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Neutron flux distributions in the materials testing reactor.
Part III,
Fuel burnout in the 3 x 9 loading /
by G.O. Bright.



Main Author: Bright, G. O.
Language(s): English
Published: Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service, 1955.
Subjects: Nuclear fuel elements.
Neutron flux > Neutron flux / Measurement.
Nuclear reactors > Nuclear reactors / Measurement.
Materials testing reactors.
Note: Work performed at the Atomic Energy Division, Phillips Petroleum Company, Idaho Falls, Idaho.
"Date Declassified: October 5, 1955."
"July 27, 1954."
Physical Description: 48 p. : ill. ; 26 cm.
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