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Mechanical properties and microstructural stability of 11Cr-ferritic/martensitic steel cladding under irradiation

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タイトル: Mechanical properties and microstructural stability of 11Cr-ferritic/martensitic steel cladding under irradiation
著者: Yano, Yasuhide 著作を一覧する
Yamashita, Shinichiro 著作を一覧する
Ohtsuka, Satoshi 著作を一覧する
Kaito, Takeji 著作を一覧する
Akasaka, Naoaki 著作を一覧する
Shibayama, Tamaki 著作を一覧する
Watanabe, Seiichi 著作を一覧する
Takahashi, Heishichiro 著作を一覧する
キーワード: Fast Reactor Materials
Mechanical Properties
Neutron Irradiation
Ferritic/Martensitic steels
発行日: 2010年 3月
出版者: Elsevier B.V.
誌名: Journal of Nuclear Materials
巻: 398
号: 1-3
開始ページ: 59
終了ページ: 63
出版社 DOI: 10.1016/j.jnucmat.2009.10.010
抄録: The in-reactor creep rupture tests of 11Cr-0.5Mo-2W, V, Nb F/M steel were carried out in the temperature range from 823 to 943 K using Materials Open Test Assembly in the Fast Flux Test Facility and tensile and temperature-transient-to-burst specimens were irradiated in the experimental fast reactor JOYO at temperatures between 693 and 1013 K to fast neutron doses ranging from 11 to 102 dpa. The results of post irradiation mechanical tests showed that there was no significant degradation in tensile and transient burst strengths even after neutron irradiation below 873 K, but that there was significant degradation in both strengths at neutron irradiation above 903 K. On the other hand, the in-reactor creep rupture times were equal or greater than those of out-reactor creep even after neutron irradiation at all temperatures. This creep rupture behavior was different from that of tensile and transient burst specimens.
資料タイプ: article (author version)
URI: http://hdl.handle.net/2115/48304
出現コレクション:雑誌発表論文等 (Peer-reviewed Journal Articles, etc)

提供者: 渡辺 精一

 

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