Understanding and mitigating ageing in nuclear power plants materials and operational aspects of plant life management (PLiM)

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Bibliographic Details
Other Authors Tipping, Philip G.
Format Electronic eBook
LanguageEnglish
Published Oxford ; Philadelphia : Woodhead Publishing, c2010.
SeriesWoodhead Publishing in energy ; no. 4.
Subjects
Nuclear reactors > Safety measures.
elektronické knihy
electronic books
Online AccessFull text
ISBN9781845699956
9781845695118
Physical Description1 online zdroj (xxxvii, 914 p.) : ill.

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Table of Contents:
  • 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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