Heat transfer analysis of the waste-container sleeve/salt configuration

Technical Report · Mon Mar 31 00:00:00 EDT 1975

DOI:https://doi.org/10.2172/7119655· OSTI ID:7119655

Callahan, G. D.; Ratigan, J. L.; Russell, J. E.; Fossum, A. F.

Prior to this investigation, the heat transport considered was only that of straight conduction. The waste container, air gap, and sleeve arrangement was considered to be a single, consistent, time-dependent, heat-generating unit in intimate contact with the salt. The conduction model does not accurately model the heat transfer mechanisms available. Thus radiation and combined radiation and convection must also be considered in the determination of the temperature field. As would be expected, the canister temperatures are higher for the case of radiation across the airgap than those that result from conduction when the canister is in intimate contact with the salt. For the radiation case, the canister temperatures rise rapidly to a temperature of approximately 1,140/sup 0/F and maintain an almost steady state condition for one year whereafter the temperatures slowly decrease. The far field temperatures, near the pillar centerline, are essentially equivalent for all cases. As time proceeds, the far field temperatures of the conduction models are about 15% different.

• Research Organization: Union Carbide Corp., Oak Ridge, TN (USA). Office of Waste Isolation
• DOE Contract Number: W-7405-ENG-26; SUB-4269
• OSTI ID: 7119655
• Report Number(s): ORNL/Sub/4269-7; TRN: 77-009036
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
RADIOACTIVE WASTES
HEAT TRANSFER
COMPUTER CALCULATIONS
FINITE ELEMENT METHOD
MATHEMATICAL MODELS
RADIOACTIVE WASTE DISPOSAL
TEMPERATURE GRADIENTS
ENERGY TRANSFER
MANAGEMENT
NUMERICAL SOLUTION
RADIOACTIVE MATERIALS
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES
052002* - Nuclear Fuels- Waste Disposal & Storage