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