2200/sup 0/C thermocouples for nuclear-reactor-fuel centerline-temperature measurements

Conference · Fri Jan 01 04:00:00 EST 1982

OSTI ID:5235763

Cannon, C P

Thermocouples capable of operation at temperatures to 2200/sup 0/C have been fabricated to measure reactor fuel centerline temperatures in Loss-of-Fluid-Tests and Severe Fuel Damage tests conducted for the Nuclear Regulatory Commission. The technology and commercial suppliers have been developed for three basic thermocouple designs. Rhenium and Mo48%/Re are used as sheath materials and HfO/sub 2/ and BeO are used as insulator materials. Laboratory qualification tests were performed including long term tests of up to 1000 hours at 2200/sup 0/C on the Re/HfO/sub 2/ design. The thermocouples are 1.57 mm 0.D., 76 cm to 104 cm length and contain 0.25 mm O.D. W5%Re/W26%Re thermoelement wires. Thermocouples probes are spliced to stainless steel sheathed, compensating lead cables. Some of the thermocouple designs contain a small diameter ceramic-to-metal gas seal in the transition region between the thermocouples and the compensating lead cable.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 5235763
• Report Number(s): HEDL-SA-2639-FP; CONF-820306-10; ON: DE82014186
• 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
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CALIBRATION
LOFT REACTOR
MEASURING INSTRUMENTS
PWR TYPE REACTORS
REACTORS
RESEARCH AND TEST REACTORS
SPECIFICATIONS
TANK TYPE REACTORS
TEST REACTORS
THERMOCOUPLES
WATER COOLED REACTORS
WATER MODERATED REACTORS