Catalog Record: An empirical prediction of temperature gradients in moderator graphite within operating nuclear reactors | HathiTrust Digital Library

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An empirical prediction of temperature gradients in moderator graphite within operating nuclear reactors /
by Robert L. Carter.

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Main Author: Carter, Robert L.
Language(s): English
Published: Canoga Park, California : Atomics International, [1962]
Subjects: Sodium graphite reactors.
Graphite > Graphite / Thermal properties.
Sodium graphite reactors.
Graphite > Graphite / Thermal properties.
Note: "NAA-SR-6616 ; Reactor technology."
"Contract AT(11-1)-GEN-8 ; Issued: Feb 15 1962."
Physical Description: vi, 44 pages : illustrations ; 28 cm.
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