Fuel rod behavior during test PCM-2. [PWR]
The results are presented from the Power-Cooling-Mismatch (PCM) Test Series, Test PCM-2, conducted in the Power Burst Facility at the Idaho National Engineering Laboratory. Four unirradiated pressurized water reactor (PWR) type fuel rods were subjected to eight departure from nucleate boiling (DNB) cycles to provide data on the thermal hydraulic conditions which affect the onset of DNB and termination of film boiling operation during nuclear operation in a PWR environment. During the last DNB cycle, film boiling conditions were continued for up to 117 seconds to provide data on the effects of sustained film boiling operation on fuel rod thermal and mechanical behavior. Conclusions were reached on factors which affect the onset of DNB and termination of film boiling, the effects of sustained film boiling on fuel rod behavior, and the resultant damage to the rod when cladding temperatures equilibrate in the high alpha phase (810 to 1105 K) temperature range and above the beta phase transformation temperature (> 1245 K).
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6142236
- Report Number(s):
- NUREG/CR-0647; TREE-1332
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fuel rod behavior during Test PCM-4
Power-Cooling-Mismatch Test Series: Test PCM-3 postirradiation examination. [PWR]
Related Subjects
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILING
ENERGY TRANSFER
FILM BOILING
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MECHANICS
PHASE TRANSFORMATIONS
POWER-COOLING-MISMATCH ACCIDENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS