Published November 1981 | Version v1
Report Restricted

Studies and research concerning BNFP: operational assessment of the FSV-1 (HTGR) spent fuel shipping cask in alternate modes

Creators

Description

This report presents an operational assessment of the FSV-1 spent fuel shipping cask which was developed by General Atomic specifically for the Fort St. Vrain reactor. Of primary interest is the adaptation to underwater loading and unloading of light-water-reactor (LWR) fuel in this cask which was designed for the dry-handling of high temperature gas cooled reactor (HTGR) fuel. Also presented is a concept for a system to compare the pros and cons of wet and dry handling of this and other casks

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A05/MF A01 as DE82007904.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
84 p.
Report number
AGNS--35900-1.1-157

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
14720035
Subject category
S42: ENGINEERING;
Descriptors DEI
BWR TYPE REACTORS; CASKS; HTGR TYPE REACTORS; MATERIALS HANDLING; PERFORMANCE TESTING; PWR TYPE REACTORS; SPENT FUEL ELEMENTS
Descriptors DEC
CONTAINERS; FUEL ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; REACTOR COMPONENTS; REACTORS; TESTING; WATER COOLED REACTORS; WATER MODERATED REACTORS