CiNii 国立情報学研究所 学術情報ナビゲータ[サイニィ]
ID:9000303989208
みずほ情報総研株式会社 Mizuho Information & Research Institute (MHIR) (2014年 CiNii収録論文より)
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眞崎 浩一 , 小坂部 和也 , 勝山 仁哉 , 勝又 源七郎 , 鬼沢 邦雄
To assure the structural integrity of a reactor pressure vessel (RPV) is one of the most critical issues to maintain the safe long-term operation of a nuclear power plant. In Japan, the assessment met …
M&M材料力学カンファレンス 2014, "OS0809-1"-"OS0809-3", 2014-07-19
西川 弘之 , 眞崎 浩一 , 小坂部 和也 , 勝山 仁哉 , 鬼沢 邦雄
M&M材料力学カンファレンス 2013, "OS1410-1"-"OS1410-3", 2013-10-12
小坂部 和也 , 西川 弘之 , 眞崎 浩一 , 勝山 仁哉 , 鬼沢 邦雄
To assess the structural integrity of a reactor pressure vessel (RPV) during pressurized thermal shock (PTS) events quantitatively, several probabilistic fracture mechanics (PFM) codes have been devel …
M&M材料力学カンファレンス 2012, "OS0814-1"-"OS0814-3", 2012-09-22
眞崎 浩一 , 西川 弘之 , 小坂部 和也 , 勝山 仁哉 , 鬼沢 邦雄
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 …
M&M材料力学カンファレンス 2012, "OS0813-1"-"OS0813-3", 2012-09-22
小坂部 和也 , 鬼沢 邦雄 , 柴田 勝之 [他] , 鈴木 雅秀
Fifty-five nuclear power plants of light water reactors (LWRs) in Japan including seven plants which have already reached a 30-year operation have been operated as of September 2006. The probabilist …
日本原子力学会和文論文誌 = Transactions of the Atomic Energy Society of Japan 6(2), 172-182, 2007-06-25
J-STAGE 参考文献12件 被引用文献2件
As a part of the materials aging degradation and structural integrity research for LWR components, the probabilistic fracture mechanics (PFM) analysis code PASCAL has been developed in JAEA. This co …
日本原子力学会和文論文誌 = Transactions of the Atomic Energy Society of Japan 6(2), 161-171, 2007-06-25
J-STAGE 参考文献27件 被引用文献3件