Generalized matrix separation acceleration method aiming at non-uniform geometrical variational nodal method

Abstract

The invention discloses a generalized matrix separation acceleration method aiming at a non-uniform geometrical variational nodal method. The generalized matrix separation acceleration method comprises the following steps: 1, decomposing a response matrix equation characterizing a nodal surface neutron current relationship into contribution superposition of six nodal surfaces; 2, deducing the response matrix equation into a form of adding a low-order response matrix related to mean partial current density of each surface by a correction source item; 3, establishing an iterative scheme between emergent and incident partial neutron currents, and performing iterative solution by utilizing a general iterative method. According to the generalized matrix separation acceleration method disclosed by the invention, the applicability of a matrix separation acceleration algorithm is improved, the mean partial neutron current density expansion moment on the axial surface is converged in the iterative process, a component of each partial neutron current density expansion moment is converged, and the calculation efficiency of the non-uniform geometrical variational nodal method can be effectively accelerated.

Description

technical field [0001] Aiming at the field of nuclear reactor core neutronics calculation, the invention proposes a generalized matrix separation acceleration method aiming at the non-uniform geometric variational segment method. Background technique [0002] Computational studies of nuclear reactor neutronics are applied to nuclear reactor cores, which consist of many different types of components. Depending on the stack type, the geometry and material arrangement inside the module is complex and variable. Therefore, the actual reactor neutronics problem is a three-dimensional non-uniform geometry neutronics problem. Fast and accurate neutronics calculations for nuclear reactors are the basic guarantee for reactor design and calibration. At present, in the process of core physical design, the method of solving the diffusion equation of uniform geometry is mainly used. [0003] The variational segmental method is one of the commonly used methods in the physical design of ...

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Problems solved by technology

[0006] However, the traditional matrix separation algorithm is only for the variational nodal method in the case of uniform nodal

The non-uniform variational nodal method uses slice constants on the axial surface of the nodule and orthogonal polynomials on the radial surface for spatial discretization. Compared with the traditional variational nodal method, the traditional matrix separation algorithm has particularity. Unable to apply to non-uniform geometric variational nodal method

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