Computer implemented method for modelizing a nuclear reactor core and a corresponding computer program product

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.;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.

主权项

1. A computer implemented method for modelizing a nuclear reactor core, comprising the steps of:
partitioning, by a computer processor, the core in cubes to constitute nodes of a grid for computer implemented calculation, calculating, by the computer processor, neutron flux by using an iterative solving procedure of at least one eigensystem, 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,wherein 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,the perturbed interface current equation being defined byjout+δ⁢⁢jout=(μ+δ⁢⁢μ)⁢c1⁡(ϕ+δϑ⁢∂ϕ∂ϑ)+Ω^⁢Y^⁡(jout+δ⁢⁢jout)where jout designates the neutron outcurrent, Φ designates the neutron flux, θ designates the control parameter, Ŷ is a coupling operator, {circumflex over (Ω)} is a mono-directional current throughflow operator, and c1 is an operator depending on the cube properties, the control parameter being a parameter of the model representing a feature of the nuclear reactor core.