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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
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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)