Power Burst Facility thermocouple effects test results report: Test Series TC-1, TC-3, and TC-4
Fuel rod cladding surface temperatures have been estimated in Loss-of-Fluid Test (LOFT) Facility and in Power Burst Facility loss-of-coolant accident (LOCA) tests using data obtained with thermocouples welded to the cladding outer surface. These cladding temperature estimates have been questioned because cladding surface thermocouples may act as cooling fins and local sites of cladding rewet, thereby delaying the time of occurrence of critical heat flux (CHF) and providing increased surface heat transfer. This report presents the results of three series of light water reactor fuel behavior tests (Thermocouple Effects Test Series TC-1, TC-3, and TC-4) that were performed in the Power Burst Facility to specifically evaluate the influence of cladding surface thermocouples on the thermal behavior of nuclear fuel rods under LOCA conditions. Twelve tests were performed in the three test series. Differences between tests included variations in system thermal-hydraulic conditions and in the initial test rod power level, as well as differences in design of the internal cladding thermocouples.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5337495
- Report Number(s):
- NUREG/CR-2665; EGG-2190; ON: DE82018832
- Country of Publication:
- United States
- Language:
- English
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ACCIDENTS
ACCURACY
BWR TYPE REACTORS
CALIBRATION
FUEL CANS
IN PILE LOOPS
LOSS OF COOLANT
MEASURING INSTRUMENTS
PBF REACTOR
PERFORMANCE
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REACTOR SAFETY
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SIMULATION
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
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THERMOCOUPLES
WATER COOLED REACTORS
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