NASA NTRS · 19720052498
Material development for thermionic fuel-cladding systems.
Abstract
Fuel-cladding systems capable of maintaining stable dimension and electron emission characteristics at high temperatures under irradiation are essential to the successful operation of nuclear thermionic power sources. Studies regarding two possible systems, involving tungsten clad uranium carbide and uranium oxide, are considered. Out-of-pile developmental efforts and the in-pile evaluation results for the two systems are described. Prototypical emitters have been tested for 8000 hours for the carbide system and 4000 hours for the oxide system.
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Yang, L., Hudson, R. G., Johnson, H., Horner, H., Allen, D. T.. 1972-06-01. Material development for thermionic fuel-cladding systems.. https://ntrs.nasa.gov/citations/19720052498
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