Calculation of Three-Dimensional Flux Distributions in CANDU Reactors Using Lattice Properties Dependent on Several Local Parameters

A refinement is proposed to the current method of evaluating lattice properties for use in calculations of Canada deuterium uranium flux distributions. This refinement, labeled the local-parameter calculation, takes into account locally appropriate values of coolant density, fuel temperature, and flux/power level where core average values were previously used. The local-parameter calculation has been implemented and tested. Results are compared to those of previous calculations and of independent methods based on in-core measurements.