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:
公開日:
キーワードタグ:
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
第11回
東海再処理施設における分析設備の保守
著者:
鈴木 久規,Hisanori SUZUKI,永山 哲也,Tetsuya NAGAYAMA,堀籠 和志,Kazushi HORIGOME,石橋 篤,Atsushi ISHIBASHI,北尾 貴彦,Tahiko KITAO,駿河谷 直樹,Naoki SURUGAYA
発刊日:
公開日:
キーワードタグ:
The Tokai Reprocessing Plant (TRP) is developing the technology to recover uranium and plutonium from spent nuclear fuel. There is an analytical laboratory which was built in 1977, as one of the most important facilities for process and material control analyses at the TRP. Samples taken from each process are a nalyzed by various analytical methods using hot cells, glove boxes and hume-hoods. A large number of maintenance work have been so far carried out and diffe rent types of experience have been accum...
英字タイトル:
Maintenance experiences at analytical laboratory at the Tokai Reprocessing Plant
第3回
軽水炉圧力容器鋼溶接部の照射脆化評価技術
著者:
熊野 秀樹,Hideki YUYA,鈴木 哲也,Tetsuya SUZUKI,肥田 茂,Shigeru HIDA,木村 晃彦,Akihiko KIMURA
発刊日:
公開日:
キーワードタグ:
The ductile-brittle transition behavior of neutron-irradiated welded A533B Cl.1 steel has been studied by means of small specimen test technique for discussing the specime n size effects on the impact properties. Standard size, one-third size and 1.5mm size Charpy V-notch specimens were prepared. Neutron irradiation was performed in JMTR wit h fluencies up to 0.75 and 1.3 X 1024 n/m°(E>1 MeV). Normalization of the USE is done by a curve fitting method and the USE of different size of specimens can be expre...
英字タイトル:
Evaluation Technique of Neutron-Irradiation Embrittlement in Welded RPV