Download or read book Analysis of the FeCrAl Accident Tolerant Fuel Concept Benefits During BWR Station Blackout Accidents written by and published by . This book was released on 2015 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Iron-chromium-aluminum (FeCrAl) alloys are being considered for fuel concepts with enhanced accident tolerance. FeCrAl alloys have very slow oxidation kinetics and good strength at high temperatures. FeCrAl could be used for fuel cladding in light water reactors and/or as channel box material in boiling water reactors (BWRs). To estimate the potential safety gains afforded by the FeCrAl concept, the MELCOR code was used to analyze a range of postulated station blackout severe accident scenarios in a BWR/4 reactor employing FeCrAl. The simulations utilize the most recently known thermophysical properties and oxidation kinetics for FeCrAl. Overall, when compared to the traditional Zircaloy-based cladding and channel box, the FeCrAl concept provides a few extra hours of time for operators to take mitigating actions and/or for evacuations to take place. A coolable core geometry is retained longer, enhancing the ability to stabilize an accident. Finally, due to the slower oxidation kinetics, substantially less hydrogen is generated, and the generation is delayed in time. This decreases the amount of non-condensable gases in containment and the potential for deflagrations to inhibit the accident response.

Download or read book Advances in Materials Science for Environmental and Energy Technologies VI written by Tatsuki Ohji and published by John Wiley & Sons. This book was released on 2018-02-07 with total page 283 pages. Available in PDF, EPUB and Kindle. Book excerpt: An excellent one-volume resource for understanding the most important current issues in the research and advances in materials science for environmental and energy technologies This proceedings volume contains a collection of 20 papers from the 2016 Materials Science and Technology (MS&T'16) meeting held in Salt Lake City, UT, from October 24-27 of that year. These conference symposia provided a forum for scientists, engineers, and technologists to discuss and exchange state-of-the-art ideas, information, and technology on advanced methods and approaches for processing, synthesis, characterization, and applications of ceramics, glasses, and composites. Topics covered include: the 8th International Symposium on Green and Sustainable Technologies for Materials Manufacturing Processing; Materials Issues in Nuclear Waste Management in the 21st Century; Construction and Building Materials for a Better Environment; Materials for Nuclear Applications and Extreme Environments; Nanotechnology for Energy, Healthcare, and Industry; and Materials for Processes for CO2 Capture, Conversion and Sequestration. Logically organized and carefully selected articles give insight into advances in materials science for environmental and energy technologies. Incorporates the latest developments related to advances in materials science for environmental and energy technologies Advances in Materials Science for Environmental and Energy Technologies VI: Ceramic Transactions Volume 262 is ideal for academics in mechanical and chemical engineering, materials and or ceramics, chemistry departments and for those working in government laboratories.

Download or read book Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors written by John H. Jackson and published by Springer. This book was released on 2018-12-20 with total page 2532 pages. Available in PDF, EPUB and Kindle. Book excerpt: This two-volume set represents a collection of papers presented at the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The purpose of this conference series is to foster an exchange of ideas about problems and their remedies in water-cooled nuclear power plants of today and the future. Contributions cover problems facing nickel-based alloys, stainless steels, pressure vessel and piping steels, zirconium alloys, and other alloys in water environments of relevance. Components covered include pressure boundary components, reactor vessels and internals, steam generators, fuel cladding, irradiated components, fuel storage containers, and balance of plant components and systems.

Download or read book Development of a Full core Reactivity Equivalence for FeCrAl Enhanced Accident Tolerant Fuel in BWRs written by and published by . This book was released on 2015 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Demonstration of a Full core Reactivity Equivalence for FeCrAl Enhanced Accident Tolerant Fuel in BWRs written by and published by . This book was released on 2015 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Reactor Core Materials written by and published by . This book was released on 1960 with total page 304 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Fuel Safety Criteria written by OECD Nuclear Energy Agency and published by OECD Publishing. This book was released on 2001 with total page 74 pages. Available in PDF, EPUB and Kindle. Book excerpt: Presents brief descriptions of 20 fuel-related safety criteria along with both the rationale for having such criteria and possible new design and operational issues which could have an effect on them.

Download or read book Design basis Accident Analysis Methods For Light water Nuclear Power Plants written by Robert Martin and published by World Scientific. This book was released on 2019-02-13 with total page 717 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book captures the principles of safety evaluation as practiced in the regulated light-water reactor nuclear industry, as established and stabilized over the last 30 years. It is expected to serve both the current industry and those planning for the future. The work's coverage of the subject matter is the broadest to date, including not only the common topics of modeling and simulation, but also methods supporting the basis for the underlying assumptions, the extension to radiological safety, what to expect in a licensing review, historical perspectives and the implication for new designs.This text is an essential resource for practitioners and students, on the current best-practices in nuclear power plant safety and their basis. Contributors of this work are subject matter experts in their specialties, much of which was nurtured and inspired by Prof. Larry Hochreiter, a prominent nuclear safety pioneer.Related Link(s)

Download or read book Pellet clad Interaction in Water Reactor Fuels written by and published by OECD Publishing. This book was released on 2005 with total page 562 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication sets out the findings of an international seminar, held in Aix-en-Provence, France in March 2004, which considered recent progress in the field of pellet-clad interaction in light water reactor fuels. It also reviews current understanding of relevant phenomena and their impact on the nuclear fuel rod under the widest possible conditions, and about both uranium-oxide and mixed-oxide fuels.

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

Download or read book Post Dryout Heat Transfer written by G.F. Hewitt and published by Routledge. This book was released on 2017-10-06 with total page 446 pages. Available in PDF, EPUB and Kindle. Book excerpt: The study of post-dryout heat transfer has generated great interest because of its importance in determining maximum clad temperature in nuclear reactor loss-of-coolant accidents (LOCAs). An associated phenomenon, the deterioration of heat transfer in boiling, is significant to other industrial sectors. This book provides comprehensive coverage of post-dryout heat transfer, discussing such essential topics as post-dryout heat transfer in dispersed flow, interpretation and use of transient data in surface rewetting by reinstatement of flow or by reducing heat flux, rod bundles, two-phase flow occurrences in the post-dryout region, various methods for predicting ""inverted annular flow,"" and new experiments for measuring thermodynamic nonequilibrium with probes in the channel. The book also presents a basis for independent safety assessment of nuclear reactors and chemical plant systems where post-dryout heat transfer may occur. Post-Dryout Heat Transfer will be a useful reference for researchers and professionals in the nuclear and chemical production industries.

Download or read book Uranium Dioxide written by J. Belle and published by . This book was released on 1961 with total page 744 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fuel Modelling in Accident Conditions written by International Atomic Energy Agency and published by . This book was released on 2020-02-29 with total page 180 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication summarizes the findings and conclusions of an IAEA coordinated research project (CRP) on fuel modelling in accident conditions, which was initiated under the IAEA Action Plan on Nuclear Safety following the Fukushima accident. The overall aim of the project was to analyse and better understand fuel behavior in accident conditions, with a focus on loss of coolant accidents. In the course of the project the participants used a mixture of data derived from accident simulation experiments, in particular data designed to investigate the fuel behaviour during design basis accident and design extension conditions. They carried out calculations on priority cases selected from a matrix of cases identified at the first research coordination meeting and designed to support their individual priorities. These priority cases were chosen as the best available to help determine which of the many models used in the codes best reflect reality. The CRP provided an ideal platform to compare their code results with others and especially with experimental data, to which they otherwise would not have had access. The achievements made within this CRP fostered new collaborations and enhanced the development and improvement of common models and highlighted differences in the interpretation of some experiments and therefore in the use of the codes ? the so-called user effects.

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 Deterministic Safety Analysis for Nuclear Power Plants written by International Atomic Energy Agency and published by International Atomic Energy Agency. This book was released on 2019-09-24 with total page 85 pages. Available in PDF, EPUB and Kindle. Book excerpt: Deterministic safety analysis is an essential component of safety assessment, particularly for safety demonstration of the design of nuclear power plants (NPPs). The objective of deterministic safety analysis is to confirm that safety functions can be fulfilled and that the necessary structures, systems and components, in combination with operator actions, are effective in keeping the releases of radioactive material from the plant below acceptable limits. Deterministic safety analysis, supplemented by further specific information and analysis, including probabilistic safety analysis, is also intended to demonstrate that the source term and the potential radiological consequences of different plant states are acceptable, and that the possibility of certain conditions arising that could lead to an early or a large radioactive release can be considered as 'practically eliminated'. The publication has been updated to maintain consistency with current IAEA safety requirements and to reflect lessons from the Fukushima Daiichi accident. It takes into account current practices and experience from deterministic safety analyses for NPPs being performed around the world.

Download or read book Fiber Bragg Grating Sensors Recent Advancements Industrial Applications and Market Exploitation written by Andrea Cusano and published by Bentham Science Publishers. This book was released on 2011 with total page 331 pages. Available in PDF, EPUB and Kindle. Book excerpt: The book is an exciting source of information for individuals interested in learning about and marketing sensors. The book focuses on scientific and commercial advances in Fiber Bragg Grating (FBG) sensor technology since its discovery over 30 years ago.

Download or read book Review of Fuel Failures in Water Cooled Reactors 2006 2015 IAEA Nuclear Energy Series No Nf T 2 5 written by International Atomic Energy Agency and published by . This book was released on 2019-12-19 with total page 65 pages. Available in PDF, EPUB and Kindle. Book excerpt: This updated version of Nuclear Energy Series NF-T-2.1 provides information on all aspects of fuel failures in current nuclear power plant operations.