Effects of cladding external thermocouples and electrical-heater-rod design on quench behavior

Conference · Sat Jan 01 04:00:00 EST 1983

OSTI ID:6635281

Gottula, R C; Tolman, E L

Separate effects experiments were conducted on a bundle of nine electrical heater rods in te Loss-of-Fluid Test (LOFT) Test Support Facility (LTSF) at the Idaho National Engineering Laboratory (INEL). The objectives of these experiments were to evaluate the effects of cladding external thermocouples on the quench (cooling) behavior of a cartridge-type nuclear fuel rod simulator, to determine ow accurately cladding external thermocouples measure cladding temperature during a high-pressure quench, and to compare the quench behavior of a cartridge-type heater rod (which simulates a fuel-pellet-cladding gap) with that of a solid-type heater rod (without a fuel-pellet-cladding gap) under thermal-hydraulic conditions that could occur during the blowdown phase (0 to 10 s) of a large break loss-of-coolant accident in a pressurized water reactor. The results of the experiments are presented.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6635281
• Report Number(s): EGG-M-06982; CONF-830103-33; ON: DE83006330
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900 -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACCURACY
ENERGY TRANSFER
FUEL CANS
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
HEATERS
LOFT REACTOR
LOSS OF COOLANT
MEASURING INSTRUMENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST FACILITIES
TEST REACTORS
THERMOCOUPLES
WATER COOLED REACTORS
WATER MODERATED REACTORS