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" Understanding and mitigating ageing in nuclear power plants "
edited by Philip G. Tipping.
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BL
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| Record Number
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673718
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| Doc. No
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b502907
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| Title & Author
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Understanding and mitigating ageing in nuclear power plants : materials and operational aspects of plant life management (PLiM) /\ edited by Philip G. Tipping.
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| Publication Statement
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Oxford ;Philadelphia :: Woodhead Publishing,, c2010.
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| Series Statement
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Woodhead publishing series in energy ;; 4.
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| Page. NO
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1 online resource (xxxvii, 914 p.) :: ill.
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| ISBN
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1845695119
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9781845695118
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| Bibliographies/Indexes
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Includes bibliographical references and index.
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| Contents
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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.
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| Subject
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Nuclear reactors-- Safety measures.
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| Dewey Classification
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621.4835
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| LC Classification
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TK9152.U52 2010eb
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| Added Entry
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Tipping, Philip G.
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Knovel (Firm)
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