Material compatibility tests for LOFT nuclear reactor fuel centerline thermocouples
Description
High-temperature (22000C) 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 (ThO2) and hafnia (HfO2) 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 22000C, pressures up to 17.2 MPa and neutron fluences of 7.2 x 1019 nvt
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A04/MF A01.
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Additional details
Publishing Information
- Imprint Pagination
- 70 p.
- Report number
- NUREG/CR--0643
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10480719
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPATIBILITY; LOFT REACTOR; PERFORMANCE TESTING; REACTOR MATERIALS; THERMOCOUPLES
- Descriptors DEC
- MEASURING INSTRUMENTS; PWR TYPE REACTORS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; TEST REACTORS; TESTING; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- HEDL-TME--78-75.