Download or read book Current State of Research on Pressurized Water Reactor Safety written by Jean Couturier and published by . This book was released on 2021 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: For more than 40 years, IPSN then IRSN has conducted research and development on nuclear safety, specifically concerning pressurized water reactors, which are the reactor type used in France. This publication reports on the progress of this research and development in each area of study - loss-of-coolant accidents, core melt accidents, fires and external hazards, component aging, etc. -, the remaining uncertainties and, in some cases, new measures that should be developed to consolidate the safety of today's reactors and also those of tomorrow. A chapter of this report is also devoted to research into human and organizational factors, and the human and social sciences more generally. All of the work is reviewed in the light of the safety issues raised by feedback from major accidents such as Chernobyl and Fukushima Daiichi, as well as the issues raised by assessments conducted, for example, as part of the ten-year reviews of safety at French nuclear reactors. Finally, through the subjects it discusses, this report illustrates the many partnerships and exchanges forged by IRSN with public, industrial and academic bodies both within Europe and internationally. This publication reflects IRSN's desire to keep an enduring record of its results and to share its knowledge.

Download or read book Current State of Research on Pressurized Water Reactor Safety written by and published by . This book was released on 2018 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Reactor Safety Research Programs written by S. K. Edler and published by . This book was released on 1983 with total page 80 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Light Water Reactor Safety written by B. Pershagen and published by Elsevier. This book was released on 2013-10-22 with total page 480 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book describes the principles and practices of reactor safety as applied to the design, regulation and operation of light water reactors, combining a historical approach with an up-to-date account of the safety, technology and operating experience of both pressurized water reactors and boiling water reactors. The introductory chapters set out the basic facts upon which the safety of light water reactors depend. The central section is devoted to the methods and results of safety analysis. The accidents at Three Mile Island and Chernobyl are reviewed and their implications for light water reactor safety are discussed. The concluding chapters examine selected safety issues and their resolution, and highlight results of reactor safety research. The book is amply illustrated, with numerous cross references and a comprehensive index.

Download or read book Reactor Safety Research Program written by United States Nuclear Regulatory Commission Division of Reactor Safety Research and published by . This book was released on 1975 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Reactor Safety Research Programs written by S. K. Edler and published by . This book was released on 1981 with total page 92 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Safety Features of Operating Light Water Reactors of Western Design written by M. Gavrilas and published by CRC Press. This book was released on 2018-01-18 with total page 312 pages. Available in PDF, EPUB and Kindle. Book excerpt: This text arose from a study originally undertaken for the Department of Energy to characterize the principal safety features of light water reactors of western design. This text should be of use to professional engineers interested in safety assessment of operating light water reactors, students interested in the principal safety features of LWRs, and others interested in tracing the design evolution of light water reactors. However, while ambitious in its scope, this text should not be viewed as presenting the levels of reactor safety of the various families of western reactor designs.

Download or read book Pressurized Water Reactor Reference Nuclear Power Plant Safety Analysis Report SWESSAR P1 written by Patsy L. Hendricks and published by . This book was released on 1975 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Power Risks written by Henry Way Kendall and published by . This book was released on 1975 with total page 68 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Guidebook to Light Water Reactor Safety Analysis written by P. B. Abramson and published by CRC Press. This book was released on 1985-01-01 with total page 418 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Guidebook to Light Water Reactor Safety Analysis brings together government and expert researchers entrusted with maintaining the safety of reactors, preventing incidents, and for creating the guidelines for responding appropriately to emergency situations. It includes an overview presented by the U.S. Nuclear Regulatory Commission. One of the most relevant compendiums of its time, it's a volume of both historical and scientific significance and well worth the consideration of those currently involved with maintaining reactor safety..

Download or read book Pressurized Water Reactors written by Yurugi Kanzaki and published by Elsevier. This book was released on 2024-07-26 with total page 507 pages. Available in PDF, EPUB and Kindle. Book excerpt: Pressurized Water Reactors, Volume Three in the JSME Series on Thermal and Nuclear Power Generation, compiles the latest research on Pressurized Water Reactors (PWRs) into a very comprehensive reference, beginning with its history. The reader is then guided through optimum design processes for PWRs, considering safety throughout. The authors then discuss thermal-hydraulic aspects within the PWR system and inside the reactor core, making this a valuable resource for nuclear and thermal engineers and researchers. Combining their wealth of experience, the book presents in-depth knowledge on the advancement and improvement of fuel rods that is gleaned from decades of experience and lessons learned. The inclusion of analysis codes for the design and safety elements ensure makes this a unique reference which will provide the reader with a solid understanding which they can transfer to their own professional and research settings. Future prospects for next generation PWR and Small Modular Reactors are also discussed, giving the reader a basis for further research of their own. Contains contributions from 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 analysis codes, such as RELAP5, for the design and safety improvement of pressurized water reactors (PWRs) Presents history, examples, and case studies from Japan and other key regions, such as the United States and Europe

Download or read book Quarterly Technical Progress Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission s Division of Reactor Safety Research April June 1981 Prepared for the U S Nuclear Regulatory Commission and Department of Energy Idaho Operations Office Under DOE Contract No DE AC07 76IDO1570 written by S. K. Edler and published by . This book was released on 1981 with total page 92 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Safety written by Great Britain. Health and Safety Executive and published by . This book was released on 1982 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Light Water Reactor Safety Research Program written by Sandia National Laboratories and published by . This book was released on 1981-10 with total page 312 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Quarterly Technical Progress Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission s Division of Reactor Safety Research written by and published by . This book was released on 1980-10 with total page 48 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 1959 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Quarterly Technical Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission s Division of Reactor Safety Research April June 1975 written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The current water reactor safety activities of ANC are accomplished in four programs. The Semiscale Program consists of small-scale nonnuclear thermal- hydraulic experiments for the generation of experimental data that can be applied to analytical models describing loss-of-coolant accident (LOCA) phenomena in water-cooled nuclear power plants. Emphasis is placed on acquiring system effects data from integral tests that characterize the most significant thermal- hydraulic phenomena during the depressurization (blowdown) and emergency cooling phase of a LOCA. The LOFT Program provides test data to support: (a) assessment and improvement of the analytical methods utilized for predicting the behavior of pressurized water reactors (PWR) under LOCA conditions; (b) evaluation of the performance of PWR engineered safety features (ESF), particularly the emergency core cooling system (ECCS); and (c) assessment of the quantitative margins of safety inherent in the performance of these safety features. The Thermal Fuels Behavior Program is a program designed to provide information on the behavior of reactor fuels under normal, off-normal, and accident conditions. The experimental portion is concentrated on testing of single fuel rods and fuel rod clusters under power-cooling-mismatch (PCM), loss-of-coolant, and reactivity initiated accident conditions. The Reactor Behavior Program encompasses the analytical aspects of predicting the response of nuclear power reactors under normal, abnormal, and accident conditions. The status of each program is reported. (auth).