書誌事項
- タイトル別名
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- OS1420 Study on Fatigue Crack Growth Behavior for Ni-base Alloys in BWR Water Environment : 1^<st> report, Expressions in Paris Law Format
抄録
When the flaws are detected m nuclear components by in-service inspection, structural integrity assessment is one of the most important procedures to assume the safety and reliability of nuclear power plants. Fatigue crack growth analysis should be performed for the technical judgment on continuous operation based on the Rules on Fitness-for-Service for Nuclear Power Plants of the Japan Society of Mechanical Engineers Code (JSME FFS Code) when the cyclic loading would be assumed. However, fatigue crack growth analysis for BWR components consisted of Ni-base alloy is currently impossible since the fatigue crack growth rate curve for Ni-base alloy in BWR water environment is not prepared yet in the JSME FFS Code. In this study, fatigue crack growth tests in BWR water environment were performed for Ni-base alloy. And fatigue crack growth rate curve in Paris law format was evaluated. As a result, fatigue crack growth rate curve for weld metal and heat affected zone (HAZ) was formulated, respectively. And the values of ΔK_<th> for less than 1s of rise time were determined.
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 2013 (0), _OS1420-1_-_OS1420-3_, 2013
一般社団法人 日本機械学会
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詳細情報 詳細情報について
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- CRID
- 1390282680850414080
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- NII論文ID
- 110009936739
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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
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- 抄録ライセンスフラグ
- 使用不可