Three-dimensional neutron flux numerical simulation method for pressurized water reactor core

Abstract

The invention discloses a three-dimensional neutron flux numerical simulation method for a pressurized water reactor core. The method comprises the following steps: firstly, dividing a three-dimensional pressurized water reactor core to be simulated into a plurality of layers along the axial direction, and establishing a two-dimensional neutron transport model for each layer based on a characteristic line method; secondly, geometrically dividing a to-be-simulated three-dimensional pressurized water reactor core into a plurality of long strips based on radial lattice cells, and establishing a one-dimensional neutron transport model for each long strip based on a discrete longitudinal marking method; and iterating a residual error model formed by the two-dimensional neutron transport model and the one-dimensional neutron transport model through a JFNK method until convergence to obtain neutron flux distribution of the three-dimensional pressurized water reactor core. Compared with the prior art, the two-dimensional neutron transport model and the one-dimensional neutron transport model are converted into the residual error model to be solved at the same time, the second-order convergence speed is achieved, and the iterative solution stability is good. The method can be used for transport module calculation of a numerical reactor, the numerical reactor transport calculation efficiency is improved, the calculation stability is improved, and the nuclear time cost generated by numerical calculation is saved.

Description

technical field [0001] The invention relates to the field of nuclear reactor core design and safety, in particular to a three-dimensional neutron flux numerical simulation method for the pressurized water reactor core. Background technique [0002] With the continuous development of the nuclear power industry, in order to cope with the life extension and safety analysis of nuclear power plants, the accuracy and efficiency requirements of the numerical simulation of the pressurized water reactor core are getting higher and higher. In order to meet the accuracy requirements of PWR numerical simulation, high-fidelity methods such as numerical reactor are more and more used in the numerical simulation of PWR. [0003] The high-fidelity method adopts the whole core to solve directly, and the number of calculated grids is large, and the calculation burden of the three-dimensional neutron transport model of the transport module is relatively large. At present, the method of transv...

AI Technical Summary

Problems solved by technology

This method can be used for the problem that the traditional one-dimensional neutron transport model and the two-dimensional neutron transport model are difficult to converge in the numerical simulation respectively. Compared with the traditional method, this method uses the JFNK method to calculate the residual Difference model, can calculate two transport models at the same time, has second-order convergence speed, high calculation efficiency, and as long as the initial value is selected to be close to the true solution, it will definitely converge and have good stability

Images