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“Bleaching” of uranium-graphite fuel for pulse graphite reactors
“Bleaching” of uranium-graphite fuel for pulse graphite reactors
1998
N.V. Gorin
Ya. Z. Kandiev
R. M. Kozybaev
V. I. Litvin
G. N. Malyshkin
S. I. Samarin
V. M. Shmakov
A. P. Vasilev
V. A. Gaidaichuk
Yu. M. Kaz'min
V. A. Pakhnits
A. S. Skivka
Keywords:
Radiochemistry
Nuclear chemistry
Neutron temperature
Nuclear reactor
Pulse (signal processing)
Graphite
Chemistry
Uranium
Correction
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