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Development And Application Of An Advanced Fuel Model For The Safety Analysis Of The Generation Iv Gas Cooled Fast Reactor
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Book Synopsis Development and Application of an Advanced Fuel Model for the Safety Analysis of the Generation IV Gas-cooled Fast Reactor by : Petr Petkevich
Download or read book Development and Application of an Advanced Fuel Model for the Safety Analysis of the Generation IV Gas-cooled Fast Reactor written by Petr Petkevich and published by . This book was released on 2008 with total page 250 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Nuclear Data Needs for Generation IV Nuclear Energy Systems by : P. Rullhusen
Download or read book Nuclear Data Needs for Generation IV Nuclear Energy Systems written by P. Rullhusen and published by World Scientific. This book was released on 2006 with total page 300 pages. Available in PDF, EPUB and Kindle. Book excerpt: This volume presents recent progress in the improvement of the nuclear database needed for the development of Generation IV nuclear energy systems. The Generation IV International Forum (GIF) identified six advanced concepts for sustainable nuclear energy production at competitive prices and with advanced safety, with special attention to nuclear non-proliferation and physical protection issues, minimization of long-lived radiotoxic waste, and optimum natural resource utilization System groups have been established for studying these concepts in detail, and nuclear data are an inherent part of these studies. This book reviews the work recently performed for the development of these systems. The contributions include an up-to-date overview of recent achievements in sensitivity analysis, model calculations, estimates of uncertainties, and the present status of nuclear databases with regard to their applications to Generation IV systems. In the workshop, special attention was given to the identification of nuclear data needs from sensitivity analysis of benchmark experiments and the treatment of uncertainties. The proceedings contain overviews of several experimental program and recent results of interest for the development of Generation IV systems. Contents: Nuclear Data Needs for Generation IV Systems: Future of Nuclear Energy and the Role of Nuclear Data (P Finck); Nuclear Data Needs for Generation IV Nuclear Energy Systems OCo Summary of US Workshop (T A Taiwo & H S Khalil); Innovative Fuel Types for Minor Actinides Transmutation (D Haas et al.); Benchmarks, Sensitivity Calculations, Uncertainties: Sensitivity of Advanced Reactor and Fuel Cycle Performance Parameters to Nuclear Data Uncertainties (G Aliberti et al.); Computer Model of an Error Propagation Through Micro-Campaign of Fast Neutron Gas Cooled Nuclear Reactor (E Ivanov); Generating Covariance Data with Nuclear Models (A J Koning); Experiments: INL Capabilities for Nuclear Data Measurements Using the Argonne Intense Pulsed Neutron Source Facility (J D Cole et al.); Cross-Section Measurements in the Fast Neutron Energy Range (A Plompen); Recent Measurements of Neutron Capture Cross Sections for Minor Actinides by an JNC and Kyoto University Group (H Harada et al.); Evaluated Data Libraries: Nuclear Data Evaluation for Generation IV (G Nogu re et al.); Improved Evaluations of Neutron-Induced Reactions on Americium Isotopes (P Talou et al.); and several other important contributions. Readership: Graduate students and nuclear physicists interested in experimental nuclear physics, nuclear reactions modeling, and reactor physics, especially the development of Generation IV reactors."
Book Synopsis Handbook of Generation IV Nuclear Reactors by : Igor Pioro
Download or read book Handbook of Generation IV Nuclear Reactors written by Igor Pioro and published by Woodhead Publishing. This book was released on 2022-12-07 with total page 1112 pages. Available in PDF, EPUB and Kindle. Book excerpt: Handbook of Generation IV Nuclear Reactors, Second Edition is a fully revised and updated comprehensive resource on the latest research and advances in generation IV nuclear reactor concepts. Editor Igor Pioro and his team of expert contributors have updated every chapter to reflect advances in the field since the first edition published in 2016. The book teaches the reader about available technologies, future prospects and the feasibility of each concept presented, equipping them users with a strong skillset which they can apply to their own work and research. Provides a fully updated, revised and comprehensive handbook dedicated entirely to generation IV nuclear reactors Includes new trends and developments since the first publication, as well as brand new case studies and appendices Covers the latest research, developments and design information surrounding generation IV nuclear reactors
Book Synopsis Nuclear Data Needs For Generation Iv Nuclear Energy Systems - Proceedings Of The International Workshop by : Peter Rullhusen
Download or read book Nuclear Data Needs For Generation Iv Nuclear Energy Systems - Proceedings Of The International Workshop written by Peter Rullhusen and published by World Scientific. This book was released on 2006-05-08 with total page 300 pages. Available in PDF, EPUB and Kindle. Book excerpt: This volume presents recent progress in the improvement of the nuclear database needed for the development of Generation IV nuclear energy systems.The Generation IV International Forum (GIF) identified six advanced concepts for sustainable nuclear energy production at competitive prices and with advanced safety, with special attention to nuclear non-proliferation and physical protection issues, minimization of long-lived radiotoxic waste, and optimum natural resource utilization System groups have been established for studying these concepts in detail, and nuclear data are an inherent part of these studies. This book reviews the work recently performed for the development of these systems.The contributions include an up-to-date overview of recent achievements in sensitivity analysis, model calculations, estimates of uncertainties, and the present status of nuclear databases with regard to their applications to Generation IV systems. In the workshop, special attention was given to the identification of nuclear data needs from sensitivity analysis of benchmark experiments and the treatment of uncertainties. The proceedings contain overviews of several experimental program and recent results of interest for the development of Generation IV systems.
Book Synopsis Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor by : Willem Frederik Geert van Rooijen
Download or read book Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor written by Willem Frederik Geert van Rooijen and published by IOS Press. This book was released on 2006 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis Handbook of Generation IV Nuclear Reactors by : Igor Pioro
Download or read book Handbook of Generation IV Nuclear Reactors written by Igor Pioro and published by Woodhead Publishing. This book was released on 2016-06-09 with total page 942 pages. Available in PDF, EPUB and Kindle. Book excerpt: Handbook of Generation IV Nuclear Reactors presents information on the current fleet of Nuclear Power Plants (NPPs) with water-cooled reactors (Generation III and III+) (96% of 430 power reactors in the world) that have relatively low thermal efficiencies (within the range of 32 36%) compared to those of modern advanced thermal power plants (combined cycle gas-fired power plants – up to 62% and supercritical pressure coal-fired power plants – up to 55%). Moreover, thermal efficiency of the current fleet of NPPs with water-cooled reactors cannot be increased significantly without completely different innovative designs, which are Generation IV reactors. Nuclear power is vital for generating electrical energy without carbon emissions. Complete with the latest research, development, and design, and written by an international team of experts, this handbook is completely dedicated to Generation IV reactors. Presents the first comprehensive handbook dedicated entirely to generation IV nuclear reactors Reviews the latest trends and developments Complete with the latest research, development, and design information in generation IV nuclear reactors Written by an international team of experts in the field
Book Synopsis Probabilistic Risk Assessment of a Vented Fuel System Utilized in a Generation IV Gas-cooled Fast Reactor Nuclear Power Plant by : Renae Lenhof
Download or read book Probabilistic Risk Assessment of a Vented Fuel System Utilized in a Generation IV Gas-cooled Fast Reactor Nuclear Power Plant written by Renae Lenhof and published by . This book was released on 2014 with total page 209 pages. Available in PDF, EPUB and Kindle. Book excerpt: A limited scope Probabilistic Risk Assessment (PRA) of a vented nuclear fuel system for a Generation IV Gas-Cooled Fast Reactor Plant was performed. The goal of the study was to better understand the safety and licensing implications of vented fuel technology. A Level 1 PRA was performed to determine the possible and probable failure mechanisms of the vented fuel fission product collection and auxiliary systems. A Level 2 PRA was performed to determine the possible releases from the vented fuel collection system under normal and abnormal operating conditions. Finally, a Level 3 PRA was performed to understand the consequence of a release of fission products from the vented fuel collection system to the population and environment. This work has found that the most probable system damage states are a release from the vented fuel system within the containment building and within the auxiliary building. As a result of the reduced fission product boundaries present in the event of a release within the auxiliary building, consequences of these events prove to be more severe. Three source term groups were found to have exceedingly higher dose consequences with respect to their estimated frequencies. As a result, the present analysis indicates that additional design and analysis on the vented fuel system is required. It should be noted that the present work operates under several highly conservative assumptions. Consequently, the vented fuel system, as modeled, may be safely operated without design changes pending the refinement of the models used to determine source term estimates and atmospheric transport. Specifically, the conservative modeling assumptions that have the potential to greatly reduce the estimated consequences, if refined, include the fraction of the activity within the adsorber beds that is released under accident conditions, the specific attenuation factors applied to the various fission product boundaries, and the atmospheric conditions selected for the atmospheric transport model. In addition, design changes such as an increase in the Exclusion Area Boundary (EAB) or placement of the entire vented fuel system within the containment building may further reduce the consequences of a release. This work was performed using funding received from the DOE Office of Nuclear Energy's Nuclear Energy University Program.
Book Synopsis High Temperature Gas-cooled Reactors by : Tetsuaki Takeda
Download or read book High Temperature Gas-cooled Reactors written by Tetsuaki Takeda and published by Academic Press. This book was released on 2021-02-24 with total page 478 pages. Available in PDF, EPUB and Kindle. Book excerpt: High-Temperature Gas Reactors is the fifth volume in the JSME Series on Thermal and Nuclear Power Generation. Series Editor Yasuo Koizumi and his Volume editors Tetsuaki Takeda and Yoshiyuki Inagaki present the latest research on High-Temperature Gas Reactor (HTGR) development and utilization, beginning with an analysis of the history of HTGRs. A detailed analysis of HTGR design features, including reactor core design, cooling tower design, pressure vessel design, I&C factors and safety design, provides readers with a solid understanding of how to develop efficient and safe HTGR within a nuclear power plant. The authors combine their knowledge to present a guide on the safety of HTGRs throughout the entire reactor system, drawing on their unique experience to pass on lessons learned and best practices to support professionals and researchers in their design and operation of these advanced reactor types. Case studies of critical testing carried out by the authors provide the reader with firsthand information on how to conduct tests safely and effectively and an understanding of which responses are required in unexpected incidents to achieve their research objectives. An analysis of technologies and systems in development and testing stages offer the reader a look to the future of HTGRs and help to direct and inform their further research in heat transfer, fluid-dynamics, fuel options and advanced reactor facility selection. This volume is of interest for nuclear and thermal energy engineers and researchers focusing on HTGRs, HTGR plant designers and operators, regulators, post graduate students of nuclear engineering, national labs, government officials and agencies in power and energy policy and regulations. Written by the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers and draws upon their combined wealth of knowledge and experience Includes real examples and case studies from Japan, the US and Europe to provide a deeper learning opportunity with practical benefits Considers the societal impact and sustainability concerns and goals throughout the discussion Includes safety factors and considerations, as well as unique results from performance testing of HTGR systems.
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976 with total page 680 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Summary Review on the Application of Computational Fluid Dynamics in Nuclear Power Plant Design by : IAEA
Download or read book Summary Review on the Application of Computational Fluid Dynamics in Nuclear Power Plant Design written by IAEA and published by International Atomic Energy Agency. This book was released on 2022-03-28 with total page 121 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication documents the results of an IAEA coordinated research project (CRP)on the application of computational fluid dynamics (CFD) codes for nuclear power plant design. The main objective was to benchmark CFD codes, model options and methods against CFD experimental data under single phase flow conditions. This publication summarizes the current capabilities and applications of CFD codes, and their present qualification level, with respect to nuclear power plant design requirements. It is not intended to be comprehensive, focusing instead on international experience in the practical application of these tools in designing nuclear power plant components and systems. The guidance in this publication is based on inputs provided by international nuclear industry experts directly involved in nuclear power plant design issues, CFD applications, and in related experimentation and validation highlighted during the CRP.
Book Synopsis ERDA Energy Research Abstracts by : United States. Energy Research and Development Administration
Download or read book ERDA Energy Research Abstracts written by United States. Energy Research and Development Administration and published by . This book was released on 1976 with total page 938 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis ERDA Research Abstracts by : United States. Energy Research and Development Administration
Download or read book ERDA Research Abstracts written by United States. Energy Research and Development Administration and published by . This book was released on 1976 with total page 1040 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Specification of Advanced Safety Modeling Requirements (Rev. 0). by :
Download or read book Specification of Advanced Safety Modeling Requirements (Rev. 0). written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The U.S. Department of Energy's Global Nuclear Energy Partnership has lead to renewed interest in liquid-metal-cooled fast reactors for the purpose of closing the nuclear fuel cycle and making more efficient use of future repository capacity. However, the U.S. has not designed or constructed a fast reactor in nearly 30 years. Accurate, high-fidelity, whole-plant dynamics safety simulations will play a crucial role by providing confidence that component and system designs will satisfy established design limits and safety margins under a wide variety of operational, design basis, and beyond design basis transient conditions. Current modeling capabilities for fast reactor safety analyses have resulted from several hundred person-years of code development effort supported by experimental validation. The broad spectrum of mechanistic and phenomenological models that have been developed represent an enormous amount of institutional knowledge that needs to be maintained. Complicating this, the existing code architectures for safety modeling evolved from programming practices of the 1970s. This has lead to monolithic applications with interdependent data models which require significant knowledge of the complexities of the entire code in order for each component to be maintained. In order to develop an advanced fast reactor safety modeling capability, the limitations of the existing code architecture must be overcome while preserving the capabilities that already exist. To accomplish this, a set of advanced safety modeling requirements is defined, based on modern programming practices, that focuses on modular development within a flexible coupling framework. An approach for integrating the existing capabilities of the SAS4A/SASSYS-1 fast reactor safety analysis code into the SHARP framework is provided in order to preserve existing capabilities while providing a smooth transition to advanced modeling capabilities. In doing this, the advanced fast reactor safety models will target leadership-class computing architectures for massively-parallel high-fidelity computations while providing continued support for rapid prototyping using modest fidelity computations on multiple-core desktop platforms.
Download or read book NASA Technical Memorandum written by and published by . This book was released on 1975 with total page 582 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Nuclear Power Plant Design and Analysis Codes by : Jun Wang
Download or read book Nuclear Power Plant Design and Analysis Codes written by Jun Wang and published by Woodhead Publishing. This book was released on 2020-11-10 with total page 612 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application presents the latest research on the most widely used nuclear codes and the wealth of successful accomplishments which have been achieved over the past decades by experts in the field. Editors Wang, Li,Allison, and Hohorst and their team of authors provide readers with a comprehensive understanding of nuclear code development and how to apply it to their work and research to make their energy production more flexible, economical, reliable and safe.Written in an accessible and practical way, each chapter considers strengths and limitations, data availability needs, verification and validation methodologies and quality assurance guidelines to develop thorough and robust models and simulation tools both inside and outside a nuclear setting. This book benefits those working in nuclear reactor physics and thermal-hydraulics, as well as those involved in nuclear reactor licensing. It also provides early career researchers with a solid understanding of fundamental knowledge of mainstream nuclear modelling codes, as well as the more experienced engineers seeking advanced information on the best solutions to suit their needs. Captures important research conducted over last few decades by experts and allows new researchers and professionals to learn from the work of their predecessors Presents the most recent updates and developments, including the capabilities, limitations, and future development needs of all codes Incudes applications for each code to ensure readers have complete knowledge to apply to their own setting
Download or read book Energy Research Abstracts written by and published by . This book was released on 1989 with total page 596 pages. Available in PDF, EPUB and Kindle. Book excerpt: Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.
Book Synopsis Proceedings of the 2023 International Conference on Finance, Trade and Business Management (FTBM 2023) by : Amalendu Bhunia
Download or read book Proceedings of the 2023 International Conference on Finance, Trade and Business Management (FTBM 2023) written by Amalendu Bhunia and published by Springer Nature. This book was released on 2023-11-30 with total page 609 pages. Available in PDF, EPUB and Kindle. Book excerpt: This is an open access book. Finance and trade are the keys to the world's continued economic and social development. Studying finance and trade can help us better understand how the world works. In addition, business management is crucial for an enterprise and a country's sustainable development. The conference mainly focused on research fields such as finance, trade, and business management. The 2023 International Conference on Finance, Trade, and Business Management(FTBM2023)will be held on September 22-24, 2023 by ZOOM. The purpose of the conference is to provide a chance for experts and scholars engaged in finance, trade, and business management-related research to exchange scientific research results and cutting-edge technologies, understand academic development trends, broaden research ideas, strengthen academic research and discussions, and promote cooperation in the industrialization of academic achievements. We sincerely invite experts, scholars, business people, and other relevant people from universities and scientific research institutions at home and abroad to attend the conference!
