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Spent fuel shipping cask shielding considerations

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5483000
None
Research Organization:
Nuclear Data, Inc., 2734 S. Cobb Industrial Boulevard, Smyrna, GA 30080
OSTI ID:
5483000
Report Number(s):
CONF-830609-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 44
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
ACTINIDES
AFTER-HEAT
BORON
BURNUP
CASKS
CERTIFICATION
COMPUTER CALCULATIONS
CONTAINERS
COOLING TIME
DEPLETED URANIUM
DESIGN
DOSE EQUIVALENTS
DOSE LIMITS
DOSE RATES
ELEMENTS
FUEL ASSEMBLIES
GAMMA SOURCES
HYDROGEN COMPOUNDS
LEAD
METALS
MONTE CARLO METHOD
NEUTRON SOURCES
OXYGEN COMPOUNDS
PARTICLE SOURCES
PERFORMANCE TESTING
RADIATION DOSE UNITS
RADIATION PROTECTION
RADIATION SOURCES
SAFETY STANDARDS
SEMIMETALS
SHIELDING
SPENT FUEL CASKS
STANDARDS
TESTING
UNITS
URANIUM
WATER