Aging and life extension of major light water reactor components
著者
書誌事項
Aging and life extension of major light water reactor components
Elsevier, 1993
大学図書館所蔵 全3件
  青森
  岩手
  宮城
  秋田
  山形
  福島
  茨城
  栃木
  群馬
  埼玉
  千葉
  東京
  神奈川
  新潟
  富山
  石川
  福井
  山梨
  長野
  岐阜
  静岡
  愛知
  三重
  滋賀
  京都
  大阪
  兵庫
  奈良
  和歌山
  鳥取
  島根
  岡山
  広島
  山口
  徳島
  香川
  愛媛
  高知
  福岡
  佐賀
  長崎
  熊本
  大分
  宮崎
  鹿児島
  沖縄
  韓国
  中国
  タイ
  イギリス
  ドイツ
  スイス
  フランス
  ベルギー
  オランダ
  スウェーデン
  ノルウェー
  アメリカ
注記
Includes bibliographical references and index
内容説明・目次
内容説明
In a comprehensive and lucid manner this book presents an understanding of the aging degradation of the major pressurized and boiling water reactor structures and components. The design and fabrication of each structure or component is briefly described followed by information on the associated stressors. Interactions between the design, materials, and various stressors that cause aging degradation are reviewed. In many cases, aging degradation problems have occurred, and the plant experience to date is analysed. The discussions summarize the available aging-related information and are supported with extensive references, including references to U.S. Nuclear Regulatory Commission (USNRC) documents, Electric Power Research Institute reports, U.S. and international conference proceedings and other publications. The book will prove a useful reference for engineers engaged in the operation and life extension of the present generation of nuclear power plants and for those engaged in the design of advanced light water reactors. It will also provide engineering students with insight into the practical materials-related issues associated with the design and operation of nuclear power plants. The work will also serve as a basis for programs to address the new aging-related issues likely to arise as plants get older.
目次
- (Selected) Pressurized Water Reactor Pressure Vessels. Design materials. Stressors. Degradation sites. Degradation mechanisms - radiation embrittlement - fatigue. Potential failure modes. Mitigation of embrittlement damage - reduction of thermal stresses - flux reductions - thermal annealing. Inservice inspection, surveillance and repair - inservice inspection methods - flaw distribution measurements - surveillance programs - estimating the mechanical properties of irradiated materials - weld repair. Summary, conclusions and recommendations. Pressurized Water Reactor Coolant Piping. Design and materials - geometry - materials and fabrication. Stressors
- - steady-state stress - transient stresses. Degradation sites. Degradation mechanisms - fatigue - thermal embrittlement - stress corrosion cracking - corrosion - erosion and cavitation - creep. Potential failure modes. Inservice inspections - inservice inspection requirements - material considerations - inservice inspection reliability. Summary, conclusions and recommendations. Counter Measures For Tube Failures In Pressurized Water Reactor Steam Generators. Steam generator tube degradation - recirculating type steam generators - once-through steam generators. Mitigation techniques - secondary-side chemical impurity control - chemical additives that inhibit corrosion - steam generator secondary-side cleaning - shot peening and rotopeening the tubing - stress relieving the U-bends - reducing the hot-leg-side temperature repair - flaw-acceptance criteria for tube integrity - plugging - sleeving - nickel plating. Replacement of steam generators. Summary, conclusions and recommendations. Boiling Water Reactor Pressure Vessels. Design and materials. Stressors. Degradation sites. Degradation mechanisms - fatigue - intergranular stress corrosion cracking - radiation embrittlement - stress corrosion cracking. Potential failure modes. Inservice inspection, surveillance, monitoring, and repair - inservice inspection - surveillance - on-line monitoring - field repair. Summary, conclusions, and recommendations. Boiling Water Reactor Vessel Internals. Design and materials - incore instrument housings - core shroud and core plate - Shroud baffle plate - fuel supports - jet pump assemblies - top guide - core spray lines and spargers - shroud head - feedwater spargers - steam separator and dryer assemblies - materials. Stressors. Degradation sites. Degradation mechanisms - intergranular stress corrosion cracking (IGSCC) - irradiation-assisted stress corrosion cracking (IASCC) - fatigue - thermal embrittlement - radiation embrittlement. Potential failure modes. Inservice inspection, monitoring, and repair. Summary, conclusions, and recommendations.
「Nielsen BookData」 より