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
- Country of Publication:
- United States
- Language:
- English
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2200/sup 0/C fuel centerline thermocouples for the LOFT program
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220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
COMPATIBILITY
LOFT REACTOR
MEASURING INSTRUMENTS
PERFORMANCE TESTING
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REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
TESTING
THERMOCOUPLES
WATER COOLED REACTORS
WATER MODERATED REACTORS