Tetsuya NAKAGAWA
著者に関連した記事は2件です。
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第11回
BWR環境におけるステンレス鋳鋼の熱時効評価
著者:
田中 重彰,Shigeaki TANAKA,平本 真紀,Maki HIRAMOTO,西山 俊明,Toshiaki NISHIYAMA,中川 純二,Junji NAKAGAWA,塩田 翔,Sho SHIODA,宮田 肇,Hajime MIYATA,豊田 哲也,Tetsuya TOYOTA,杉山 正成,Masanari SUGIYAMA
発刊日:
公開日:
キーワードタグ:
Charpy impact test fracture toughness impact value model equation PLM thermal aging
田中 重彰,Shigeaki TANAKA,平本 真紀,Maki HIRAMOTO,西山 俊明,Toshiaki NISHIYAMA,中川 純二,Junji NAKAGAWA,塩田 翔,Sho SHIODA,宮田 肇,Hajime MIYATA,豊田 哲也,Tetsuya TOYOTA,杉山 正成,Masanari SUGIYAMA
発刊日:
公開日:
キーワードタグ:
Charpy impact test fracture toughness impact value model equation PLM thermal aging
Effect of thermal aging under BWR condition on material properties of casting s tainless steel were evaluated by such as Charpy impact test, using replaced BWR omponent material. Solution heat treatment was performed to the same material d the material properties were obtained. Comparing each material test results , impact value of thermal aging material was lower than solution heat treatment material. By the results, thermal aging effect on material properties under BW condition was confirmed. The materi...
英字タイトル:
Thermal Aging Evaluation of Casting Stainless Steel under BWR Environment
英字タイトル:
Thermal Aging Evaluation of Casting Stainless Steel under BWR Environment
第5回
中性子照射によって延性が著しく低下する場合の延性破壊条件と構造健全性確保の概念
著者:
實川 資朗,Shiro JITSUKAWA,鈴木 一彦,Kazuhiko SUZUKI,大久保 成彰,Nariaki OKUBO,芝 清之,Kiyoyuki SHIBA,高田 文樹,Fumiki TAKADA,近江 正男,Masao OHMI,中川 哲也,Tetsuya NAKAGAWA
発刊日:
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Austenitic steel Ductility loss Ferritic steel Neutron irradiation Structural integrity
實川 資朗,Shiro JITSUKAWA,鈴木 一彦,Kazuhiko SUZUKI,大久保 成彰,Nariaki OKUBO,芝 清之,Kiyoyuki SHIBA,高田 文樹,Fumiki TAKADA,近江 正男,Masao OHMI,中川 哲也,Tetsuya NAKAGAWA
発刊日:
公開日:
キーワードタグ:
Austenitic steel Ductility loss Ferritic steel Neutron irradiation Structural integrity
Results of irradiation experiment on the degradation of ductility of 8-9Cr reduced activation ferritic/martensitic steels are introduced, including those of irradiated austenitic steels. M acroscopic models of post irradiation tensile and fatigue properties obtained from the results are shown. Concept of the models should be essential for future design criteria development....
英字タイトル:
Ductility loss of materials by neutron irradiation and structural integrity of reactor core
英字タイトル:
Ductility loss of materials by neutron irradiation and structural integrity of reactor core