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

Conference · Wed Apr 01 00:00:00 EST 1992

OSTI ID:5664668

McKinnon, M A; Dodge, R E ^[1]; Schmitt, R C ^[2]

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1. Pacific Northwest Lab., Richland, WA (United States)
2. EG and G Idaho, Inc., Idaho Falls, ID (United States)

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.

• Research Organization: Pacific Northwest Lab., Richland, WA (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 5664668
• Report Number(s): PNL-SA-19941; CONF-920430-91; ON: DE92012326
• Resource Relation: Conference: International high level radioactive waste management (IHLRWM) conference: promoting understanding through education and communication, Las Vegas, NV (United States), 12-16 Apr 1992
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
42 ENGINEERING
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
SPENT FUEL CASKS
HEAT TRANSFER
PERFORMANCE TESTING
CONCRETES
DOSE RATES
GAMMA RADIATION
NEUTRONS
PERFORMANCE
PWR TYPE REACTORS
SHIELDING
SPENT FUEL STORAGE
TEMPERATURE MEASUREMENT
BARYONS
BUILDING MATERIALS
CASKS
CONTAINERS
ELECTROMAGNETIC RADIATION
ELEMENTARY PARTICLES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FERMIONS
HADRONS
IONIZING RADIATIONS
MATERIALS
NUCLEONS
POWER REACTORS
RADIATIONS
REACTORS
STORAGE
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
052002* - Nuclear Fuels- Waste Disposal & Storage
420203 - Engineering- Handling Equipment & Procedures
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled