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Oral presentation

R&D of advanced stainless steels for BWR fuel claddings, 2-6; Tritium permeability and high temperature steam oxidation properties

Takahashi, Katsuhito*; Sakamoto, Kan*; Otsuka, Teppei*; Ukai, Shigeharu*; Hirai, Mutsumi*; Yamashita, Shinichiro

no journal, , 

no abstracts in English

Oral presentation

R&D of advanced stainless steels for BWR fuel claddings, 3-8; Mechanical properties after neutron irradiation

Takahashi, Katsuhito*; Nozue, Mitsuo*; Miura, Yusuke*; Sakamoto, Kan*; Kimura, Akihiko*; Ukai, Shigeharu*; Yamashita, Shinichiro

no journal, , 

Influence of the neutron irradiation on mechanical properties of FeCrAl ODS stainless steel was estimated as a part of research and development of the accident tolerant fuel. Neutron irradiation of FeCrAl-ODS stainless steel aiming at dose level of 2.6, 3.9, 7.8 and 13 dpa is being carried out at ORNL. In the study, the mechanical properties of FeCrAl-ODS stainless steel were measured up to 2.6 dpa.

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