Assessment of LOFT fuel rod quench behavior based on electric rod quench tests

Conference · Tue Jan 01 04:00:00 EST 1980

OSTI ID:6257855

Gottula, R C; Carboneau, M L; Tolman, E L

Measurements from fuel rod cladding external surface thermocouples indicated unexpected cladding quench early in the blowdown of the Loss-of-Fluid Test (LOFT) large break loss-of-coolant experiments. Swaged and cartridge type electrically heated fuel rod simulators are being used to evaluate the effects, if any, of cladding surface thermocouples on quench behavior, and to determine the accuracy of the cladding surface. Preliminary tests conducted on a single, swaged heater rod over a wide range of flooding conditions indicate that cladding external thermocouples increase the cooldown rate and reduce the time-to-quench on that type of rod. The results of the heater rod tests are being used to reassess the fuel rod cladding temperature response during the LOFT L2-2 and L2-3 tests as measured by the cladding surface thermocouples.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6257855
• Report Number(s): CONF-801091-4; ON: TI85004892
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACCIDENTS
CLADDING
DEPOSITION
FUEL ELEMENTS
FUEL RODS
GRAPHS
LOFT REACTOR
LOSS OF COOLANT
MEASURING INSTRUMENTS
PWR TYPE REACTORS
QUENCHING
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SURFACE COATING
TABLES
TANK TYPE REACTORS
TEST REACTORS
THERMOCOUPLES
WATER COOLED REACTORS
WATER MODERATED REACTORS