The 9th International Conference on Multiscale Materials Modeling

講演情報

Symposium

B. Challenges in the Multiscale Modelling of Radiation Effects in Nuclear Materials

[SY-B6] Symposium B-6

2018年11月1日(木) 11:15 〜 12:30 Room10

Chair: Jaime Marian(University of California Los Angeles, United States of America)

[SY-B6] Ion Irradiation as a Surrogate for Reactor Irradiation: The Expected and the Surprises

Invited

Gary S Was1, Zhijie Jiao1, David Woodley1, Stephen Taller1, Gerrit Vancoevering1, Anthony Monterrosa1, Elizabeth Getto4, Brian Wirth2, Arthur Motta3 (1.University of Michigan, United States of America, 2.University of Tennessee, United States of America, 3.Pennsylvania State University, United States of America, 4.United Stated Naval Academy, United States of America)

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 of fast and thermal reactors, and high chromium and high nickel-containing austenitic steels are potential replacement alloys for LWR core materials. Both require high dpa, for which ion irradiation is ideally suited. To simulate the reactor radiation environment, self-ion irradiation and He injection are conducted simultaneously into both F-M and austenitic alloys. Reactor irradiations of the same alloys have been, or are being conducted in the BOR-60 fast reactor to assess the capability of ion irradiation to emulate the evolution of reactor generated microstructures and mechanical properties. 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. To date, agreement is quite promising with many outcomes ocurring as expected. However, there are a number of observations or results that are unexpected. Results will be presented on the microstructure and mechanical property evolution in ion and reactor irradiation integrated with computational modelling in an effort to understand the extent to which ion irradiation can be used as a surrogate for reactor irradiation, and to illuminate processes that are not well understood.