Status of Usa Neuclear Reactor Pressure Vessel Surveillance for Radiation Effects PDF Download

Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 287

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Author: Lendell E. Steele
Publisher: ASTM International
ISBN: 9780803100664
Category : Freshwater microbiology
Languages : en
Pages : 269

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Book Description

Author: K. G. Hoge
Publisher:
ISBN:
Category : Nuclear pressure vessels
Languages : en
Pages : 132

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Book Description

Author: Lendell E. Steele
Publisher: ASTM International
ISBN: 9780803102293
Category : Technology & Engineering
Languages : en
Pages : 290

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Book Description

Author: Philip G Tipping
Publisher: Elsevier
ISBN: 1845699955
Category : Technology & Engineering
Languages : en
Pages : 953

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Book Description
Plant life management (PLiM) is a methodology focussed on the safety-first management of nuclear power plants over their entire lifetime. It incorporates and builds upon the usual periodic safety reviews and licence 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 plants critically 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 characterise and analyse the ageing of materials and to mitigate or eliminate ageing degradation effects. Part three reviews analysis, monitoring and modelling 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 IV 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 plants is a standard reference for all nuclear plant designers, operators, and nuclear safety and materials professionals and researchers. - Introduces the reader to the role of nuclear power in the global energy mix - Reviews the fundamental ageing-degradation mechanisms of materials used in nuclear power plant structures, systems and components (SSC) - Examines topics including elimination of ageing effects, plant design, and the application of plant life management (PLiM) practices in a range of commercial nuclear reactor types

Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 120

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Book Description
The master curve approach for assessing the fracture toughness of a sampled irradiated material has been gaining acceptance throughout the world. This direct measurement approach is preferred over the correlative and indirect methods used in the past to assess irradiated reactor pressure vessel (RPV) integrity. The master curve methodology already has been or is being assimilated into the ASME Boiler and Pressure Vessel Code, ASTM standards, USNRC regulations, German regulations (KTA 3203), IAEA PTS guidelines for WWER reactors as well as the VERLIFE "Unified Procedure for WWER Component Lifetime Assessment" and other industry guidance documents governing RPV integrity analysis. As this report was prepared using the results of many research projects and experiments, these guidelines for application will be used for a long time to evaluate and assess the residual life of RPVs.

Author: Samuel Apikyan
Publisher: Springer
ISBN: 9048135044
Category : Technology & Engineering
Languages : en
Pages : 300

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Book Description
The basic logic is very simple. Countries around the globe have a need for more electrical generating capacity because of increases in population and increases in energy use per capita. The needs are constrained by the requirement that the ba- load energy source be economical, secure, and not emit climate-changing gases. Nuclear power fits this description. Therefore, many countries that have not had a nuclear power program (or only had a small program) see a need to develop one in the future. However, the development of a national nuclear energy program is not so simple. The purpose of the NATO Advanced Research Workshop on Nuclear Power and Energy Security was to contribute to our understanding of how these programs might evolve. The workshop took place 26–29 May 2009 in Yerevan, Armenia. Approximately 50 participants discussed the infrastructure that is needed and some of the reactor options that might be considered. The papers in this book helped define the discussion that took place. The infrastructure that is needed includes a legal framework, a functioning regulator, a plan for waste disposal, a plan for emergency response, etc. These needs were explained and just as importantly, it was explained what international, bilateral, and regional cooperation is available. Although there were many co- tries represented, the Armenian experience was of particular interest because of where the meeting was located. The papers on reactor options covered both innovative and evolutionary designs.

Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 782

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Author: Naoki Soneda
Publisher: Elsevier
ISBN: 0857096478
Category : Technology & Engineering
Languages : en
Pages : 437

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Book Description
Reactor Pressure Vessels (RPVs) contain the fuel and therefore the reaction at the heart of nuclear power plants. They are a life-determining structural component: if they suffer serious damage, the continued operation of the plant is in jeopardy. This book critically reviews irradiation embrittlement, the main degradation mechanism affecting RPV steels, and mitigation routes for managing the RPV lifetime. Part I reviews RPV design and fabrication in different countries, with an emphasis on the materials required, their important properties, and manufacturing technologies. Part II then considers RVP embrittlement in operational nuclear power plants using different reactors. Chapters are devoted to embrittlement in light-water reactors, including WWER-type reactors and Magnox reactors. Finally, Part III presents techniques for studying embrittlement, including irradiation simulation techniques, microstructural characterisation techniques, and probabilistic fracture mechanics. Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants provides a thorough review of an issue that is central to the safety of nuclear power generation. The book includes contributions from an international team of experts, and will be a useful resource for nuclear plant operators and managers, relevant regulatory and safety bodies, nuclear metallurgists and other academics in this field - Discusses reactor pressure vessel (RPV) design and the effect irradiation embrittlement can have, the main degradation mechanism affecting RPVs - Examines embrittlement processes in RPVs in different reactor types, as well as techniques for studying RPV embrittlement

Author: Martin L. Grossbeck
Publisher: ASTM International
ISBN: 0803134770
Category : Materials
Languages : en
Pages : 767

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