Abstract
Irradiation creep behavior of low activation steels, developed as structural materials for fusion reactors, was investigated. The objective of this study is to provide a fundamental understanding of the irradiation creep mechanism based on microstructural evolution under fast neutron irradiation. Pressurized tube creep specimens fabricated from tube segments were irradiated in the Fast Flux Test Facility (FFTF), Materials Open Test Assembly (MOTA) during FFTF Cycles 11 and 12. This paper provides the first creep results obtained after FFTF cycle-11 irradiation. (2.25-3)Cr-(1-2)W bainitic steels and 12Cr-2W ferritic/martensitic steels showed equivalent or superior creep resistance to a modified 316 stainless steel, known as Japanese Prime Candidate Alloy (JPCA), under fast neutron irradiation up to 600 o C
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