| 摘要 |
PROBLEM TO BE SOLVED: To provide a nuclear constant preparation method for nuclear fuel for preparing a small-number group constant, using a continuous-energy Monte Carlo method, a reactor core design method using the method, a nuclear constant preparing device for the nuclear fuel, and to provide a reactor core design system that uses the device. SOLUTION: Neutrons are generated simulatedly by a random number, using neutron transport calculation, using, as input information, geometrical arrangement in a calculation system, a constituting substances, the cross-sectional area of the constitutive substance, marked area and neutron energy group classified into a multigroup. A reaction rate in the marked area is calculated, by multiplying a neutron flux with a neutron reaction cross-sectional area, and an energy multigroup reaction rate in the marked area is calculated by classification into the energy groups, in response to energy levels to be collected. A multigroup differential scattering cross-sectional area, that is the probability of transition from the energy group before scattering to the energy group after the scattering, is calculated, by dividing the weight of the neutrons collected in an energy two-dimensional array with a collected energy multigroup neutron flux corresponding to the energy group after scattering. COPYRIGHT: (C)2006,JPO&NCIPI
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