Material compatibility tests for LOFT nuclear reactor fuel centerline thermocouples
High-temperature (2200/sup 0/C) compatibilty tests were conducted at the Hanford Engineering Development Laboratory (HEDL) to select proper materials for commercial fabrication of fuel centerline thermocouples for Loss of Fluid Test (LOFT) reactor use. Materials investigated include the following: (a) beryllia (BeO), thoria (ThO/sub 2/) and hafnia (HfO/sub 2/) insulators, (b) molybdenum 48% rhenium (Mo48Re), tungsten 22% rhenium (W22Re), rhenium (Re), and rhenium/tungsten-augmented (Re/W-augmented) sheaths; (c) tungsten 3% rhenium versus tungsten 25% rhenium (W3Re/ W25Re) and tungsten 5% rhenium versus tungsten 26% rhenium (W5Re/W26Re) thermoelectric wires. Candidate materials had to withstand temperatures of up to 2200/sup 0/C, pressures up to 17.2 MPa and neutron fluences of 7.2 x 10/sup 19/ nvt.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- OSTI ID:
- 6126500
- Report Number(s):
- NUREG/CR-0643; HEDL-TME-78-75; TRN: 79-012239
- Country of Publication:
- United States
- Language:
- English
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2200/sup 0/C fuel centerline thermocouples for the LOFT program
RESEARCH AND EVALUATION OF MATERIALS FOR THERMOCOUPLE APPLICATION SUITABLE FOR TEMPERATURE MEASUREMENTS UP TO 4500F ON THE SURFACE OF GLIDE RE-ENTRY VEHICLES
Related Subjects
LOFT REACTOR
REACTOR MATERIALS
THERMOCOUPLES
COMPATIBILITY
PERFORMANCE TESTING
MEASURING INSTRUMENTS
PWR TYPE REACTORS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors