Vitrification of high level wastes: a review of the computer thermal analyses for storage canisters
CANIST, a two-dimensional (r and THETA) computer program that solves the unsteady-state, heat conduction equation was used to model the thermal behavior of canisters filled with waste glass. CANIST has been found to be a valuable analytical tool for predicting the temperature profile of a waste storage canister as a function of several variables, including the diameter of the canister, the placement of internal fins, the heat generation rate of the waste glass, and the thermophysical properties of the canister and the waste glass. Thus, temperature dependent processes that may affect the integrity of the glass/canister unit, for example cracking, can be investigated using an analytical approach. In the present study, the canister temperature profiles predicted by CANIST were compared to canister temperatures measured during full-scale non-radioactive waste immobilization tests conducted at Pacific Northwest Laboratory. The agreement between experimental and predicted temperatures was good, particularly considering the fact that the thermophysical properties of the waste glass modeled have not yet been accurately determined. Examination of some glass-filled canisters has revealed cracking to have occurred in the glass. However, the comparison between measured and CANIST predicted temperatures suggests that cracking does not significantly influence the heat-transfer process. CANIST was also used to evaluate different ways of reducing the centerline temperature of a canister, and to predict the centerline temperature as a function of the heat generation rate of the waste glass and the type of interim storage, i.e., air or water.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 6665183
- Report Number(s):
- PNL-SA-7917; CONF-790822-17; TRN: 81-002895
- Resource Relation:
- Conference: 87. AICHE national meeting, Boston, MA, USA, 19 Aug 1979
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
CONTAINERS
HEAT TRANSFER
TEMPERATURE DISTRIBUTION
RADIOACTIVE WASTE STORAGE
HIGH-LEVEL RADIOACTIVE WASTES
C CODES
COMPUTERIZED SIMULATION
GLASS
RADIOACTIVE WASTE PROCESSING
SOLID WASTES
SOLIDIFICATION
VITRIFICATION
COMPUTER CODES
ENERGY TRANSFER
MANAGEMENT
MATERIALS
PHASE TRANSFORMATIONS
POLLUTANTS
PROCESSING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
SIMULATION
STORAGE
WASTE MANAGEMENT
WASTE PROCESSING
WASTE STORAGE
WASTES
052002* - Nuclear Fuels- Waste Disposal & Storage
990200 - Mathematics & Computers