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

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Title: Mechanical properties and microstructural stability of 11Cr-ferritic/martensitic steel cladding under irradiation
Authors: Yano, Yasuhide Browse this author
Yamashita, Shinichiro Browse this author
Ohtsuka, Satoshi Browse this author
Kaito, Takeji Browse this author
Akasaka, Naoaki Browse this author
Shibayama, Tamaki Browse this author
Watanabe, Seiichi Browse this author →KAKEN DB
Takahashi, Heishichiro Browse this author
Keywords: Fast Reactor Materials
Mechanical Properties
Neutron Irradiation
Ferritic/Martensitic steels
Issue Date: Mar-2010
Publisher: Elsevier B.V.
Journal Title: Journal of Nuclear Materials
Volume: 398
Issue: 1-3
Start Page: 59
End Page: 63
Publisher DOI: 10.1016/j.jnucmat.2009.10.010
Abstract: 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.
Type: article (author version)
Appears in Collections:工学院・工学研究院 (Graduate School of Engineering / Faculty of Engineering) > 雑誌発表論文等 (Peer-reviewed Journal Articles, etc)

Submitter: 渡辺 精一

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