Miniature Zircaloy-sheathed fuel rod cladding surface thermocouples. Progress report
Technical Report
·
OSTI ID:6223378
Tungsten--rhenium alloy thermocouples with 0.71-mm diameter Zircaloy sheaths have been fabricated and tested. These thermocouples are intended for cladding surface temperature measurements on nuclear fuel rods, with the goal of minimizing the measurement perturbation through miniaturization of the instruments. Design and fabrication details and laboratory test results are included.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6223378
- Report Number(s):
- TFBP-TR-286
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
440300 -- Miscellaneous Instruments-- (-1989)
47 OTHER INSTRUMENTATION
ALLOYS
DESIGN
FABRICATION
FUEL CANS
MEASURING INSTRUMENTS
PWR TYPE REACTORS
REACTORS
RHENIUM ALLOYS
TEMPERATURE MEASUREMENT
THERMOCOUPLES
TIN ALLOYS
TUNGSTEN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
440300 -- Miscellaneous Instruments-- (-1989)
47 OTHER INSTRUMENTATION
ALLOYS
DESIGN
FABRICATION
FUEL CANS
MEASURING INSTRUMENTS
PWR TYPE REACTORS
REACTORS
RHENIUM ALLOYS
TEMPERATURE MEASUREMENT
THERMOCOUPLES
TIN ALLOYS
TUNGSTEN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS