1966
DOI: 10.3327/jnst.3.209
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A Method for the Numerical Integration of the Neutron Transport Equation in Slab Geometry

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1968
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“…(2) The neutron spectra within and behind material are obtained. (3) The angular distributions and energy spectra of neutrons within and behind multi-layered slabs can be calculated. (4) The method can effectively calculate neutron problems pertaining to sources presenting ariy given angular distribution.…”
Section: Discussionmentioning
confidence: 99%
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“…(2) The neutron spectra within and behind material are obtained. (3) The angular distributions and energy spectra of neutrons within and behind multi-layered slabs can be calculated. (4) The method can effectively calculate neutron problems pertaining to sources presenting ariy given angular distribution.…”
Section: Discussionmentioning
confidence: 99%
“…(2) The distribution function f(E, f.k) is allowed to be approximated by a step function with respect to L1E. (3) The slowing down kernel g(E', E) is represented by the two forms written below(7), one of which is a simple continuous function for a continuous spectrum in the distribution of energy level of the nucleus, and the other is a sum of o functions for discrete levels:…”
Section: Calculation Of Scattering Integralsmentioning
confidence: 99%