Studies and research concerning BNFP: operational assessment of the FSV-1 (HTGR) spent fuel shipping cask in alternate modes
Technical Report
·
OSTI ID:5367093
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.
- Research Organization:
- Allied-General Nuclear Services, Barnwell, SC (USA)
- DOE Contract Number:
- AC09-78ET35900
- OSTI ID:
- 5367093
- Report Number(s):
- AGNS-35900-1.1-157; ON: DE82007904
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
420204 -- Engineering-- Shipping Containers
BWR TYPE REACTORS
CASKS
CONTAINERS
FUEL ELEMENTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
LOADING
MATERIALS HANDLING
PERFORMANCE TESTING
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
SPENT FUEL CASKS
SPENT FUEL ELEMENTS
TESTING
UNLOADING
WATER COOLED REACTORS
WATER MODERATED REACTORS
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
420204 -- Engineering-- Shipping Containers
BWR TYPE REACTORS
CASKS
CONTAINERS
FUEL ELEMENTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
LOADING
MATERIALS HANDLING
PERFORMANCE TESTING
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
SPENT FUEL CASKS
SPENT FUEL ELEMENTS
TESTING
UNLOADING
WATER COOLED REACTORS
WATER MODERATED REACTORS