| 摘要 |
A computer implemented method for modelizing a nuclear reactor core, including the steps of: partitioning the core in cubes to constitute nodes of a grid for computer implemented calculation, calculating neutron flux by using an iterative solving procedure of at least one eigensystem, the components of an iterant of the eigensystem corresponding either to a neutron flux, to a neutron outcurrent or to a neutron incurrent, for a respective cube to be calculated. The neutrons are sorted in a plurality of neutron energy groups, and the eigensystem iterative solving procedure includes a substep of conditioning the eigensystem into a restricted eigensystem corresponding to the eigensystem for a selection of some neutron energy groups.
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