THERMAL HISTORY OF CLADDING IN A 21 PWR WASTE PACKAGE LOADED WITH AVERAGE FUEL
The purpose of this calculation is to evaluate a mid-assembly axial fuel cladding temperature profile of a 21 pressurized water reactor (PWR) spent nuclear fuel (SNF) waste package (WP) loaded with average fuel assemblies and emplaced in a monitored geologic repository. This calculation is intended to evaluate Viability Assessment (VA) and Enhanced Design Alternatives (EDA) II design configurations in support of performance assessment. This calculation was developed by Waste Package Operations (WPO) under Office of Civilian Radioactive Waste Management (OCRWM) procedure AP-3.12Q, Revision 0.
- Research Organization:
- Office of Scientific and Technical Information, Oak Ridge, TN
- Sponsoring Organization:
- USDOE
- OSTI ID:
- 860280
- Report Number(s):
- CAL-UDC-ME-000001 REV 00; MOL.20000216.0105 DC#27604
- Country of Publication:
- United States
- Language:
- English
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