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Bundle experiments on the meltdown behavior of PWR fuel rods

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5352819
;
None
Research Organization:
Kernforschungszentrum, Karlsruhe, Germany
OSTI ID:
5352819
Report Number(s):
CONF-791103-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 33
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
ALLOYS
CHALCOGENIDES
CHEMICAL REACTIONS
FLUID FLOW
FUEL ELEMENTS
FUEL RODS
LIQUID FLOW
LOSS OF COOLANT
MELTDOWN
OXIDATION
OXIDES
OXYGEN COMPOUNDS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
THERMAL STRESSES
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS