著者

佐郷 ひろみ 町田 秀夫 和田 宏 加口 仁 田辺 宏暁

出版者

一般社団法人日本機械学会

雑誌

年次大会講演論文集 : JSME annual meeting

巻号頁・発行日

no.1, pp.383-384, 2001-08-22

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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.