Advanced Fuel Cycle And Reactor Concepts
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Advanced Fuel Cycle And Reactor Concepts
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Author : International Nuclear Fuel Cycle Evaluation
language : en
Publisher:
Release Date : 1980
Advanced Fuel Cycle And Reactor Concepts written by International Nuclear Fuel Cycle Evaluation and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1980 with Technology & Engineering categories.
Advanced Reactor Concepts Arc
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Author : Ali Zamani Paydar
language : en
Publisher: Elsevier
Release Date : 2023-07-20
Advanced Reactor Concepts Arc written by Ali Zamani Paydar and has been published by Elsevier this book supported file pdf, txt, epub, kindle and other format this book has been release on 2023-07-20 with Technology & Engineering categories.
Nuclear engineers advancing the energy transition are understanding more about the next generation of nuclear plants; however, it is still difficult to access all the critical types, concepts, and applications in one location. Advanced Reactor Concepts (ARC): A New Nuclear Power Plant Perspective Producing Energy gives engineers and nuclear engineering researchers the comprehensive tools to get up to date on the latest technology supporting generation IV nuclear plant systems. After providing a brief history of this area, alternative technology is discussed such as electromagnetic pumps, heat pipes as control devices, Nuclear Air-Brayton Combined Cycles integration, and instrumentation helping nuclear plants to provide dispatchable electricity to the grid and heat to industry. Packed with examples of all the types, benefits, and challenges involved, Advanced Reactor Concepts (ARC) delivers the go-to reference that engineers need to advance safe nuclear energy as a low-carbon option. Describes theory and concepts on generation IV technology such as advanced reactor concepts (ARC) and electromagnetic pumps, and compares different types and sizes. Sets out the energy transition with critical carbon-free technology that can supplement intermittent power sources such as wind and solar. Explains alternative heat storage technology, including Nuclear Air-Brayton Combined Cycles. Introduces advanced main instrumentation systems for in-core probes.
Data Base For A Candu Phw Operating On The Thorium Cycle
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Author : Atomic Energy of Canada Limited
language : en
Publisher:
Release Date : 1979
Data Base For A Candu Phw Operating On The Thorium Cycle written by Atomic Energy of Canada Limited and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1979 with categories.
Infce Summary Volume
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Author : International Nuclear Fuel Cycle Evaluation
language : en
Publisher:
Release Date : 1980
Infce Summary Volume written by International Nuclear Fuel Cycle Evaluation and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1980 with Technology & Engineering categories.
Of working group 1 : fuel and heavy water availability -- Summary of working group 2 : enrichment availability -- Summary of working group 3 : assurances of long-term supply of technology, fuel and heavy water and services in the interest of national needs consistent with non-proliferation -- Summary of working group 4 : reprocessing, plutonium handling, recycle -- Summary of working group 5 : fast breeders -- Summary of working group 6 : spent fuel management -- Summary of working group 7 : waste management and disposal -- Summary of working group 8 : advanced fuel cycle and reactor concepts -- Final communiqué of the organizing conference of the international nuclear fuel cycle evaluation -- Technical and economic scope and methods of work -- Press communiqué of the first INFCE plenary conference -- List of actions and decisions taken by the first INFCE plenary conference -- List of participants in the first INFCE plenary conference -- Communiqué of the final INFCE plenary conference -- List of participants in the final INFCE plenary conference -- List of participants in the technical co-ordinating committee -- Primer on the nuclear fuel cycle -- INFCE documentation.
Data Base For A Candu Phw Operating On A Once Through Natural Uranium Cycle
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Author : Atomic Energy of Canada Limited
language : en
Publisher:
Release Date : 1979
Data Base For A Candu Phw Operating On A Once Through Natural Uranium Cycle written by Atomic Energy of Canada Limited and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1979 with categories.
Data Base For A Candu Phw Operating On A Once Through Slightly Enriched Uranium Cycle
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Author : Atomic Energy of Canada Limited
language : en
Publisher:
Release Date : 1979
Data Base For A Candu Phw Operating On A Once Through Slightly Enriched Uranium Cycle written by Atomic Energy of Canada Limited and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1979 with categories.
Improving Fuel Cycle Design And Safety Characteristics Of A Gas Cooled Fast Reactor
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Author : Willem Frederik Geert van Rooijen
language : en
Publisher: IOS Press
Release Date : 2006
Improving Fuel Cycle Design And Safety Characteristics Of A Gas Cooled Fast Reactor written by Willem Frederik Geert van Rooijen and has been published by IOS Press this book supported file pdf, txt, epub, kindle and other format this book has been release on 2006 with Technology & Engineering categories.
The Generation IV Forum is an international nuclear energy research initiative aimed at developing the fourth generation of nuclear reactors, envisaged to enter service halfway the 21st century. One of the Generation IV reactor systems is the Gas Cooled Fast Reactor (GCFR), the subject of study in this thesis. The Generation IV reactor concepts should improve all aspects of nuclear power generation. Within Generation IV, the GCFR concept specifically targets sustainability of nuclear power generation. The Gas Cooled Fast Reactor core power density is high in comparison to other gas cooled reactor concepts. Like all nuclear reactors, the GCFR produces decay heat after shut down, which has to be transported out of the reactor under all circumstances. The layout of the primary system therefore focuses on using natural convection Decay Heat Removal (DHR) where possible, with a large coolant fraction in the core to reduce friction losses.
Energy
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Author : John Grossenbacher
language : en
Publisher: TheCapitol.Net
Release Date : 2010
Energy written by John Grossenbacher and has been published by TheCapitol.Net this book supported file pdf, txt, epub, kindle and other format this book has been release on 2010 with Political Science categories.
Part of the government series on energy, from TheCapitol.Net, this text discusses the nuclear energy issues facing Congress including federal incentives for new commercial reactors, radioactive waste management policy, research and development priorities, power plant safety and regulation, nuclear weapons proliferation, and security against terrorist attacks.
Safety Issues Associated With Plutonium Involvement In The Nuclear Fuel Cycle
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Author : Theodore A. Parish
language : en
Publisher: Springer Science & Business Media
Release Date : 2012-12-06
Safety Issues Associated With Plutonium Involvement In The Nuclear Fuel Cycle written by Theodore A. Parish and has been published by Springer Science & Business Media this book supported file pdf, txt, epub, kindle and other format this book has been release on 2012-12-06 with Technology & Engineering categories.
The "VOLGA" conferences, hosted in odd-numbered years by the Department of Theoretical and Experimental Reactor Physics of the Moscow Engineering Physics Institute (MEPhI), are some of the most prestigious technical meetings held in Russia. Traditionally, these conferences present the opportunity for reactor physicists from around the world to gather at MEPhI's holiday camp on the banks of the Volga river (near Tver) to exchange ideas and explore innovative concepts related to nuclear power development. In 1997, NATO became involved in the "VOLGA" meetings for the first time by co-sponsoring "VOLGA97" as an advanced research workshop. This workshop broke with tradition a bit in that the venue was moved from MEPhI's holiday camp to a location nearer Moscow. The workshop program was effectively organized in order to cover a broad range of topics relating to the theme of the meeting. Generally, the papers concerned safety related questions associated with utilizing both weapons-grade and reactor-grade plutonium in the nuclear fuel cycle, including facility requirements, licensing issues, proliferation risks, and a variety of advanced concepts for alternative fuel cycles. The program contained a total of ninety-nine papers presented in five days of sessions.
Terms For Describing Advanced Nuclear Power Plants
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Author : IAEA
language : en
Publisher: International Atomic Energy Agency
Release Date : 2023-10-31
Terms For Describing Advanced Nuclear Power Plants written by IAEA and has been published by International Atomic Energy Agency this book supported file pdf, txt, epub, kindle and other format this book has been release on 2023-10-31 with Technology & Engineering categories.
The terms for describing advanced nuclear power plants (NPPs) need to conform to the broad, general, common understanding by the public as well as by the technical community. This publication is a revision of IAEA-TECDOC-936 incorporating developments and initiatives since 1997 in the areas of advanced, evolutionary, and innovative nuclear reactor designs, description of design development phases, inclusive of relevant safety and regulatory terminology, consistent with current IAEA safety standards and glossaries. The objective of this publication is to provide Member States with up-to-date terms for describing advanced NPPs, to draw distinctions between design phases reflecting the maturities of designs, and to clarify definitions of commonly used terms in describing advanced NPPs.