| 摘要 |
PROBLEM TO BE SOLVED: To solve the problem that a nuclear constant used in reactor core calculation is created for each fuel assembly, and a change in spatial distribution and energy distribution of a neuron flux caused by adjacent fuel assemblies of different kinds is not taken into consideration. SOLUTION: At least, the fission cross section, a capture cross section and a generation cross section of a thermal group are corrected by using a nuclear reaction rate, nuclear constant correction database or the like in a fuel assembly. Thus, a change in spatial distribution and energy distribution of a neuron flux caused by adjacent fuel assemblies is taken in the nuclear constant so as to effect a reactor core performance calculating apparatus improved in effective multiplication factor obtained by three-dimensional reactor core nuclear hydrothermal force calculating and analysis accuracy such as output distribution.
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