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

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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 ... continued below

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Pages: (10 p)

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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)) April 1, 1992.

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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.

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Pages: (10 p)

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OSTI; NTIS; INIS; GPO Dep.

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  • International high level radioactive waste management (IHLRWM) conference: promoting understanding through education and communication, Las Vegas, NV (United States), 12-16 Apr 1992

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  • Other: DE92012326
  • Report No.: PNL-SA-19941
  • Report No.: CONF-920430--91
  • Grant Number: AC06-76RL01830
  • Office of Scientific & Technical Information Report Number: 5664668
  • Archival Resource Key: ark:/67531/metadc1094086

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • April 1, 1992

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  • Feb. 10, 2018, 10:06 p.m.

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  • April 20, 2018, 12:51 p.m.

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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)). Testing and COBRA-SFS analysis of the VSC-17 ventilated concrete, spent fuel storage cask, article, April 1, 1992; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc1094086/: accessed December 13, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.