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Fuel-cladding compatibility of stainless steels with gas and sodium bonded uranium plutonium carbide fuels

O. Goetzmann, +1 more
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The article was published on 1972-01-01 and is currently open access. It has received 2 citations till now. The article focuses on the topics: Carbide & Uranium.

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Journal ArticleDOI

Development and Fabrication of 70% PuC–30% UC Fuel for the Fast Breeder Test Reactor in India

TL;DR: Mixed uranium-plutonium monocarbide with a controlled amount of mixed sesquicarbide (M2C3) was used as driver fuel for the first time in the world in the fast breeder test reactor (FBTR) as discussed by the authors.
Journal ArticleDOI

Fabrication, characterization and property evaluation of mixed carbide fuels for a test Fast Breeder Reactor

TL;DR: The Fast Breeder Test Reactor (FBTR) at Kalpakkam, India is operating successfully since October 1985 with high plutonium content hyperstoichiometic mixed carbide as driver fuel as discussed by the authors.