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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

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)

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