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The fast multiplication effect of beryllium oxide in reactors
The twenty grand program for the numerical solution of few-group neutron diffusion equations in two dimensions
Calculation of fission-source thermal-neutron distribution in water by the transfusion method
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Published Year
1960-1969 (3) *
Subject
Neutron transport theory (3) *
Beryllium oxide (1)
Neutron cross sections (1)
Neutron diffusion theory (1)
Neutron flux (1)
Nuclear fission (1)
Nuclear reactors--Reactivity (1)
Reactor moderators (1)
Thermal neutrons (1)
Author
Fowler, T. B. (1)
H©·afele, W. (1)
Tobias, M. L. (1)
Trubey, D. K. (1)
Tsagaris, Marina. (1)