Catalog Record: Prediction of the critical heat flux in forced convection flow | HathiTrust Digital Library

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Prediction of the critical heat flux in forced convection flow /
by S. Levy.

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Main Author: Levy, S.
Language(s): English
Published: Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1962.
Subjects: Two-phase flow.
Heat > Heat / Transmission.
Boiling water reactors.
Boiling water reactors.
Heat > Heat / Transmission.
Two-phase flow.
Note: Work performed at the General Electric Company, Atomic Power Equipment Department, San Jose, California.
"GEAP-3961; Engineering and Equipment."
"June 20, 1962."
Physical Description: 27 pages : illustrations (some folded) ; 28 cm.
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