Application of the TEMPEST computer code to canister-filling heat transfer problems
Description
Pacific Northwest Laboratory (PNL) researchers used the TEMPEST computer code to simulate thermal cooldown behavior of nuclear waste glass after it was poured into steel canisters for long-term storage. The objective of this work was to determine the accuracy and applicability of the TEMPEST code when used to compute canister thermal histories. First, experimental data were obtained to provide the basis for comparing TEMPEST-generated predictions. Five canisters were instrumented with appropriately located radial and axial thermocouples. The canister were filled using the pilot-scale ceramic melter (PSCM) at PNL. Each canister was filled in either a continous or a batch filling mode. One of the canisters was also filled within a turntable simulant (a group of cylindrical shells with heat transfer resistances similar to those in an actual melter turntable). This was necessary to provide a basis for assessing the ability of the TEMPEST code to also model the transient cooling of canisters in a melter turntable. The continous-fill model, Version M, was found to predict temperatures with more accuracy. The turntable simulant experiment demonstrated that TEMPEST can adequately model the asymmetric temperature field caused by the turntable geometry. Further, TEMPEST can acceptably predict the canister cooling history within a turntable, despite code limitations in computing simultaneous radiation and convection heat transfer between shells, along with uncertainty in stainless-steel surface emissivities. Based on the successful performance of TEMPEST Version M, development was initiated to incorporate 1) full viscous glass convection, 2) a dynamically adaptive grid that automatically follows the glass/air interface throughout the transient, and 3) a full enclosure radiation model to allow radiation heat transfer to non-nearest neighbor cells. 5 refs., 47 figs., 17 tabs
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A08/MF A01 as DE88008072.
Files
Additional details
Publishing Information
- Imprint Pagination
- 175 p.
- Report number
- PNL--6474
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20009016
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S42: ENGINEERING;
- Descriptors DEI
- ANNEALING; CONTAINERS; COOLING; CRACKS; GLASS; HEAT TRANSFER; HIGH-LEVEL RADIOACTIVE WASTES; INHIBITION; RADIANT HEAT TRANSFER; T CODES; THERMAL INSULATION; VITRIFICATION
- Descriptors DEC
- COMPUTER CODES; ENERGY TRANSFER; HEAT TREATMENTS; MATERIALS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; WASTES