Evaluation of refractory-metal-clad uranium nitride and uranium dioxide fuel pins after irradiation for times up to 10,450 hours at 990/sup 0/C. [Lithium cooled space power reactor]
Technical Report
·
OSTI ID:7149607
The effects of some materials variables on the irradiation performance of fuel pins for a lithium-cooled space power reactor design concept were examined. The variables studied were UN fuel density, fuel composition, and cladding alloy. All pins were irradiated at about 990/sup 0/C in a thermal neutron environment to the design fuel burnup. An 85-percent dense UN fuel gave the best overall results in meeting the operational goals. The T-111 cladding on all specimens was embrittled, possibly by hydrogen in the case of the UN fuel and by uranium and oxygen in the case of the UO/sub 2/ fuel. Tests with Cb-1Zr cladding indicate potential use of this cladding material. The UO/sub 2/ fueled specimens met the operational goals of less than 1 percent cladding strain, but other factors make UO/sub 2/ less attractive than low-density UN for the contemplated space power reactor use. (Auth)
- Research Organization:
- National Aeronautics and Space Administration, Cleveland, Ohio (USA). Lewis Research Center
- OSTI ID:
- 7149607
- Report Number(s):
- N-75-24843; NASA-TN-D-7891; E-7988
- Country of Publication:
- United States
- Language:
- English
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NESDPS Office of Nuclear Energy Space and Defense Power Systems
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OXYGEN COMPOUNDS
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SPACE POWER REACTORS
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URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM NITRIDES
URANIUM OXIDES