Fuel/Basket Degradation and Waste Package Pressure Effects Modeling (Progress Report)
- Itasca Consulting Group, Minneapolis, MN (United States)
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Progress is reported on development and testing of the Fuel/Basket Degradation Model, and the Waste Package Breach Model. The work follows on reported FY19 model development (SNL-ICG 2019). Modeling has addressed questions framed in the deliverable description: 1) how fuel/basket damage, including from seismic ground motion, could impact reactivity; 2) whether dynamic degradation processes (e.g., caused by seismic ground motion) should be targets for further model development; and 3) what are the key model parameters and how do they affect the likelihood and energy of criticality events. For basket structure made from aluminum-based metal-matrix composite material, basket collapse would coincide with loss of neutron absorbers, and would occur within a few hundred years after waste package breach. Degradation models discussed in this report have thus far focused on a generic 32-PWR (pressurized water reactor fuel) basket with aluminum-based plates
- Research Organization:
- Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Itasca Consulting Group, Minneapolis, MN (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE), Office of Spent Fuel and Waste Disposition; USDOE National Nuclear Security Administration (NNSA)
- DOE Contract Number:
- AC04-94AL85000; NA0003525
- OSTI ID:
- 1763591
- Report Number(s):
- SAND--2021-0015R; M2SF--20SN010305073-Rev.01; 693173
- Country of Publication:
- United States
- Language:
- English
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