書誌事項
- タイトル別名
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- K-0802 Development of Structural Integrity Oriented Reliability Assessment System (SORE) For FBR MONJU (2) : Reactor Vessel
抄録
A part of the SORE system was developed for Reactor Vessel. SORE is prototype system that calculates stress history and creep-fatigue damage for main component of MONJU using plant data In this study, the calculating method of stress and temperature using plant data and the procedure of fatigue damage and creep damage evaluation using calculated history of temperature and stress was investigated.
収録刊行物
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- 年次大会講演論文集
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年次大会講演論文集 I.01.1 (0), 383-384, 2001
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
- 1390282681044856448
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- NII論文ID
- 110002526399
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- ISSN
- 24331325
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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