A Method to Accelerate the Solving of Generalized Conjugate Neutron Transport Equation

Abstract

The invention relates to the technical field of nuclear reactor cores, and specifically discloses a method for accelerating the solution of generalized conjugated neutron transport equations. The method includes: using the characteristic line method to solve the neutron transport equation and the conjugated neutron transport equation respectively, and obtain their corresponding neutron flux distributions; source term, and construct the generalized conjugate neutron transport equation; build a fixed source solver to solve the generalized conjugate neutron transport equation; solve to obtain the generalized conjugate neutron transport equation; this method scans the characteristic line to ensure that the generalized conjugate neutron transport equation is The accuracy of the solution of the conjugated neutron transport equation is accelerated by the coarse network finite difference to ensure the high efficiency of the generalized conjugated neutron transport equation; the invention is used to solve the physical parameters such as the reaction rate ratio and the average fission power of the reactor to verify the nuclear power. When the sensitivity coefficient of the data is adjusted, the calculation time can be significantly reduced and the efficiency can be 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 a generalized conjugated neutron transport equation. 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 calculated nuclear data. With the development of neutronics calculation methods and the development of computer science, nuclear data uncertainty has become the main source of uncertainty in core physics calculations. [0003] Since the 20th century, the evaluation of the uncertainty of nuclear data by the output response of the core physics calculation is mainly based on the conjugate sensitivity analysis method...

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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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