The most general equations for multigroup neutron diffusion in P1 approximation
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Date
1962
Authors
Journal Title
Journal ISSN
Volume Title
Publisher
T.A.E.C. Çekmece Nuclear Research Center
Abstract
Starting from the general transport equation and within the limits of P1 approximation, a set of coupled second order partial integro-differential equations is obtained. These equations consider the effect of m groups of retarded neutrons and contain both the first and the second derivatives of the neutron fluxes with respect to the time variable.
Description
TENMAK D.N.. 10304
Keywords
Neutrons, Nötronlar, Neutron diffusion, Nötron difüzyonu
Citation
Şuhubi, E. ve Özemre, A. Y. (1962).The most general equations for multigroup neutron diffusion in P1 approximation. İstanbul : T.A.E.C. Çekmece Nuclear Research Center.