Overview of lower length scale model development for accident tolerant fuels regarding U3Si2 fuel and FeCrAl cladding
- 1. Idaho National Laboratory (United States)
Description
U3Si2 and FeCrAl have been proposed as fuel and cladding concepts, respectively, for accident tolerance fuels with higher tolerance to accident scenarios compared to UO2. However, a lot of key physics and material properties regarding their in-pile performance are yet to be explored. To accelerate the understanding and reduce the cost of experimental studies, multiscale modeling and simulation are used to develop physics-based materials models to assist engineering scale fuel performance modeling. In this report, the lower-length-scale efforts in method and material model development supported by the Accident Tolerance Fuel (ATF) high-impact-problem (HIP) under the NEAMS program are summarized. Significant progresses have been made regarding interatomic potential, phase field models for phase decomposition and gas bubble formation, and thermal conductivity for U3Si2 fuel, and precipitation in FeCrAl cladding. The accomplishments are very useful by providing atomistic and mesoscale tools, improving the current understanding, and delivering engineering scale models for these two ATF concepts.
Availability note (English)
Available from https://inldigitallibrary.inl.gov/sites/sti/sti/7406472.pdf; PURL: http://www.osti.gov/servlets/purl/1389929/Additional details
Identifiers
Publishing Information
- Imprint Pagination
- vp.
- Report number
- INL/EXT--16-40010
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 49039361
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- ACCIDENT-TOLERANT NUCLEAR FUELS; CLADDING; COMPARATIVE EVALUATIONS; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; DEPOSITION; ENERGY SOURCES; EVALUATION; FUELS; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; REACTOR MATERIALS; SURFACE COATING; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Contract/Grant/Project number
- AC07-05ID14517
- Funding organization
- USDOE Office of Nuclear Energy - NE (United States)
- Secondary number(s)
- OSTIID--1389929