Hiroyuki NISHIKAWA
著者に関連した記事は2件です。
更新情報
第9回
高経年化技術評価の高度化 一原子炉圧力容器の健全性評価一
著者:
鬼沢 邦雄,Kunio ONIZAWA,真﨑 浩一,Koichi MASAKI,小坂部 和也,Kazuya OSAKABE,西川 弘之,Hiroyuki NISHIKAWA,勝山 仁哉,Jinya KATSUYAMA,西山 裕孝,Yutaka NISHIYAMA
発刊日:
公開日:
キーワードタグ:
Fracture Probability Fracture Toughness Irradiation Embrittlement Postulated Crack Pressurized Thermal Shock Probabilistic Fracture Mechanics Reactor Pressure Vessel Structural Integrity
鬼沢 邦雄,Kunio ONIZAWA,真﨑 浩一,Koichi MASAKI,小坂部 和也,Kazuya OSAKABE,西川 弘之,Hiroyuki NISHIKAWA,勝山 仁哉,Jinya KATSUYAMA,西山 裕孝,Yutaka NISHIYAMA
発刊日:
公開日:
キーワードタグ:
Fracture Probability Fracture Toughness Irradiation Embrittlement Postulated Crack Pressurized Thermal Shock Probabilistic Fracture Mechanics Reactor Pressure Vessel Structural Integrity
Abstract To assure the structural integrity of a reactor pressure vessel (RPV) is known as one of the critical issues to maintain the safe long-term operation of a nuclear power plant. In Japan, the assessment meth ods for RPV integrity, stipulated in the codes and standards, have been endorsed by the regulatory body. Authors have initiated extensive research on the improvement of structural integrity assessment methods of RP Vs. In this paper, we describe some research results obtained from the first-year...
英字タイトル:
Study of System Safety Evaluation on LTO of National ProjectStructural Integrity Assessment of Reactor Pressure Vessels
英字タイトル:
Study of System Safety Evaluation on LTO of National ProjectStructural Integrity Assessment of Reactor Pressure Vessels
第10回
高経年化技術評価の高度化 －原子炉圧力容器の健全性評価
著者:
勝又 源七郎,Genshichiro KATSUMATA,眞崎 浩一,Koichi MASAKI,小坂部 和也,Kazuya OSAKABE,西川 弘之,Hiroyuki NISHIKAWA,勝山 仁哉,Jinya KATSUYAMA,西山 裕孝,Yutaka NISHIYAMA,鬼沢 邦雄,Kunio ONIZAWA
発刊日:
公開日:
キーワードタグ:
Fracture Probability Fracture Toughness Irradiation Embrittlement Postulated Crack Pressurized Thermal Shock Probabilistic Fracture Mechanics Reactor Pressure Vessel Structural Integrity
勝又 源七郎,Genshichiro KATSUMATA,眞崎 浩一,Koichi MASAKI,小坂部 和也,Kazuya OSAKABE,西川 弘之,Hiroyuki NISHIKAWA,勝山 仁哉,Jinya KATSUYAMA,西山 裕孝,Yutaka NISHIYAMA,鬼沢 邦雄,Kunio ONIZAWA
発刊日:
公開日:
キーワードタグ:
Fracture Probability Fracture Toughness Irradiation Embrittlement Postulated Crack Pressurized Thermal Shock Probabilistic Fracture Mechanics Reactor Pressure Vessel Structural Integrity
To assure the structural integrity of a reactor pressure vessel (RPV) is known as one of the critical issu es to maintain the safe long-term operation of a nuclear power plant. In Japan, the assessment methods for RPV integrity, stipulated in the codes and standards, have been endorsed by the regulatory body. Authors h ave initiated extensive research on the improvement of structural integrity assessment methods of RPVs. I this paper, we describe some research results obtained from the second-year activity...
英字タイトル:
Study of System Safety Evaluation on LTO of National Project Structural Integrity Assessment of Reactor Pressure Vessels
英字タイトル:
Study of System Safety Evaluation on LTO of National Project Structural Integrity Assessment of Reactor Pressure Vessels