Abstract
A procedure for developing neutron coupling coefficients for power-distribution calculations in LWRs using nodal analysis is described. The coefficients account for the fast and thermal flux variation within each node or fuel assembly by utilizing a 1-D diffusion-theory analysis of the flux ‘modes’ within the nodal volume. The procedure utilizes the fact that the fuel assemblies in most LWRs are arranged in such a manner that the reactor volume consists of a large number of neutronically self-sustaining zones. The paper provides both a physical and an analytical justification for the evaluation of neutron coupling coefficients in two energy groups.
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