Anisotropic Effects of Loading on Zircaloy Cladding Performance
This presentation provides recent results related to the mechanical behavior of Zircaloy cladding for the Light Water Reactor Fuels Workshop/CRAFT Initiative Update presented by the Advanced Fuels Campaign. This presentation focuses on Zircaloy cladding response to pellet-cladding interactions and how mechanical anisotropy makes the cladding sensitive to the testing mode. Results are compared to existing material models used by BISON, and implications for reactor performance are briefly discussed.
Authors
- Malachi Nelson (ORCID: https://orcid.org/0000-0002-6027-552X)
Institutions
- Idaho National Laboratory (US)
Publication Details
- Journal
- OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
- Published
- 2024-12-20
- Primary Topic
- Nuclear Materials and Properties
- Type
- article
Funders
- U.S. Department of Energy
- Battelle