Catalog Record: Transient temperature analysis of the fuel loader push rod and guide tube in the ultra high temperature reactor experiment (UHTREX) | HathiTrust Digital Library

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Transient temperature analysis of the fuel loader push rod and guide tube in the ultra high temperature reactor experiment (UHTREX) /
by C.H. Treat.

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Main Author: Treat, C. H.
Language(s): English
Published: Los Alamos, N.M. : Los Alamos Scientific Laboratory of the University of California, 1965.
Subjects: Nuclear fuel elements > Nuclear fuel elements / Thermal properties.
High temperatures.
Heat > Heat / Radiation and absorption.
Note: "Contract W-7405-ENG.36 with the U.S. Atomic Energy Commission."
"LA-3174-MS ; UC-80, Reactor Technology ; TID-4500 (35th Ed.)."
"Report written: September 1964 ; Report distributed: January 22, 1965."
Physical Description: 24 p. : ill. ; 28 cm.
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