Catalog Record: Development and properties of coextruded zircaloy-clad uranium fuel elements with integral end seals | HathiTrust Digital Library

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Development and properties of coextruded zircaloy-clad uranium fuel elements with integral end seals /
by H. F. Sawyer.

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Main Author: Sawyer, H. F.
Language(s): English
Published: Oak Ridge, Tennessee : United States Atomic Energy Commission, Office of Technical Information, 1958.
Subjects: Zircaloy-2.
Nuclear fuel claddings.
Extrusion process.
Extrusion process.
Nuclear fuel claddings.
Zircaloy-2.
Note: "Contract no. AT(30-1)-1565."
"November 6, 1958."
"Nuclear Metals, Inc., Concord, Massachusetts."
"NMI-4710 ; Metallurgy and Ceramics."
Physical Description: 83 pages : illustrated ; 27 cm.
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