Thermal analysis of the modified Hallum Nuclear Power Facility cask using experimentally obtained thermal boundary conditions corresponding to an engulfing open pool fire
Abstract
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 ratesmore »
- Authors:
- Publication Date:
- Research Org.:
- Sandia National Labs., Albuquerque, NM (USA)
- OSTI Identifier:
- 5999839
- Report Number(s):
- SAND-87-0060; TTC-0712
ON: DE87014309
- DOE Contract Number:
- AC04-76DP00789
- Resource Type:
- Technical Report
- 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
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 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
Citation Formats
Longenbaugh, R S, Sanchez, L C, and Gregory, J J. Thermal analysis of the modified Hallum Nuclear Power Facility cask using experimentally obtained thermal boundary conditions corresponding to an engulfing open pool fire. United States: N. p., 1987.
Web.
Longenbaugh, R S, Sanchez, L C, & Gregory, J J. Thermal analysis of the modified Hallum Nuclear Power Facility cask using experimentally obtained thermal boundary conditions corresponding to an engulfing open pool fire. United States.
Longenbaugh, R S, Sanchez, L C, and Gregory, J J. 1987.
"Thermal analysis of the modified Hallum Nuclear Power Facility cask using experimentally obtained thermal boundary conditions corresponding to an engulfing open pool fire". United States.
@article{osti_5999839,
title = {Thermal analysis of the modified Hallum Nuclear Power Facility cask using experimentally obtained thermal boundary conditions corresponding to an engulfing open pool fire},
author = {Longenbaugh, R S and Sanchez, L C and Gregory, J J},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/5999839},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Aug 01 00:00:00 EDT 1987},
month = {Sat Aug 01 00:00:00 EDT 1987}
}