Method for accelerating solving of generalized conjugate neutron transport equation

Abstract

The invention relates to the technical field of nuclear reactor cores, and particularly discloses a method for accelerating solving of a generalized conjugate neutron transport equation. The method comprises the following steps: respectively solving a neutron transport equation and a conjugate neutron transport equation by utilizing a characteristic line method, and respectively obtaining corresponding neutron flux distribution; calculating to obtain a source item of the generalized conjugate equation according to a response which specifically needs to be solved, and constructing a generalizedconjugate neutron transport equation; constructing a fixed source solver to solve a generalized conjugate neutron transport equation; and solving to obtain a generalized conjugate neutron transport equation. According to the method, the solving accuracy of the generalized conjugate neutron transport equation is ensured through characteristic line scanning, and the high efficiency of the generalized conjugate neutron transport equation is ensured through coarse net finite difference acceleration; when the method is used for solving the sensitivity coefficient of physical parameters such as thereaction rate ratio and the average fission power of the reactor to nuclear data, the calculation time can be remarkably shortened, and the efficiency is improved.

Description

technical field [0001] The invention belongs to the technical field of nuclear reactor cores, in particular to a method for accelerating the solution of generalized conjugate neutron transport equations. Background technique [0002] Reactor design is a system engineering that integrates reactor nuclear design, thermal hydraulic design, and system equipment design, and there are inevitably uncertainties. The calculation uncertainty of the core comes from the uncertainty of the calculation model, the uncertainty of the calculation method and the uncertainty of the calculation nuclear data. With the development of neutronics calculation methods and the development of computer science, nuclear data uncertainty has become the main source of core physics calculation uncertainty. [0003] Since the 20th century, the evaluation of the nuclear data uncertainty by the core physical calculation output response is mainly based on the conjugate sensitivity analysis method. Sensitivity...

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Problems solved by technology

[0005] The purpose of the present invention is to provide a method for accelerating the solution of the generalized conjugate neutron transport equation, solve the efficiency problem of the generalized conjugate neutron transport equation, and realize the comparison of nuclear data in solving physical parameters such as reactor reaction rate ratio and average fission power. Significantly reduce calculation time and improve efficiency when the sensitivity coefficient of

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