Use of a commercial heat transfer code to predict horizontally oriented spent fuel rod temperatures
- GRAM, Inc., Albuquerque, NM (United States)
- Sandia National Labs., Albuquerque, NM (United States)
Radioactive spent fuel assemblies are a source of hazardous waste that will have to be dealt with in the near future. It is anticipated that the spent fuel assemblies will be transported to disposal sites in spent fuel transportation casks. In order to design a reliable and safe transportation cask, the maximum cladding temperature of the spent fuel rod arrays must be calculated. The maximum rod temperature is a limiting factor in the amount of spent fuel that can be loaded in a transportation cask. The scope of this work is to demonstrate that reasonable and conservative spent fuel rod temperature predictions can be made using commercially available thermal analysis codes. The demonstration is accomplished by a comparison between numerical temperature predictions, with a commercially available thermal analysis code, and experimental temperature data for electrical rod heaters simulating a horizontally oriented spent fuel rod bundle.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 10191811
- Report Number(s):
- SAND--92-2138C; CONF-930408--5; ON: DE93002302
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
052002
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
99 GENERAL AND MISCELLANEOUS
990200
FUEL ASSEMBLIES
FUEL CANS
HEAT TRANSFER
MATHEMATICS AND COMPUTERS
P CODES
Q CODES
SPENT FUEL CASKS
SPENT FUELS
TEMPERATURE DISTRIBUTION
TEMPERATURE MEASUREMENT
THERMAL ANALYSIS
TRANSPORT
TRANSPORT, HANDLING, AND STORAGE
WASTE DISPOSAL AND STORAGE