Download or read book Fast Reactor Safety written by John Graham and published by Elsevier. This book was released on 2012-12-02 with total page 390 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fast Reactor Safety deals with safety design criteria and methodology for fast reactors. Topics covered include safety evaluation methods, system disturbances, containment, and licensing. The characteristics of fast reactors, including heat ratings and coolants, are also discussed. Comprised of six chapters, this book opens with an overview of methods used to evaluate nuclear safety, along with neutron kinetics, thermal and feedback effects, and fault tree analysis. The reader is then introduced to possible system disturbances in relation to three distinct fast reactor systems: liquid-metal-cooled fast breeder reactors, gas-cooled fast breeder reactors, and steam-cooled fast breeder reactors. The next chapter looks at safety criteria that are set to define the design of a safe plant, together with the safety features that might be included. The remaining chapters focus on the particular problems of a sodium-cooled design; containment building and primary circuit and vessel containment; and licensing of the plant. This monograph is intended for graduates and undergraduates in nuclear engineering who are attending courses in reactor safety.
Download or read book Proceedings of the 1990 International Fast Reactor Safety Meeting written by and published by . This book was released on 1990 with total page 544 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Reactor Safety written by F Farmer and published by Elsevier. This book was released on 2012-12-02 with total page 231 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear Reactor Safety aims to put the nuclear hazard in perspective by providing an objective overall technical review of the field. It focuses on reactor accidents and their consequences. The technical arguments will be concerned broadly with reactor accident conditions and will deal with both the arrangements necessary to prevent any dangerous diversion from normal operation and to ameliorate the consequences if such a diversion should occur. The book is organized into three parts. Part I describes the nature of fission products and the hazards to man and his environment resulting from the uncontrolled release of fission products in accident conditions. Part II discusses a quantitative approach to reactor safety assessment and the quantification of vessel integrity. Part III deals with the basic principles of analysis and assessment of reactor safety, and then considers the specific safety problems of thermal and fast reactors in detail. This book is intended for two types of readers. First are technicians, those engaged in nuclear engineering: designers, constructors, and operators of nuclear stations, as well as those who would make a career in nuclear safety. Second are those (not necessarily scientists) who are tasked with making decisions in the field of energy use and allocation, or are concerned with environmental matters.
Download or read book Proceedings of the International Meeting on Fast Reactor Safety Technology Seattle Washington August 1923 1979 written by and published by . This book was released on 1979 with total page 634 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Safety written by and published by . This book was released on 1971 with total page 80 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Proceedings of the 1990 International Fast Reactor Safety Meeting written by International Fast Reactor Safety Meeting. 1990, Snowbird, Utah and published by . This book was released on 1990 with total page 543 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Safety written by and published by . This book was released on 1965-03 with total page 96 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Proceedings of the International Meeting on Fast Reactor Safety and Related Physics October 5 8 1976 Chicago Illinois Invited papers panels summary written by and published by . This book was released on 1977 with total page 402 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Fast Reactor Fuel Type and Reactor Safety Performance written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Fast Reactor Fuel Type and Reactor Safety Performance R. Wigeland, Idaho National Laboratory J. Cahalan, Argonne National Laboratory The sodium-cooled fast neutron reactor is currently being evaluated for the efficient transmutation of the highly-hazardous, long-lived, transuranic elements that are present in spent nuclear fuel. One of the fundamental choices that will be made is the selection of the fuel type for the fast reactor, whether oxide, metal, carbide, nitride, etc. It is likely that a decision on the fuel type will need to be made before many of the related technologies and facilities can be selected, from fuel fabrication to spent fuel reprocessing. A decision on fuel type should consider all impacts on the fast reactor system, including safety. Past work has demonstrated that the choice of fuel type may have a significant impact on the severity of consequences arising from accidents, especially for severe accidents of low probability. In this paper, the response of sodium-cooled fast reactors is discussed for both oxide and metal fuel types, highlighting the similarities and differences in reactor response and accident consequences. Any fast reactor facility must be designed to be able to successfully prevent, mitigate, or accommodate all consequences of potential events, including accidents. This is typically accomplished by using multiple barriers to the release of radiation, including the cladding on the fuel, the intact primary cooling system, and most visibly the reactor containment building. More recently, this has also included the use of 'inherent safety' concepts to reduce or eliminate the potential for serious damage in some cases. Past experience with oxide and metal fuel has demonstrated that both fuel types are suitable for use as fuel in a sodium-cooled fast reactor. However, safety analyses for these two fuel types have also shown that there can be substantial differences in accident consequences due to the neutronic and thermophysical properties of the fuel and their compatibility with the reactor coolant, with corresponding differences in the challenges presented to the reactor developers. Accident phenomena are discussed for the sodium-cooled fast reactor based on the mechanistic progression of conditions from accident initiation to accident termination, whether a benign state is achieved or more severe consequences are expected. General principles connecting accident phenomena and fuel properties are developed from the oxide and metal fuel safety analyses, providing guidelines that can be used as part of the evaluation for selection of fuel type for the sodium-cooled fast reactor.
Download or read book Molten Salt Reactors and Thorium Energy written by Thomas James Dolan and published by Elsevier. This book was released on 2024-01-25 with total page 1068 pages. Available in PDF, EPUB and Kindle. Book excerpt: Molten Salt Reactors and Thorium Energy, Second Edition is a fully updated comprehensive reference on the latest advances in MSR research and technology. Building on the successful first edition, Tom Dolan and the team of experts have fully updated the content to reflect the impressive advances from the last 5 years, ensuring this book continues to be the go-to reference on the topic. This new edition covers progress made in MSR design, details innovative experiments, and includes molten salt data, corrosion studies and deployment plans. The successful case studies section of the first edition have been removed, expanded, and fully updated, and are now published in a companion title called Global Case Studies on Molten Salt Reactors. Readers will gain a deep understanding of the advantages and challenges of MSR development and thorium fuel use, as well as step-by-step guidance on the latest in MSR reactor design. Each chapter provides a clear introduction, covers technical issues and includes examples and conclusions, while promoting the sustainability benefits throughout. - A fully updated comprehensive handbook on Molten Salt Reactors and Thorium Energy, written by a team of global experts - Covers MSR applications, technical issues, reactor types and reactor designs - Includes 3 brand new chapters which reflect the latest advances in research and technology since the first edition published - Presents case studies on molten salt reactors which aid in the transition to net zero by providing abundant clean, safe energy to complement wind and solar powe
Download or read book Fast Reactor Core Test Facility Safety Analysis Report written by Los Alamos Scientific Laboratory. K Division and published by . This book was released on 1962 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Power Reactor Safety written by Elmer Eugene Lewis and published by John Wiley & Sons. This book was released on 1977 with total page 664 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Fast Reactor Safety written by American Nuclear Society. Nuclear Reactor Safety Division and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
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.
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 Summary of APDA Fast Reactor Safety Studies written by W. H. Jens and published by . This book was released on 1956 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Proceedings of the International Topical Meeting on Fast Reactor Safety written by and published by . This book was released on 1985 with total page 560 pages. Available in PDF, EPUB and Kindle. Book excerpt:
