NEAMS-ATF M3 Milestone Report: Literature Review of Modeling of Radiation-Induced Swelling in Fe-Cr-Al Steels
Fe-Cr-Al steels are proposed as accident-tolerant-fuel (ATF) cladding materials in light water reactors due to their excellent oxidation resistance at high temperatures. Currently, the understanding of their performance in reactor environment is still limited. In this review, firstly we reviewed the experimental studies of Fe-Cr-Al based alloys with particular focus on the radiation effects in these alloys. Although limited data are available in literature, several previous and recent experimental studies have shown that Fe-Cr-Al based alloys have very good void swelling resistance at low and moderate irradiation doses but the growth of dislocation loops is very active. Overall, the behavior of radiation damage evolution is similar to that in Fe-Cr ferritic/martensitic alloys. Secondly, we reviewed the rate theory-based modeling methods for modeling the coevolution of voids and dislocation loops in materials under irradiation such as Frenkel pair three-dimensional diffusion model (FP3DM) and cluster dynamics. Finally, we summarized and discussed our review and proposed our future plans for modeling radiation damage in Fe-Cr-Al based alloys.
- Idaho National Lab. (INL), Idaho Falls, ID (United States). Fuel Modeling and Simulation Dept.
- Publication Date:
- OSTI Identifier:
- Report Number(s):
- DOE Contract Number:
- Resource Type:
- Technical Report
- Research Org:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Org:
- USDOE Office of Nuclear Energy (NE)
- Country of Publication:
- United States
- 36 MATERIALS SCIENCE; CHROMIUM STEELS; ALUMINIUM ALLOYS; PHYSICAL RADIATION EFFECTS; ACCIDENT-TOLERANT NUCLEAR FUELS; DISLOCATIONS; SWELLING; WATER MODERATED REACTORS; COMPUTERIZED SIMULATION; FUEL CANS; WATER COOLED REACTORS; RADIATION DOSES; VOIDS; THREE-DIMENSIONAL CALCULATIONS; TIME DEPENDENCE; IRRADIATION
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