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Response of unirradiated and irradiated PWR fuel rods tested under power-cooling-mismatch conditions

Journal Article · · Nucl. Saf.; (United States)
OSTI ID:6741176
; ; ; ;
The report summarizes the results from the single-rod power-cooling-mismatch (PCM) and irradiation effects (IE) tests conducted to date in the Power Burst Facility (PBF) at the U.S. Department of Energy's Idaho National Engineering Laboratory. This work was performed for the U.S. Nuclear Regulatory Commission under contract to the Department of Energy. These tests are part of the Nuclear Regulatory Commission's Fuel Behavior Program, which is designed to provide data for the development and verification of analytical fuel behavior models that are used to predict fuel response to abnormal or postulated accident conditions in commercial light-water reactors (LWRs). The mechanical, chemical, and thermal response of both previously unirradiated and previously irradiated LWR-type fuel rods tested under power-cooling-mismatch conditions is discussed. A brief description of the test designs is presented. The results of the PCM thermal-hydraulic studies are summarized. Primary emphasis is placed on the behavior of the fuel and cladding during and after stable film boiling.
OSTI ID:
6741176
Journal Information:
Nucl. Saf.; (United States), Journal Name: Nucl. Saf.; (United States) Vol. 19:4; ISSN NUSAA
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
BOILING
CHALCOGENIDES
CHEMICAL REACTIONS
CORROSION
DEFORMATION
DEPARTURE NUCLEATE BOILING
FILM BOILING
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
NUCLEATE BOILING
OXIDATION
OXIDES
OXYGEN COMPOUNDS
PBF REACTOR
PERFORMANCE TESTING
PHASE TRANSFORMATIONS
PHYSICAL RADIATION EFFECTS
POWER-COOLING-MISMATCH ACCIDENTS
PULSED REACTORS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SIMULATION
SWELLING
TANK TYPE REACTORS
TESTING
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS