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Probabilistic assssment of fuel rod ballooning in large-bundle LOCA experiments. [BWR, PWR]

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5355844
; ;
None
Research Organization:
Commission of European Community, Ispra, Italy
OSTI ID:
5355844
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 27
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Nonbreeding
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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ACCIDENTS
BWR TYPE REACTORS
DEFORMATION
ELASTICITY
FLOW BLOCKAGE
FUEL ELEMENTS
FUEL RODS
LOSS OF COOLANT
MECHANICAL PROPERTIES
PROBABILITY
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
TENSILE PROPERTIES
THERMOELASTICITY
WATER COOLED REACTORS
WATER MODERATED REACTORS