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Stainless steel university reactor

Calculations of neutron age in H₂O and other materials

The nucleon transport code, NTC

Program STATEST :an application of the method of statistical estimation to the calculation of neutron flux in anisotropically scattering media by Monte Carlo

Published Year

• 1950-1959 (1)
• 1960-1969 (3)

Subject

• Monte Carlo method--Computer programs (1)
• Neutron flux (1)
• Neutrons (1)
• Neutrons--Scattering (1)
• Nuclear fuels--Measurement--Mathematical models (1)
• Nuclear reactions (1)
• Scattering (Physics) (1)
• Stainless steel (1)
• Swimming pool reactors (1)

Author

• Kinney, W. E. (4) *
• Bate, R. R. (1)
• Coveyou, R. R. (1)
• Goldstein, H. (1)
• Sullivan, J. G. (1)

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