||The future of nuclear energy can potentially look very different than it does today. New accident tolerant fuel concepts are being developed for a broad range of reactors, including light water reactors (LWRs) and small modular reactors. However, material performance defines the efficiency, safety, and commercial feasibility of all reactor concepts. With recent improvements in modeling and simulation across a wide range of length- and time-scales, computational materials modeling will play a critical role in understanding current reactor technology and in developing new reactor concepts. This symposium will highlight current computational materials engineering efforts for nuclear reactors in the United States and abroad, e.g., the Consortium for the Advanced Simulation of LWRs (CASL) and the Nuclear Energy Advanced Modeling and Simulation Program (NEAMS).
This symposium is seeking abstracts that apply atomistic, mesoscale, and macroscale simulations to discover, understand, and engineer the performance of fission/fusion reactor materials, including fuel, cladding, and structural materials. This symposium will also consider multiscale modeling efforts that bridge length and time scales in order to better connect simulation results with experimental data for predictive model validation. Finally, the application of ICME approaches to use modeling and simulation to better understand structure-property relationships, their associated links with performance, and their application to designing future reactor concepts and materials is also desired. Some examples include, but are not limited to:
- Developing improved material models for LWR fuel and cladding
- Modeling and simulation of critical phenomena in LWRs including CRUD-induced power shift, grid-to-rod-fretting, and pellet-cladding interaction
- Modeling and simulation of new fuel materials including metal, silicide, and nitride fuels
- Modeling and simulation of new cladding materials, such as silicon carbide, coated zirconium alloys, or FeCrAl
- Development and integration of computational tools, methods, and databases for reactor structural material design