Published May 1992 | Version v1
Report

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

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

Description

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 ampersand 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

Availability note (English)

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Additional details

Additional titles

Subtitle (English)
Final report

Publishing Information

Imprint Pagination
169 p.
Report number
EPRI-TR--100305

Optional Information