Catalog Record: Washout testing of mixed oxide ceramic core fuel elements | HathiTrust Digital Library

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Washout testing of mixed oxide ceramic core fuel elements /
K. D. Hayden.

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Main Author: Hayden, K. D.,
Language(s): English
Published: Richland, Washington : Pacific Northwest Laboratory, 1966.
Subjects: Nuclear fuel elements.
Mixed oxide fuels (Nuclear engineering).
Note: "UC-25, Metals, Ceramics and Materials."
"October 1966."
Physical Description: ii, 14 pages : illustrations ; 28 cm.
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