LOFT experimental support branch data abstract report: LOFT fuel rod thermocouple calibration test rod RRF-A-88102

Technical Report · Wed Apr 25 04:00:00 EST 1979

DOI:https://doi.org/10.2172/5475193· OSTI ID:5475193

Solbrig, C. W.; Tolman, E. L.; Selcho, H. S.

This report presents the comparison between LOFT type thermocouples (surface mounted) and embedded thermocouples placed in comparable locations on stainless steel clad electrically heated rod. The experiments performed on this rod simulated a hot leg break loss-of-coolant accident (LOCA) with the rods at a high steady state power level. The maximum steady state linear heat generation rate (MLHGR) was 19 kW/ft and the peak cladding temperatures ranged from 1200 to 1600/sup 0/F, thus these experiments are representative of high power LOCA conditions. The purpose of the test was to determine the difference in temperature measured by the two types of thermocouples and from this to infer how well the LOFT thermocouple measures the surface temperature of a nuclear rod.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 5475193
• Report Number(s): EGG/LTR-141-100
• Country of Publication: United States
• Language: English

Related Subjects

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