One-step transport calculation method and system based on axial flux expansion

A technology of axial flux and calculation method, which is applied in complex mathematical operations, design optimization/simulation, geometric CAD, etc., and can solve problems such as iterative divergence, large amount of calculation, and difficult application
CN113672849APending Publication Date: 2021-11-19NUCLEAR POWER INSTITUTE OF CHINA
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Patent Information

Authority / Receiving Office
CN · China
Current Assignee / Owner
NUCLEAR POWER INSTITUTE OF CHINA
Publication Date
2021-11-19

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Abstract

The invention discloses a one-step transport calculation method and system based on axial flux expansion. The method comprises the steps: building a three-dimensional neutron transport equation, wherein an input item of the three-dimensional neutron transport equation is advanced reactor data; in the axial direction, carrying out flux expansion in a first-order difference mode, and carrying out layer-by-layer integration on a three-dimensional neutron transport equation; and solving the three-dimensional neutron transport equation to obtain a reactor core characteristic value and three-dimensional neutron flux distribution for reactor design calculation. According to the invention, under existing calculation conditions, the calculation amount is not increased, meanwhile, good stability is achieved, iterative divergence is avoided, and the problem of one-step transport calculation of an advanced reactor is solved.
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Description

technical field

[0001] The invention relates to the field of nuclear reactor core design and reactor physical numerical calculation, in particular to a one-step transport calculation method and system based on axial flux expansion. Background technique

[0002] As the basis of nuclear reactor system analysis and calculation, reactor physics analysis and calculation obtains the reactivity of the core and the fine power distribution of the whole reactor by solving the neutron transport equation. In order to quickly carry out the research and development of advanced nuclear power reactor core, it is necessary to develop advanced high-precision reactor physical design software. In order to simulate complex structural cores, researches on "one-step" reactor physical calculation methods based on accurate physical models and fine geometric modeling are being carried out extensively at home and abroad.

[0003] The one-step transport calculation method refers to the neutron transpo...

Claims

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