Testing and COBRA-SFS analysis of the VSC-17 ventilated concrete, spent fuel storage cask
Abstract
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.
- Authors:
-
- Pacific Northwest Lab., Richland, WA (United States)
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
- Publication Date:
- Research Org.:
- Pacific Northwest Lab., Richland, WA (United States)
- Sponsoring Org.:
- USDOE, Washington, DC (United States)
- OSTI Identifier:
- 10141991
- Report Number(s):
- PNL-SA-19941; CONF-920430-91
ON: DE92012326
- DOE Contract Number:
- AC06-76RL01830
- Resource Type:
- Conference
- Resource Relation:
- Conference: 3. international high level radioactive waste management (IHLRWM) conference,Las Vegas, NV (United States),12-16 Apr 1992; Other Information: PBD: Apr 1992
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 42 ENGINEERING; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; SPENT FUEL CASKS; PERFORMANCE TESTING; HEAT TRANSFER; SPENT FUEL STORAGE; PWR TYPE REACTORS; DOSE RATES; GAMMA RADIATION; NEUTRONS; PERFORMANCE; TEMPERATURE MEASUREMENT; CONCRETES; SHIELDING; 052002; 420203; 210200; WASTE DISPOSAL AND STORAGE; HANDLING EQUIPMENT AND PROCEDURES; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED
Citation Formats
McKinnon, M A, Dodge, R E, and Schmitt, R C. Testing and COBRA-SFS analysis of the VSC-17 ventilated concrete, spent fuel storage cask. United States: N. p., 1992.
Web.
McKinnon, M A, Dodge, R E, & Schmitt, R C. Testing and COBRA-SFS analysis of the VSC-17 ventilated concrete, spent fuel storage cask. United States.
McKinnon, M A, Dodge, R E, and Schmitt, R C. 1992.
"Testing and COBRA-SFS analysis of the VSC-17 ventilated concrete, spent fuel storage cask". United States. https://www.osti.gov/servlets/purl/10141991.
@article{osti_10141991,
title = {Testing and COBRA-SFS analysis of the VSC-17 ventilated concrete, spent fuel storage cask},
author = {McKinnon, M A and Dodge, R E and Schmitt, R C},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/10141991},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Apr 01 00:00:00 EST 1992},
month = {Wed Apr 01 00:00:00 EST 1992}
}