A GROUP CONSTANT GENERATION METHOD USING STOCHASTIC THEORY OF NEUTRON TRANSPORT AND A GROUP CONSTANT GENERATION DEVICE

摘要

The present invention relates to a method and apparatus for generating multi-group group constants that reduce errors due to multi-group approximation while processing complexity due to various geometrical structure modeling by using a Monte Carlo code using continuous energy for calculation of multi-group group constants. Estimating an average neutron flux for each of the plurality of regions and the plurality of energy groups in the core using nuclear data; estimating an intrinsic reaction rate by multiplying the estimated flux by the cross-sectional area of interest; And generating a multi-group nuclear cross-sectional area for each reaction type and energy group based on the intrinsic reaction rate.