A neutron transport method for pressurized water reactor based on deep learning-interfacial flow coupling

Abstract

The invention discloses a pressurized water reactor neutron transport method based on deep learning-interface flow coupling. The Monte Carlo method is used to simulate the neutron migration process after neutron and material capture, fission or scattering of local simple geometric problems. Using the simulation results of Monte Carlo method and deep learning method, the neutron incident-exit distribution law of different materials and geometric units is learned, and the connection relationship between simple geometric units and the calculation process of neutron transport are established based on the interface flow conservation. This method subverts the traditional process of obtaining multi-group cross-sections in deterministic methods, and then performs complex geometric multi-group transport calculations, and forms a new type of neutron that integrates Monte Carlo methods, deep learning and deterministic methods. Transport calculation method.

Description

technical field [0001] The invention relates to the field of nuclear reactor core design and safety, in particular to a pressurized water reactor neutron transport method based on deep learning-interface flow coupling. Background technique [0002] In the current development of nuclear energy, the Monte Carlo method has high computational accuracy and geometric adaptability for the calculation of neutron transport in a pressurized water reactor with complex geometry. However, a large number of particle sampling calculations lead to low computational efficiency. Compared with the Monte Carlo method, the deterministic method has high computational efficiency, but the current resonance calculation method and transport calculation method cannot meet the high-precision and high-efficiency calculation requirements of the complex geometry PWR. The deep learning method has a strong ability to learn complex laws. It can use the deep learning method to learn the migration laws of a la...

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Problems solved by technology

[0002] In the current development of nuclear energy, for the calculation of neutron transport in PWR with complex geometry, the Monte Carlo method has high calculation accuracy and geometric adaptability, but a large number of particle sampling calculations lead to low calculation efficiency

Compared with the Monte Carlo method, the deterministic method has high computational efficiency, but the current resonance calculation method and transport calculation method cannot meet the high-precision and high-efficiency calculation requirements of complex geometric PWRs.

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