Computer Implemented Method for Modelizing a Nuclear Reactor Core and a Corresponding Computer Program Product

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.A control parameter is varied to impact a neutron eigenvalue μ through a perturbed interface current equation and drive the neutron eigenvalue μ towards 1.