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Testing and COBRA-SFS analysis of the VSC-17 ventilated concrete, spent fuel storage cask

Description: A performance test of a Pacific Sierra Nuclear VSC-17 ventilated concrete storage cask loaded with 17 canisters of consolidated PWR spent fuel generating approximately 15 kW was conducted. The performance test included measuring the cask surface, concrete, air channel surface, and fuel temperatures, as well as cask surface gamma and neutron dose rates. Testing was performed using vacuum, nitrogen, and helium backfill environments. Pretest predictions of cask thermal performance were made using the COBRA-SFS computer code. Analysis results were within 15{degrees}C of measured peak fuel temperature. Peak fuel temperature for normal operation was 321{degrees}C. In general, the surface dose rates were less than 30 mrem/h on the side of the cask and 40 mrem/h on the top of the cask.
Date: April 1, 1992
Creator: McKinnon, M.A.; Dodge, R.E. (Pacific Northwest Lab., Richland, WA (United States)) & Schmitt, R.C. (EG and G Idaho, Inc., Idaho Falls, ID (United States))
Partner: UNT Libraries Government Documents Department