Modeling Creep Rupture of Zirconium Alloys
Safe interim dry storage of spent nuclear fuel (SNF) must be maintained for a minimum of twenty years according to the Code of Federal Regulations. The most important variable that must be regulated by dry storage licensees in order to meet current safety standards is the temperature of the SNF. The two currently accepted models to define the maximum allowable storage temperature for SNF are based on a diffusion controlled cavity growth (DCCG) failure mechanism for the cladding. Although these models are based on the same fundamental failure theory (DCCG), the researchers who developed the models made different assumptions, including selection of some of the most critical variables in the DCCG failure equation. These inconsistencies are discussed together with recommended modifications to the failure models based on recent data.
- Research Organization:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Sponsoring Organization:
- USDOE Office of Defense Programs (DP) (US)
- DOE Contract Number:
- W-7405-Eng-48
- OSTI ID:
- 791517
- Report Number(s):
- UCRL-JC-138714; TRN: US0300680
- Resource Relation:
- Conference: 8th International Symposium on Plasticity and its Current Applications, Whistler Resort, British Columbia (CA), 07/17/2000--07/21/2000; Other Information: PBD: 8 Apr 2000
- Country of Publication:
- United States
- Language:
- English
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