Catalog Record: Comparison of flux and power distributions, and void and temperature coefficients of the MTR with U²³⁵ and Pu²³⁹ fuel | HathiTrust Digital Library

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Comparison of flux and power distributions, and void and temperature coefficients of the MTR with U²³⁵ and Pu²³⁹ fuel /
by B.W. Johnson and H.L. McMurry.

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Main Author: Johnson, B. W.
Related Names: McMurry, H. L.
Language(s): English
Published: [Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1957].
Subjects: Heat flux.
Plutonium as fuel.
Uranium as fuel.
Materials testing reactors.
Note: "Reactors ; (TID-4500, 13th Ed.)"--Cover.
"July 26, 1957"--Cover.
Caption title.
Physical Description: 29 p. : ill. ; 28 cm.
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