Three-dimensional quasi-transport acceleration method for uniform geometric variational nodal method

Abstract

The invention discloses a three-dimensional quasi-transport acceleration method for a uniform geometric variation nodal method. An axial and radial cross derivative term in a second-order even-space neutron transport equation is eliminated through quasi-transport approximation processing; considering that in an actual pressurized water reactor, axial non-uniformity is weak, in a Ritz discrete process, diffusion approximation is adopted for angular distribution of odd neutron angular flux density on an axial surface; in the Ritz discrete process, the number of odd neutron angular flux density angle basis functions of a radial surface is reduced by using the symmetry of the angle space. According to the method, the calculation efficiency can be greatly improved and the calculation memory can be reduced under the condition that the calculation precision is not obviously influenced, so that the method is used for accurate and efficient neutronics simulation in nuclear reactor design.

Description

technical field [0001] The invention relates to a technology in the field of nuclear engineering, in particular to a three-dimensional quasi-transport acceleration method for the uniform geometric variational segmental method. Background technique [0002] In reactor design, in order to analyze the neutronics performance and safety of the reactor, accurate and efficient neutronics simulation of the reactor is required to obtain the effective multiplication coefficient of the reactor and the neutron flux density distribution in the reactor. The effective multiplication coefficient and neutron flux density are obtained by solving the neutron transport equation. At present, the widely used method for solving the neutron transport equation is the variational segment method, which divides the reactor area into a series of typical segments , by constructing the corresponding response matrix for typical nodes and completing the solution of the response matrix equation, the effectiv...

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Problems solved by technology

[0003] Aiming at the problem of high computational cost of the existing uniform geometric variational nodal method in large-scale reactor three-dimensional neutronics simulation, the present invention proposes a three-dimensional quasi-transport acceleration method for the uniform geometrical variational nodal method, which can be used without Significantly improve computational efficiency and reduce computational memory with significant impact on computational accuracy for accurate and efficient neutronics simulations in nuclear reactor design

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