Post-test thermal calculations and data analyses for the Spent Fuel Test, Climax
Description
After the Spent Fuel Test - Climax (SFT-C) was completed, additional calculations were performed using the best available (directly measured or inferred from measurements made during the test) input parameters, thermal properties, and power levels. This report documents those calculations and compares the results with measurements made during the three-year heating phase and six-month posttest cooling phase of the SFT-C. Three basic types of heat-transfer calculations include a combined two-dimensional/three-dimensional, infinite-length, finite-difference model; a fully three-dimensional, finite-length, finite-difference model; and a fully three-dimensional, finite-length, analytical solution. The finite-length model much more accurately reflects heat flow near the ends of the array and produces cooler temperatures everywhere than does its infinite-length counterpart. 14 refs., 144 figs., 4 tabs
Availability note (English)
Available from NTIS, PC A04/MF A01; 1 as DE87013822.
Files
Additional details
Additional titles
- Augmented title (English)
- NNWSI
Publishing Information
- Imprint Pagination
- 72 p.
- Report number
- UCRL--53728
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19014309
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; DATA PROCESSING; FLOW MODELS; HEAT TRANSFER; HIGH-LEVEL RADIOACTIVE WASTES; MATHEMATICAL MODELS; NEVADA; SPENT FUELS; UNDERGROUND STORAGE; VENTILATION; YUCCA MOUNTAIN
- Descriptors DEC
- DEVELOPED COUNTRIES; ENERGY SOURCES; ENERGY TRANSFER; EVALUATION; FUELS; MATERIALS; MOUNTAINS; NORTH AMERICA; NUCLEAR FUELS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; REACTOR MATERIALS; STORAGE; USA; WASTES
Optional Information
- Notes
- Portions of this document are illegible in microfiche products.