http://www.loc.gov/mods/v3 http://www.loc.gov/standards/mods/v3/mods-3-2.xsd
Understanding and mitigating ageing in nuclear power plants
materials and operational aspects of plant life management (PLiM)
1 online resource (xxxvii, 914 pages) : illustrations.
Annotation Plant life management PLiM is a methodology focused on the safety-first management of nuclear power plants over their entire lifetime. It incorporates and builds upon the usual periodic safety reviews and license renewals as part of an overall framework designed to assist plant operators and regulators in assessing the operating conditions of a nuclear power plant, and establishing the technical and economic requirements for safe, long-term operation. Understanding and Mitigating Ageing in Nuclear Power Plantscritically reviews the fundamental ageing-degradation mechanisms of materials used in nuclear power plant structures, systems and components SSC, along with their relevant analysis and mitigation paths, as well as reactor-type specific PLiM practices. Obsolescence and other less obvious ageing-related aspects in nuclear power plant operation are also examined in depth. Part one introduces the reader to the role of nuclear power in the global energy mix, and the importance and relevance of plant life management for the safety regulation and economics of nuclear power plants. Key ageing degradation mechanisms and their effects in nuclear power plant systems, structures and components are reviewed in Part two, along with routes taken to characterize and analyze the ageing of materials and to mitigate or eliminate ageing degradation effects. Part three reviews analysis, monitoring and modeling techniques applicable to the study of nuclear power plant materials, as well as the application of advanced systems, structures and components in nuclear power plants. Finally, Part four reviews the particular ageing degradation issues, plant designs, and application of plant life management PLiM practices in a range of commercial nuclear reactor types. With its distinguished international team of contributors, Understanding and Mitigating Ageing in Nuclear Power Plantswill be a standard reference for all nuclear plant designers, operators, and nuclear safety and materials professionals and researchers --
Note continued: 17.7. Application of research and operational experience to the practical solution of problems (relation to plant life management, PLiM) -- 17.8. Conclusions -- 17.9. References -- pt. IV Plant life management (PLiM) practices in nuclear power plants -- 18. Plant life management (PLiM) practices for pressurized light water nuclear reactors (PWR) / Ph. G. Tipping -- 18.1. Introduction -- 18.2. Ageing-related terminology and descriptions of major pressurized water reactor (PWR) components -- 18.3. Overview of fuel and control of core power in pressurized water reactors (PWR) -- 18.4. Discussion -- 18.5. Conclusions -- 18.6. Sources of further information -- 18.7. References -- 19. Plant life management (PLiM) practices for water-cooled water-moderated nuclear reactors (WWER) / T.J. Katona -- 19.1. Introduction -- 19.2. Description of water-cooled water-moderated nuclear reactors (WWERs) -- 19.3. Plant life management (PLiM) policy of water-cooled water-moderated nuclear reactor (WWER) operators -- 19.4. Mechanical components relevant for safe long-term operation -- 19.5. Structures and structural components relevant for safe long-term operation -- 19.6. Electrical, instrumentation and control equipment relevant for safe long-term operation -- 19.7. Regulatory requirements for continued operation -- 19.8. Integration of plant life management (PLiM) programmes for water-cooled water-moderated nuclear reactor (WWERs) -- 19.9. Feedback of operational experience -- 19.10. Research needs in area of ageing of water-cooled water-moderated nuclear reactor (WWER) components -- 19.11. Role of international organizations and programmes -- 19.12. Future trends -- 19.13. Sources of further information -- 19.14. References -- 20. Plant life management (PLiM) practices for boiling water nuclear reactors (BWR): Japanese experience / N. Yamashita -- 20.1. Introduction -- 20.2. Features and types of boiling water reactors -- boiling water reactor (BWR) and advanced boiling water reactor (ABWR) -- 20.3. Major ageing mechanisms significant for boiling water reactor (BWR) systems, structures and components (SSCs) -- 20.4. Ageing management practices against major significant ageing mechanisms -- 20.5. Major component replacement/refurbishment programmes -- 20.6. Technical subjects to be facilitated for ageing management -- 20.7. Current direction for more effective and systematic ageing management programmes -- 20.8. Knowledge management and research and development (R & D) -- 20.9. References -- 20.10. Abbreviations -- 21. Plant life management (PLiM) practices for pressurised heavy water nuclear reactors (PHWR) / D.K. Jain -- 21.1. Introduction -- 21.2. Pressurised heavy water reactor (PHWR)/Canadian Deuterium Uranium (CANDU) -- 21.3. Critical components of Indian pressurised heavy water reactor (PHWR) -- 21.4. Reactor ageing issues: pressure tube, end shields and calandria tube -- 21.5. Reactor ageing issues: reactivity mechanisms and fuel handling systems -- 21.6. Reactor ageing issues: feeders, secondary side piping, steam generators and heat exchangers -- 21.7. Reactor ageing issues: civil structures, cables and sea water systems -- 21.8. Regulatory issues associated with plant life management (PLiM) -- 21.9. Application of research and operational experience to find the practical solution to problems -- 21.10. Future trends -- 21.11. Acknowledgements -- 21.12. References -- 22. Plant life management (PLiM) practices for sodium cooled fast neutron spectrum nuclear reactors (SFRs) / K. Bhanu Sankara Rao -- 22.1. Introduction -- 22.2. Sodium cooled fast neutron spectrum reactors (SFRs) -- 22.3. Design approach -- 22.4. Safety and regulatory perspective -- 22.5. In-service inspection (ISI) and robotics in life assessment based on research and development (R & D) and applications -- 22.6. Life extension aspects of international sodium cooled fast neutron spectrum reactors (SFRs) -- 22.7. Future trends -- 22.8. Conclusion -- 22.9. Acknowledgements -- 22.10. References -- 23. Plant life management (PLiM) practices for gas-cooled, graphite-moderated nuclear reactors: UK experience / G.B. Neighbour -- 23.1. Introduction -- 23.2. UK gas-cooled reactor types (Magnox and advanced gas-cooled reactor (AGR)) -- 23.3. Nuclear graphite -- 23.4. Effects of reactor environment on the graphite moderator -- 23.5. The UK nuclear regulatory regime -- 23.6. Maintaining the safety of graphite moderator cores -- 23.7. Regulatory requirements for continued operation -- 23.8. Future trends -- 23.9. Sources of further information -- 23.10. Useful websites -- 23.11. References -- 24. Outlook for nuclear power plant life management (PLiM) practices -- summary, conclusions, recommendations / Ph. G. Tipping -- 24.1. Introduction -- 24.2. Further elements to consider for nuclear power plant ageing and plant life management (PLiM-AM) -- 24.3. Discussion -- 24.4. Current and projected requirements of the nuclear power industry -- 24.5. List of topical issues of current and future relevance to nuclear power plants (NPPs) -- 24.6. Conclusions -- 24.7. References.
Plný text je dostupný pouze z IP adres počítačů Univerzity Tomáše Bati ve Zlíně nebo vzdáleným přístupem pro zaměstnance a studenty
Includes bibliographical references and index.
Oxford ; Philadelphia : Woodhead Publishing, ©2010