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Abstract

A calculation method of nuclear reactor core on neutronic characteristics and thermal hydraulic characteristics is provided, which is capable of getting an equivalent calculation precision to a heterogeneous core calculation by a coarse mesh core calculation thereby achieving curtailment and reduction of calculation time and memory capacity. It comprises conducting both a coarse mesh core calculation based on fuel assembly cross section tables including homogeneous fuel assembly cross sections and discontinuity factors at fuel assemblies boundaries and a heterogeneous core calculation on the premise of the same core conditions as in the aforesaid calculation; comparing two calculation results so obtained with each other to derive correction factors to the homogeneous cross sections and the discontinuity factors; and further conducting another coarse mesh core calculation using these correction factors to get final calculation results equivalent in precision to ones obtainable from a heterogeneous core calculation method at high speed.

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