Catalog Record: Calculation and measurement of the transient temperature in a low-enrichment UO₂ fuel rod during large power excursions | HathiTrust Digital Library

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Calculation and measurement of the transient temperature in a low-enrichment UO₂ fuel rod during large power excursions /
by J.E. Houghtaling, T.M. Quigley and A.H. Spano.

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Main Author: Houghtaling, J. E.
Related Names: Spano, A. H. , Quigley, T. M.
Language(s): English
Published: [Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1962.
Subjects: Heat > Heat / Transmission > Heat / Transmission / Measurement.
Uranium oxides.
Nuclear fuels.
Nuclear fuel elements > Nuclear fuel elements / Thermal properties.
Nuclear fuel elements > Nuclear fuel elements / Testing.
Note: At head of title: SPERT.
"National Reactor Testing Station"--Cover.
"Reactor Technology ; TID-4500 (17th Ed.)."
"Issued: May 18, 1962."
Physical Description: vii, 25 p. : ill. ; 28 cm.
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