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Mitsui, Hiroyuki*; Takahashi, Rieko*; Otsuki, Akiyoshi*; Asano, Hidekazu*; Taniguchi, Naoki; Yui, Mikazu
no journal, ,
The slow strain rate tests(SSRT) of carbon steel were performed in sodium carbonate-sodium-bicarbonate aqueous solution to acquire knowlwdges regarding susceptibility to stress corrosion cracking of welded joint of carbon steel overpack for high-level radioiactive waste disposal. The specimens were taken from thick cylindrical sample welded by TIG and EBW, and then SSRT tests were applied to the each of specimens of base metal, heat affected zone and welded metal. Based on the results, the susceptibility to stress corrosion cracking of welded joint of carbon steel overpack was evaluated.
Taniguchi, Naoki; Suzuki, Hiroyuki*; Yui, Mikazu; Nakanishi, Tomoaki*; Nakayama, Takenori*; Masugata, Tsuyoshi*; Tateishi, Tsuyoshi*
no journal, ,
Titanium (including titanium alloy) is one of the candidate materials of overpacks for geological disposal of high-level radioactive waste, and required long term integrity against the groundwater for more than 1000 years. As the corrosion of titanium occurs, hydrogen is generated since the deep underground environment is originally low oxygen concentration condition. There is a possibility that the titanium overpack will be attackd by the hydrogen embrittlement due to long term hydrogen absorption. In this study, the amount of hydrogen and the possibility of embrittlement were investigated based on the experimental data on the corrosion rate, hydrogen absorption behavior, mechanical proparty of titanium containing hydrogen.
Watanabe, Masatoshi; Takeda, Seiji; Kimura, Hideo
no journal, ,
no abstracts in English
Yamamoto, Masahiro
no journal, ,
no abstracts in English
Onuki, Kaoru; Kubo, Shinji; Tanaka, Nobuyuki; Terada, Atsuhiko; Ota, Hiroyuki; Noguchi, Hiroki; Iwatsuki, Jin; Hino, Ryutaro
no journal, ,
no abstracts in English