Analysis for Materials Test Reactor (MTR Fuel Assemblies in Dry Storage)
This report documents a creep analysis to estimate the maximum acceptable temperature for spent aluminum clad nuclear fuels in dry storage.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 14488
- Report Number(s):
- WSRC-TR-95-0121; TRN: US0111052
- Resource Relation:
- Other Information: PBD: 20 Oct 1999
- Country of Publication:
- United States
- Language:
- English
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