Thermal analysis of the modified Hallum Nuclear Power Facility cask using experimentally obtained thermal boundary conditions corresponding to an engulfing open pool fire
This report presents the two-dimensional heat transfer analysis of an open pool fire surrounding a modified radioactive materials transport cask. The cask is an older cask that was used by the Hallum Nuclear Power Facility (HNPF). The HNPF cask did not have a neutron shielding region but was modified to include one for testing purposes. Analysis of the thermal effects of an engulfing open pool fire was performed with the use of the heat transfer code Q/TRAN, which had previously been used in thermal benchmarking problems for spent nuclear fuel casks. Boundary condition data for the analysis were derived from experimental open pool fire tests of large-scale calorimeter test articles performed at SNL that produced information about cask surface heat flux versus surface temperature relationships. Data analysis was directed toward a determination of the thermal response of the cask, particularly the extent of lead melt since lead is used within the HNPF cask's gamma-shielding region. Parameters, such as surface emissivity and internal heat generation rate, can affect the results of the thermal analysis which control the amount of lead melt. A parameter sensitivity analysis was performed using a one-dimensional model to describe how surface emissivity and internal heat generation rates affect the temperature distribution within the cask. The information from this analysis was used to determine the range of parameters for the two-dimensional thermal analysis. 13 refs., 57 figs., 8 tabs.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5999839
- Report Number(s):
- SAND-87-0060; TTC-0712; ON: DE87014309
- Resource Relation:
- Other Information: Portions of this document are illegible in microfiche products. Original copy available until stock is exhausted
- Country of Publication:
- United States
- Language:
- English
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CASKS
HEAT TRANSFER
TEMPERATURE DISTRIBUTION
COMPUTER CODES
SPENT FUEL CASKS
BOUNDARY CONDITIONS
CALORIMETERS
FIRES
GAMMA RADIATION
HIGH-LEVEL RADIOACTIVE WASTES
LEAD
MELTING
Q CODES
SENSITIVITY
SHIELDING
TWO-DIMENSIONAL CALCULATIONS
CONTAINERS
ELECTROMAGNETIC RADIATION
ELEMENTS
ENERGY TRANSFER
IONIZING RADIATIONS
MATERIALS
MEASURING INSTRUMENTS
METALS
PHASE TRANSFORMATIONS
RADIATIONS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
WASTES
050900* - Nuclear Fuels- Transport
Handling
& Storage