書誌事項
- タイトル別名
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- OS0813 Technical Review of Structural Integrity Assessment Procedure on Reactor Pressure Vessel (1) : Comparison of Procedures in Japan and U.S. and Study on the Postulated Flaw
抄録
The structural integrity of a reactor pressure vessel (RPV) should be maintained to ensure the safe long-term operation of a nuclear power plant. The assessment methods for RPV integrity are provided for in the codes and standards. Authors have compared the assessment methods for RPV integrity under pressurized thermal shock in domestic and the United States. After reviewing the technical background of the structural integrity assessment method, we clarified the technical issues based on the latest knowledge in this field, and the differences of postulated crack treatments between domestic and the United States based on fracture mechanics analyses.
収録刊行物
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- M&M材料力学カンファレンス
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M&M材料力学カンファレンス 2012 (0), _OS0813-1_-_OS0813-3_, 2012
一般社団法人 日本機械学会
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キーワード
詳細情報 詳細情報について
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- CRID
- 1390001205872536704
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- NII論文ID
- 110009937358
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- ISSN
- 24242845
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- 本文言語コード
- ja
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- データソース種別
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- JaLC
- Crossref
- CiNii Articles
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- 抄録ライセンスフラグ
- 使用不可