Catalog Record: Oxidation-reduction reprocessing of uranium carbide reactor fuel. II, Behavior of plutonium and fission products | HathiTrust Digital Library

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Oxidation-reduction reprocessing of uranium carbide reactor fuel.
II,
Behavior of plutonium and fission products /
by W.G. Smiley.

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Main Author: Smiley, W. G.
Language(s): English
Published: Canoga Park, California : Atomics International, [1965]
Subjects: Reduction (Chemistry)
Plutonium.
Nuclear fuels.
Fission products.
Reduction (Chemistry)
Fission products.
Plutonium.
Nuclear fuels.
Note: "NAA-SR-10738 ; Metals, Ceramics, and Materials."
"Contract AT(11-1)-GEN-8 ; Issued: Jun 15 1965."
Physical Description: 35 pages : illustrations ; 28 cm.
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