Performance testing and analyses of the VSC-17 ventilated concrete cask. Final report

Technical Report · Fri May 01 00:00:00 EDT 1992

OSTI ID:10156410

McKinnon, M A; Dodge, R E ^[1]; Schmitt, R C; Eslinger, L E; Dineen, G ^[2]

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

This document details performance test which was conducted on a Pacific Sierra Nuclear VSC-17 ventilated concrete storage cask configured for pressurized-water reactor (PWR) spent fuel. The performance test consisted of loading the VSC-17 cask with 17 canisters of consolidated PWR spent fuel from Virginia Power`s Surry and Florida Power & Light Turkey Point reactors. Cask surface, concrete, air channel surfaces, and fuel canister guide tube temperatures were measured, as were cask surface gamma and neutron dose rates. Testing was performed with vacuum, nitrogen, and helium backfill environments in a vertical cask orientation. Data on spent fuel integrity were also obtained.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (United States); Pacific Northwest Lab., Richland, WA (United States); EG and G Idaho, Inc., Idaho Falls, ID (United States)
• Sponsoring Organization: Electric Power Research Inst., Palo Alto, CA (United States)
• DOE Contract Number: FC06-88RL11394
• OSTI ID: 10156410
• Report Number(s): EPRI-TR--100305; PNL--7839; ON: UN92016487
• Country of Publication: United States
• Language: English

Related Subjects

052002
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
42 ENGINEERING
420204
CONCRETES
HEAT TRANSFER
HELIUM
HYDRAULICS
INERT ATMOSPHERE
NITROGEN
PERFORMANCE TESTING
PWR TYPE REACTORS
RADIATION DOSES
SHIELDING
SHIPPING CONTAINERS
SPENT FUEL CASKS
SPENT FUEL STORAGE
SPENT FUELS
SURRY-1 REACTOR
SURRY-2 REACTOR
SURRY-3 REACTOR
SURRY-4 REACTOR
TEMPERATURE MEASUREMENT
TURKEY POINT-3 REACTOR
TURKEY POINT-4 REACTOR
WASTE DISPOSAL AND STORAGE