LOFT Experimental Support Branch data report for LOFT fuel rod thermocouple calibration test rod IH-8029-1

Technical Report · Mon Sep 25 04:00:00 EDT 1978

OSTI ID:6786607

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

LOFT thermocouple response data are presented from the first zircaloy clad heater rod tests conducted in the Blowdown Facility which were intended to simulate coolant and cladding temperature conditions expected during the LOFT loss-of-coolant experiments. Comparison is made to previous stainless steel clad heater rod tests and discussion of the application of these results for correcting LOFT cladding temperature measurements is presented.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 6786607
• Report Number(s): LTR-141-87
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
CALIBRATION
FUEL ELEMENTS
LOFT REACTOR
MEASURING INSTRUMENTS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SIMULATION
TANK TYPE REACTORS
TEMPERATURE DISTRIBUTION
TEST REACTORS
THERMOCOUPLES
WATER COOLED REACTORS
WATER MODERATED REACTORS