Wind Power, Renewable Energy, Solar...

Proceedings from the technical workshop on near-field performance assessment for high-level waste

International Nuclear Information System (INIS)

Sellin, P.; Apted, M.; Gago, J.

1991-12-01

This report contains the proceedings of 'Technical workshop of near-filed performance assessment for high-level waste' held in Madrid October 15-17, 1990. It includes the invited presentations and summaries of the scientific discussions. The workshop covered several topics: * post-emplacement environment, * benchmarking of computer codes, * glass release, * spent-fuel release, * radionuclide solubility, * near-field transport processes, * coupled processes in the near-field, * integrated assessments, * sensitivity analyses and validation. There was an invited presentation on each topic followed by an extensive discussion. One of the points highlighted in the closing discussion of the workshop was the need for international cooperation in the field of near-field performance assessment. The general opinion was that this was best achieved in smaller groups discussing specific questions. (au) Separate abstracts were prepared for 9 papers in this volume

37 CFR 351.3 - Controversy and further proceedings.

Science.gov (United States)

2010-07-01

..., the contested amount of a claim is $10,000 or less, the Copyright Royalty Judges shall decide the... CONGRESS COPYRIGHT ROYALTY JUDGES RULES AND PROCEDURES PROCEEDINGS § 351.3 Controversy and further... negotiation period, the Copyright Royalty Judges will issue an order declaring that further proceedings are...

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. CHANCHAL KUMAR. Articles written in Proceedings – Mathematical Sciences. Volume 120 Issue 2 April 2010 pp 163-168. Deficiently Extremal Cohen-Macaulay Algebras · Chanchal Kumar Pavinder Singh · More Details Abstract Fulltext PDF. The aim of this paper is ...

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. Satyendra Tomar. Articles written in Proceedings – Mathematical Sciences. Volume 112 Issue 4 November 2002 pp 601-639. Stability Estimates for ℎ- Spectral Element Methods for Elliptic Problems · Pravir Dutt Satyendra Tomar B V Rathish Kumar · More Details ...

77 FR 58941 - Appeal Proceedings Before the Commission

Science.gov (United States)

2012-09-25

... forth more specific rules for the different types of appeals. Rules for appeals of ordinance..., 582, 583, 584, and 585 RIN 3141-AA47 Appeal Proceedings Before the Commission AGENCY: National Indian... Commission) promulgates this final rule to enhance and clarify appeal proceedings before the Commission. This...

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. Rémi Léandre. Articles written in Proceedings – Mathematical Sciences. Volume 116 Issue 4 November 2006 pp 507-518 Non-commutative Probability Theory. Malliavin Calculus of Bismut Type without Probability · Rémi Léandre · More Details Abstract Fulltext PDF.

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. MEGHA GOYAL. Articles written in Proceedings – Mathematical Sciences. Volume 128 Issue 1 March 2018 pp 2 Research Article. On 3-way combinatorial identities · A K AGARWAL MEGHA GOYAL · More Details Abstract Fulltext PDF. In this paper, we provide ...

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. Pravir Dutt. Articles written in Proceedings – Mathematical Sciences. Volume 112 Issue 4 November 2002 pp 601-639. Stability Estimates for ℎ- Spectral Element Methods for Elliptic Problems · Pravir Dutt Satyendra Tomar B V Rathish Kumar · More Details Abstract ...

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. B V Rao. Articles written in Proceedings – Mathematical Sciences. Volume 116 Issue 1 February 2006 pp 83-96. On Characterisation of Markov Processes Via Martingale Problems · Abhay G Bhatt Rajeeva L Karandikar B V Rao · More Details Abstract Fulltext PDF.

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. Suprio Bhar. Articles written in Proceedings – Mathematical Sciences. Volume 125 Issue 1 February 2015 pp 113-125. Differential operators on Hermite Sobolev spaces · Suprio Bhar B Rajeev · More Details Abstract Fulltext PDF. In this paper, we compute the Hilbert ...

News from the Library: Focus on AIP conference proceedings

CERN Multimedia

CERN Library

2011-01-01

The American Institute of Physics (AIP) publishes conference proceedings covering a broad range of subjects, such as nuclear and particle physics, materials science, astronomy and astrophysics and many more. Today, this series includes some 1,300 volumes, starting with Volume 1 (1970), and dozens of new volumes are added each year.   This represents more than 100,000 conference papers available online. Among other things, AIP publishes e.g. the proceedings of the International Cryogenic Materials Conference, the Cryogenic Engineering Conference, and the International Workshop on Neutrino Factories and Superbeams. You can access AIP conference proceedings from CERN or from outside, thanks to the Library Proxy Service. See instructions on how to access them from outside CERN: access AIP Proceedings. Please send any feedback and questions to library.desk@cern.ch.  

Proceedings of the 9th NUSIM 2000 Conference. Joint Slovak, Czech and German Seminar on Nuclear Power

International Nuclear Information System (INIS)

2000-01-01

Scientific conference deals with problems of reactor safety upgrading, mainly of two blocks of the NPP V-1 Bohunice as well as decomissioning of the NPP A-1 Bohunice. Other problems of the nuclear engineering were discussed. Totally, 201 participants from the Slovak Republic, Czech Republic and Germany and from other countries took part in the conference. The Conference included the following sessions: (i): Survey on the situation of nuclear power in the partner countries; (ii) Mochovce design safety enhacement and operational experience; (iii) Bohunice V-1 safety upgrading and operational experience; (iv) Decomissioning, spent fuel and radwaste management; (v) Young Generation Presentation. Proceedings contains thirty one papers dealing with the scope of INIS

Nuclear fuel waste disposal. Canada's consultative approach

International Nuclear Information System (INIS)

Hillier, J.A.R.; Dixon, R.S.

1993-01-01

Over the past two decades, society has increasingly demanded more public participation and public input into decision-making by governments. Development of the Canadian concept for deep geological disposal of used nuclear fuel has proceeded in a manner that has taken account of the requirements for social acceptability as well as technical excellence. As the agency responsible for development of the disposal concept, Atomic Energy of Canada Limited (AECL) has devoted considerable effort to consultation with the various publics that have an interest in the concept. This evolutionary interactive and consultative process, which has been underway for some 14 years, has attempted to keep the public informed of the technical development of the concept and to invite feedback. This paper describes the major elements of this evolutionary process, which will continue throughout the concept assessment and review process currently in progress. (author)

Nuclear fuel waste disposal. Canada's consultative approach

Energy Technology Data Exchange (ETDEWEB)

Hillier, J A.R.; Dixon, R S [AECL (Canada)

1993-07-01

Over the past two decades, society has increasingly demanded more public participation and public input into decision-making by governments. Development of the Canadian concept for deep geological disposal of used nuclear fuel has proceeded in a manner that has taken account of the requirements for social acceptability as well as technical excellence. As the agency responsible for development of the disposal concept, Atomic Energy of Canada Limited (AECL) has devoted considerable effort to consultation with the various publics that have an interest in the concept. This evolutionary interactive and consultative process, which has been underway for some 14 years, has attempted to keep the public informed of the technical development of the concept and to invite feedback. This paper describes the major elements of this evolutionary process, which will continue throughout the concept assessment and review process currently in progress. (author)

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. INDRANIL BISWAS. Articles written in Proceedings – Mathematical Sciences. Volume 111 Issue 3 August 2001 pp 263-269. Stability of Picard Bundle Over Moduli Space of Stable Vector Bundles of Rank Two Over a Curve · Indranil Biswas Tomás L Gómez.

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. OLIVIA X M YAO. Articles written in Proceedings – Mathematical Sciences. Volume 127 Issue 3 June 2017 pp 393-410 Research Article. New modular relations involving cubes of the Göllnitz–Gordon functions · OLIVIA X M YAO · More Details Abstract Fulltext PDF.

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. K R Parthasarathy. Articles written in Proceedings – Mathematical Sciences. Volume 113 Issue 1 February 2003 pp 3-13. A Remark on the Unitary Group of a Tensor Product of Finite-Dimensional Hilbert Spaces · K R Parthasarathy · More Details Abstract Fulltext ...

Radiofrequency plasma heating: proceedings

International Nuclear Information System (INIS)

Swenson, D.G.

1985-01-01

The conference proceedings include sessions on Alfven Wave Heating, ICRF Heating and Current Drive, Lower Hybrid Heating and Current Drive, and ECRF Heating. Questions of confinement, diagnostics, instabilities and technology are considered. Individual papers are cataloged separately

Federal Court of Administration dismissed appeals in nuclear power plant proceedings

International Nuclear Information System (INIS)

Anon.

1980-01-01

On July 18, 1980 the Federal Court of Administration handed down several decisions made in proceedings on nuclear power stations. It dismissed the appeal field by the complaining party. 1. In the proceedings concerning the Kruemmel reactor being about to be completed, the World Association for the Protecteion of Life was again denied the right to file a complaint. 2. In the proceedings concerning the nuclear power station under construction at Muelheim-Kaerlich, the objections raised were regarded as being insufficient for repealing the licence. 3. In the proceedings concerning the nuclear power staion at Wyhl which has not been built yet, the objections raised were declared not to be sufficiently substantiated in time. The written opinions of all proceedings are not yet available. (HSCH) [de

Fuel cells are gaining ground. Fuel cells as a key technology: future potential, state of the art, economic aspects, practical reports. Proceedings. Brennstoffzellen auf dem Vormarsch. Die Brennstoffzelle als Schluesseltechnologie. Zukunftspotentiale, Stand der Technik, Wirtschaftlichkeit und Praxisberichte. Tagungsband

Energy Technology Data Exchange (ETDEWEB)

1999-01-01

This conference report comprises 16 papers on fuel cells. Subjects: Funds for fuel cell technology provided by the 4. programme for energy research and energy technologies; Funds provided by the European Commission for demonstration projects; Fuel cells: Stationary applications in power supply; Liberalisation of the energy markets - effects on fuel cell development; Fuel cell technology from a utility's point of view; PEMFC membrane fuel cells; PFC in domestic energy supply; Applications of PEMFC in stationary power generation; Development of a fuel cell drive; Comparative evaluations of passenger car drives with fuel cells and internal combustion engines; Economic aspects of PAFC fuel cells; Development of the carbonate fuel cell (MCFC); Demonstration plant at Santa Clara (MCFC); Development, demonstration and application of oxide ceramics fuel cells SOFC, Experience with SOFC. Four contributions are available as separate records in this database.

22 CFR 401.30 - Proceedings under Article X.

Science.gov (United States)

2010-04-01

... 22 Foreign Relations 2 2010-04-01 2010-04-01 true Proceedings under Article X. 401.30 Section 401... References § 401.30 Proceedings under Article X. When a question or matter of difference arising between the... Article X of the Treaty, the Commission, after consultation with the said Governments, will adopt such...

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. Proceedings – Mathematical Sciences. Volumes & Issues. Volume 128. Issue 1. Mar 2018; Issue 2. Apr 2018. Volume 127. Issue 1. Feb 2017; Issue 2. Apr 2017; Issue 3. Jun 2017; Issue 4. Sep 2017; Issue 5. Nov 2017. Volume 126. Issue 1. Feb 2016; Issue 2

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. Hongliang Yao. Articles written in Proceedings – Mathematical Sciences. Volume 120 Issue 2 April 2010 pp 199-207. A T -Algebras and Extensions of A T -Algebras · Hongliang Yao · More Details Abstract Fulltext PDF. Lin and Su classified A T -algebras of real rank ...

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. Vijay Kodiyalam. Articles written in Proceedings – Mathematical Sciences. Volume 110 Issue 3 August 2000 pp 263-292. The Algebra of -relations · Vijay Kodiyalam R Srinivasan V S Sunder · More Details Abstract Fulltext PDF. In this paper, we study a tower { A n G ...

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. Bülent Nafi Örnek. Articles written in Proceedings – Mathematical Sciences. Volume 126 Issue 1 February 2016 pp 69-78. Sharpened forms of the generalized Schwarz inequality on the boundary · Tuğba Akyel Bülent Nafi Örnek · More Details Abstract Fulltext PDF.

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. K B Sinha. Articles written in Proceedings – Mathematical Sciences. Volume 111 Issue 2 May 2001 pp 179-201. Spectra of Anderson Type Models with Decaying Randomness · M Krishna K B Sinha · More Details Abstract Fulltext PDF. In this paper we consider some ...

Proceedings of oceans '91

International Nuclear Information System (INIS)

Anon.

1991-01-01

This volume contains the proceedings of the Oceans '91 Conference. Topics addressed include: ocean energy conversion, marine communications and navigation, ocean wave energy conversion, environmental modeling, global climate change, ocean minerals technology, oil spill technology, and submersible vehicles

Development of rapid mixing fuel nozzle for premixed combustion

International Nuclear Information System (INIS)

Katsuki, Masashi; Chung, Jin Do; Kim, Jang Woo; Hwang, Seung Min; Kim, Seung Mo; Ahn, Chul Ju

2009-01-01

Combustion in high-preheat and low oxygen concentration atmosphere is one of the attractive measures to reduce nitric oxide emission as well as greenhouse gases from combustion devices, and it is expected to be a key technology for the industrial applications in heating devices and furnaces. Before proceeding to the practical applications, we need to elucidate combustion characteristics of non-premixed and premixed flames in high-preheat and low oxygen concentration conditions from scientific point of view. For the purpose, we have developed a special mixing nozzle to create a homogeneous mixture of fuel and air by rapid mixing, and applied this rapidmixing nozzle to a Bunsen-type burner to observe combustion characteristics of the rapid-mixture. As a result, the combustion of rapid-mixture exhibited the same flame structure and combustion characteristics as the perfectly prepared premixed flame, even though the mixing time of the rapid-mixing nozzle was extremely short as a few milliseconds. Therefore, the rapid-mixing nozzle in this paper can be used to create preheated premixed flames as far as the mixing time is shorter than the ignition delay time of the fuel

RHIC spin physics: Proceedings. Volume 7

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-01

This proceedings compiles one-page summaries and five transparencies for each talk, with the intention that the speaker should include a web location for additional information in the summary. Also, email addresses are given with the participant list. The order follows the agenda: gluon, polarimetry, accelerator, W production and quark/antiquark polarization, parity violation searches, transversity, single transverse spin, small angle elastic scattering, and the final talk on ep collisions at RHIC. The authors begin the Proceedings with the full set of transparencies from Bob Jaffe`s colloquium on spin, by popular request.

RHIC spin physics: Proceedings. Volume 7

International Nuclear Information System (INIS)

1998-01-01

This proceedings compiles one-page summaries and five transparencies for each talk, with the intention that the speaker should include a web location for additional information in the summary. Also, email addresses are given with the participant list. The order follows the agenda: gluon, polarimetry, accelerator, W production and quark/antiquark polarization, parity violation searches, transversity, single transverse spin, small angle elastic scattering, and the final talk on ep collisions at RHIC. The authors begin the Proceedings with the full set of transparencies from Bob Jaffe's colloquium on spin, by popular request

Proceedings of the OECD/CSNI specialists meeting on fuel-coolant interactions

Energy Technology Data Exchange (ETDEWEB)

Akiyama, Mamoru; Yamano, Norihiro; Sugimoto, Jun [eds.

1998-01-01

The OECD/CSNI Specialists Meeting on Fuel Coolant Interactions (FCI) was held at Tokai-mura in Japan on May 19 through 21, 1997, and attended by 80 participants from 14 countries and one international organizations. In the meeting 36 papers were presented followed by active discussions in six sessions on various aspects of FCI issues, such as reactor application, premixing, propagation/trigger, experiments and code/models. At the end of the Meeting, the participants have reached to the consensus on the summary and recommendations, which consists of the following items; (1) We find no new evidence that would change or violate the conclusion of SERG-2 (1996) that alpha-mode failure is not risk significant. (2) Significant progress has been made since the Santa Barbara meeting (1993). (3) Several areas have been identified, which need further investigations to understand the basic FCI phenomena, and to improve the modeling. (4) We recommend maximizing open communication between various research groups in order to accelerate the resolution of the remaining issues. (5) We recommend that the next specialist meeting be held within 3 to 5 years in order to synthesize the activities described above. (J.P.N.)

Magnetotomography—a new method for analysing fuel cell performance and quality

Science.gov (United States)

Hauer, Karl-Heinz; Potthast, Roland; Wüster, Thorsten; Stolten, Detlef

Magnetotomography is a new method for the measurement and analysis of the current density distribution of fuel cells. The method is based on the measurement of the magnetic flux surrounding the fuel cell stack caused by the current inside the stack. As it is non-invasive, magnetotomography overcomes the shortcomings of traditional methods for the determination of current density in fuel cells [J. Stumper, S.A. Campell, D.P. Wilkinson, M.C. Johnson, M. Davis, In situ methods for the determination of current distributions in PEM fuel cells, Electrochem. Acta 43 (1998) 3773; S.J.C. Cleghorn, C.R. Derouin, M.S. Wilson, S. Gottesfeld, A printed circuit board approach to measuring current distribution in a fuel cell, J. Appl. Electrochem. 28 (1998) 663; Ch. Wieser, A. Helmbold, E. Gülzow, A new technique for two-dimensional current distribution measurements in electro-chemical cells, J. Appl. Electrochem. 30 (2000) 803; Grinzinger, Methoden zur Ortsaufgelösten Strommessung in Polymer Elektrolyt Brennstoffzellen, Diploma thesis, TU-München, 2003; Y.-G. Yoon, W.-Y. Lee, T.-H. Yang, G.-G. Park, C.-S. Kim, Current distribution in a single cell of PEMFC, J. Power Sources 118 (2003) 193-199; M.M. Mench, C.Y. Wang, An in situ method for determination of current distribution in PEM fuel cells applied to a direct methanol fuel cell, J. Electrochem. Soc. 150 (2003) A79-A85; S. Schönbauer, T. Kaz, H. Sander, E. Gülzow, Segmented bipolar plate for the determination of current distribution in polymer electrolyte fuel cells, in: Proceedings of the Second European PEMFC Forum, vol. 1, Lucerne/Switzerland, 2003, pp. 231-237; G. Bender, S.W. Mahlon, T.A. Zawodzinski, Further refinements in the segmented cell approach to diagnosing performance in polymer electrolyte fuel cells, J. Power Sources 123 (2003) 163-171]. After several years of research a complete prototype system is now available for research on single cells and stacks. This paper describes the basic system (fundamentals

Virtuelle Fachbibliothek Sozialwissenschaften - Projektskizze

OpenAIRE

Kluck, Michael; Krause, Jürgen; Müller, Matthias N.O.; Schmiede, Rudi; Wenzel, H.; Winkler, Stefan; Meier, Wolfgang

2000-01-01

Das Projekt zielt auf die integrierte Bereitstellung sozialwissenschaftlicher Literaturinformationen aus verteilten und inhaltlich unterschiedlich erschlossenen Datenbeständen. In erster Linie sollen Probleme des inhaltlichen Zugriffs auf solch heterogene Dokumentenbestände gelöst werden.

Fuel cell generator with fuel electrodes that control on-cell fuel reformation

Science.gov (United States)

Ruka, Roswell J [Pittsburgh, PA; Basel, Richard A [Pittsburgh, PA; Zhang, Gong [Murrysville, PA

2011-10-25

A fuel cell for a fuel cell generator including a housing including a gas flow path for receiving a fuel from a fuel source and directing the fuel across the fuel cell. The fuel cell includes an elongate member including opposing first and second ends and defining an interior cathode portion and an exterior anode portion. The interior cathode portion includes an electrode in contact with an oxidant flow path. The exterior anode portion includes an electrode in contact with the fuel in the gas flow path. The anode portion includes a catalyst material for effecting fuel reformation along the fuel cell between the opposing ends. A fuel reformation control layer is applied over the catalyst material for reducing a rate of fuel reformation on the fuel cell. The control layer effects a variable reformation rate along the length of the fuel cell.

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. José M Sigarreta. Articles written in Proceedings – Mathematical Sciences. Volume 120 Issue 5 November 2010 pp 593-609. Gromov Hyperbolicity in Cartesian Product Graphs · Junior Michel José M Rodríguez José M Sigarreta María Villeta · More Details Abstract ...

Proceedings – Mathematical Sciences | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Proceedings – Mathematical Sciences. A R Aithal. Articles written in Proceedings – Mathematical Sciences. Volume 115 Issue 1 February 2005 pp 93-102. On Two Functionals Connected to the Laplacian in a Class of Doubly Connected Domains in Space-Forms · M H C Anisa A R Aithal · More Details ...

12 CFR 513.7 - Proceeding under this part.

Science.gov (United States)

2010-01-01