Accelerated Ion Irradiation for Emulation of In-reactor Radiation Damage
Reactor core materials in both fast reactors and LWRs granted life extension must withstand irradiation to high doses at high temperature. Ferritic-martensitic (F-M) alloys are attractive candidates for structural components and fuel cladding in fast and thermal reactors, and high chromium and high nickel-containing austenitic steels are potential replacement alloys for LWR core materials. To reach high doses, self-ion irradiation is conducted with simultaneous He injection into both F-M and austenitic alloys, accompanied by reactor irradiations conducted in the BOR-60 fast reactor to assess the capability of ion irradiation to emulate the evolution of microstructure and mechanical properties in reactor. Computational models for defect cluster evolution are being developed and benchmarked against experimental data to ultimately provide predictive capability for the response of both microstructure (loops, voids, precipitates, etc.), and mechanical properties (hardening, ductility, slip behavior) to irradiation. A research program is aimed at understanding how to emulate neutron irradiation using ion irradiation. Results to date have been focused on microstructure and properties of ion irradiated alloys T91, 800H and Fe21Ce32Ni. Data from single ion irradiations are thus far in good agreement with that expected based on previous ion and neutron irradiation data. Dual ion irradiations and neutron irradiated samples are being evaluated and these will be the focus of future work. (authors)