High-order transport correction method and system for pressurized water reactor plate fuel

By employing a higher-order transport correction method based on the OSC correction method and the power iteration method, the problem of neutron transport calculation error in plate-shaped fuels was solved, achieving more accurate neutron flux distribution and safety assessment, thus ensuring the safety and reliability of the reactor.

CN122452195APending Publication Date: 2026-07-24NAVAL UNIV OF ENG PLA
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Patent Information

Authority / Receiving Office
CN Β· China
Patent Type
Applications(China)
Current Assignee / Owner
NAVAL UNIV OF ENG PLA
Filing Date
2026-06-25
Publication Date
2026-07-24

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Abstract

The application discloses a high-order transport correction method and system based on a pressurized water reactor plate fuel, and comprises the following steps: obtaining initial self-scattering cross sections to high-order self-scattering cross sections in the same energy group of the pressurized water reactor plate fuel; obtaining an effective multiplication factor according to a preset weight through an OSC correction method and a power iteration method based on the initial self-scattering cross sections to the high-order self-scattering cross sections; calculating a reference weight according to the preset weight and the effective multiplication factor; and finally, correcting transport cross sections and self-scattering cross sections of the pressurized water reactor plate fuel through the OSC correction method based on the reference weight and the initial self-scattering cross sections to the high-order self-scattering cross sections. The application adopts a Monte Carlo method to obtain high-precision high-order scattering cross sections, and introduces a calibratable weight coefficient to correct the self-scattering cross sections in a physical driving mode; the corrected cross sections are input into a characteristic line method transport solver to obtain neutron flux distribution closer to a real physical field, thereby guaranteeing the safety and reliability of reactor design and operation.
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