Kazuya OSAKABE
著者に関連した記事は4件です。
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第12回
原子炉圧力容器の健全性評価手法の高度化について
著者:
宇野 隼平,Shumpei UNO,勝山 仁哉,Jinya KATSUYAMA,勝又 源七郎,Genshichiro KATSUMATA,眞崎 浩一,Koichi MASAKI,小坂部 和也,Kazuya OSAKABE,李 銀生,Yinsheng LI
発刊日:
公開日:
キーワードタグ:
Fracture Probability Fracture Toughness Irradiation Embrittlement Pressurized Thermal Shock Probabilistic Fracture Mechanics Reactor Pressure Vessel Structural Integrity
宇野 隼平,Shumpei UNO,勝山 仁哉,Jinya KATSUYAMA,勝又 源七郎,Genshichiro KATSUMATA,眞崎 浩一,Koichi MASAKI,小坂部 和也,Kazuya OSAKABE,李 銀生,Yinsheng LI
発刊日:
公開日:
キーワードタグ:
Fracture Probability Fracture Toughness Irradiation Embrittlement Pressurized Thermal Shock Probabilistic Fracture Mechanics Reactor Pressure Vessel Structural Integrity
Assuring 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. Authors have been conducting extensive research on the improvement of structural integrity assessment methods of RPVs. In this paper, we describe some research results obtained from the recent activity including the review on the technical background of the methods and study on probabilistic methods for the applicability to the cu...
英字タイトル:
Study on Structural Integrity Assessment of Reactor Pressure Vessels
英字タイトル:
Study on Structural Integrity Assessment of Reactor Pressure Vessels
第3回
非破壊検査を考慮した原子炉容器の確率論的構造健全性評価手法の開発
著者:
小坂部 和也,Kazuya OSAKABE,鬼沢 邦雄一,Kunio ONIZAWA,柴田 勝之,Katsuyuki SHIBATA
発刊日:
公開日:
キーワードタグ:
Fracture Toughness Irradiation Embrittlement Non-Destructive Examination Pressurized Thermal Shock Probabilistic Fracture Mechanics Reactor Pressure Vessel
小坂部 和也,Kazuya OSAKABE,鬼沢 邦雄一,Kunio ONIZAWA,柴田 勝之,Katsuyuki SHIBATA
発刊日:
公開日:
キーワードタグ:
Fracture Toughness Irradiation Embrittlement Non-Destructive Examination Pressurized Thermal Shock Probabilistic Fracture Mechanics Reactor Pressure Vessel
As a part of the aging structural integrity research for LWR components, the probabilistic fracture mechanics (PFM) analysis code PASCAL has been developed in JAEA. This code evaluates the conditional probabilities of crack initiation and fracture of a reactor pressure vessel (RPV) under transient conditions such as pressurized thermal shock (PTS). A case study on the effect of non-destructive examination performance was performed using PASCAL. The analysis results showed that one non-destr uctive examinat...
英字タイトル:
Development of Probabilistic Fracture Mechanics Analysis Code PASCAL For Reactor Pressure Vessel Considering Non-Destructive Examination
英字タイトル:
Development of Probabilistic Fracture Mechanics Analysis Code PASCAL For Reactor Pressure Vessel Considering Non-Destructive Examination
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