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Report No.
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Structure stability of ferritic ODS steel for fast reactor fuel cladding tube under irradiation

Tanno, Takashi  ; Oka, Hiroshi   ; Yano, Yasuhide  ; Otsuka, Satoshi   ; Kaito, Takeji 

Fe self-ion irradiation to ODS steels was conducted at 400$$^{circ}$$C to evaluate the stability of oxide nano-dispersoids in the ODS steels and embrittlement behavior of higher Cr ODS steel under irradiation. Fe and He dual ion irradiation test at 470$$^{circ}$$C was also conducted to evaluate the influence of He existence. The indentation hardness increased in early stage of the irradiation, and decreased over 150 dpa. But the hardness was higher than that as unirradiated, even if the dose reached 230 dpa. The Cr enrichment from 9Cr to 11Cr would not lead to extra irradiation hardening and/or irradiation embrittlement because the irradiation hardening behavior of 9Cr and 11Cr-ODS steels were almost same. The irradiation hardening due to Fe+He dual ions irradiation was negligible or comparatively small. Therefore it was considered that fine and dense voids formation enhanced by He existence was not significant.

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