Open AccessMulti-scale modeling of radiation damage in FeCr alloy
Author(s) -
HE Xin-fu,
Yang Wen,
Fan Su
Publication year - 2009
Publication title -
wuli xuebao
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.199
H-Index - 47
ISSN - 1000-3290
DOI - 10.7498/aps.58.8657
Subject(s) - austenite , irradiation , materials science , alloy , radiation damage , martensite , corrosion , metallurgy , nuclear engineering , chromium , neutron , neutron irradiation , microstructure , nuclear physics , engineering , physics
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 irradiationin 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 Ⅳ 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.