Multi-scale modeling of radiation damage in FeCr alloy

Since irradiation experiments of ferritic/martensitic (F/M) FeCr alloys show that F/M steels undergo much less swelling than austenitic steels during neutron or charged particle irradiation, in addition, it is well-known that high chromium content of F/M alloys provide good resistance against corrosion, they are considered as one of the most attractive candidate materials for future nuclear facilities, such as Fusion Reactor, ADS and generation W reactors. Although irradiation experiments can not be replaced by modeling, a purely experimental approach to understanding the effects of irradiation is also not practicable, so in recent years substantial progress has been made in the field of multi-scale modeling of radiation damage in F/M FeCr alloys. The present paper is a review of methods used and results achieved within the last couple of years, and some suggestions are put forward for the further improvements.