Nuclear Science and Engineering / Volume 38 / Number 2 / November 1969 / Pages 114-124
Technical Paper / dx.doi.org/10.13182/NSE69-A19515
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Three methods are presented for calculating the multiplication of the delayed-neutron response which occurs in far-subcritical samples of fissionable material irradiated by an external neutron source: a three-energy group analytic expression; the zero prompt-lifetime approximation in conjunction with a one-dimensional steady-state transport theory code; and a three-dimensional time-dependent Monte Carlo code. The accuracy and limitations of the calculational techniques are demonstrated by a comparison with experimental measurements.