Conceptional design of spent fuel shipping casks for older PWR fuel
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5144310
None
- Research Organization:
- ORNL, Oak Ridge, Tn 37830
- OSTI ID:
- 5144310
- Report Number(s):
- CONF-810606-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 38
- 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
CASKS
CONTAINERS
DESIGN
ENERGY SOURCES
FUEL ASSEMBLIES
FUELS
LINERS
MATERIALS
NUCLEAR FUELS
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
SHELLS
SHIELDS
SPENT FUEL CASKS
SPENT FUELS
TRANSPORT
WATER COOLED REACTORS
WATER MODERATED REACTORS
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
420204* -- Engineering-- Shipping Containers
CASKS
CONTAINERS
DESIGN
ENERGY SOURCES
FUEL ASSEMBLIES
FUELS
LINERS
MATERIALS
NUCLEAR FUELS
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
SHELLS
SHIELDS
SPENT FUEL CASKS
SPENT FUELS
TRANSPORT
WATER COOLED REACTORS
WATER MODERATED REACTORS