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Behavior of a failed fuel rod during film boiling operation. [PWR]

Conference ·
OSTI ID:6168938
; ;
A single rod power-coolant-mismatch test (Test PCM-1) was conducted in the Power Burst Facility to evaluate the behavior of a pressurized water reactor (PWR)-type fuel rod subjected to film boiling operation at high power for a time exceeding that resulting in rod failure. The mechanisms of rod failure, the test rod response following failure, and the consequences of operation with a large molten fuel radius following fuel rod failure were investigated through destructive and nondestructive examination.
Research Organization:
Idaho National Engineering Lab., Idaho Falls (USA)
DOE Contract Number:
EY-76-C-07-1570
OSTI ID:
6168938
Report Number(s):
CONF-790602-3
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
BOILING
FILM BOILING
FUEL ELEMENT FAILURE
PBF REACTOR
PHASE TRANSFORMATIONS
POWER-COOLING-MISMATCH ACCIDENTS
PULSED REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
SIMULATION
TANK TYPE REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS