Modeling of Canwall failure for whole core transition phase analysis
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5114265
None
- Research Organization:
- ANL, Argonne, IL 60439
- OSTI ID:
- 5114265
- Report Number(s):
- CONF-811103-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 39
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
EPITHERMAL REACTORS
FAILURES
FAST REACTORS
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FUEL ASSEMBLIES
FUEL CANS
FUEL-CLADDING INTERACTIONS
LIQUID METAL COOLED REACTORS
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REACTOR ACCIDENTS
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STRESSES
THERMAL STRESSES
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
EPITHERMAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FUEL ASSEMBLIES
FUEL CANS
FUEL-CLADDING INTERACTIONS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
THERMAL STRESSES