Abstract
An analytical procedure for calculating the 3-D power distribution in LWRs based on two-group coarse-mesh nodal analysis is described. The use of source-sink analysis of the fast-neutron source distribution yields a very efficient eigenvalue equation. Neutron coupling between nodes is evaluated using a modal analysis of the neutron-source shape within each node based on the multiplication and transport properties of the source node and its immediate neighbors. Both the core and fuel-assembly geometry and the neutronic characteristics of LWRs are particularly well suited to this type of analysis.
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