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Behavior of metallic uranium-fissium fuel in TREAT transient overpower tests
Behavior of metallic uranium-fissium fuel in TREAT transient overpower tests
1986
T.H. Bauer
A. E. Klickman
R. K. Lo
E. A. Rhodes
W.R. Robinson
G.S. Stanford
A.E. Wright
Keywords:
Thermal expansion
Power density
Nuclear engineering
Nuclear reactor
Materials science
Metal
Uranium
Correction
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