LOFT cladding surface thermocouple calibration test results for stainless steel clad rod RRF-A-88107

Technical Report · Tue Jan 16 04:00:00 EST 1979

OSTI ID:6158977

Eaton, A M; Tolman, B L; Solbrig, C W

LOFT thermocouple response data are presented for the stainless steel clad electrical heater rod RRF-A-88107. Tests were conducted in the LOFT Test Support Facility and were intended to simulate coolant and cladding temperature conditions expected during the LOFT loss-of-coolant experiments. Comparisons are made with previously obtained stainless steel and Zircaloy clad heater rod data. Differences in thermocouple behavior between previously tested stainless steel and Zircaloy clad heater rods are discussed. It is recommended that the stainless steel clad heater rod test data not be used to correct or characterize the measurement of the cladding surface temperature of a nuclear fuel rod by the LOFT surface thermocouple.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 6158977
• Report Number(s): LTR-141-89
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
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ACCIDENTS
CALIBRATION
FUEL CANS
HEATERS
LOFT REACTOR
LOSS OF COOLANT
MEASURING INSTRUMENTS
PERFORMANCE TESTING
PWR TYPE REACTORS
REACTOR ACCIDENTS
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TEMPERATURE GRADIENTS
TEMPERATURE MEASUREMENT
TEST REACTORS
TESTING
THERMOCOUPLES
WATER COOLED REACTORS
WATER MODERATED REACTORS