Axial flux-based quasi-three-dimensional transport calculation method and system

A technology of axial flux and calculation method, which is applied in complex mathematical operations, design optimization/simulation, special data processing applications, etc., can solve problems affecting right-end source items, unstable iteration process, negative flux, etc., and achieve improved Computational Stability Effects

Pending Publication Date: 2021-11-26
NUCLEAR POWER INSTITUTE OF CHINA
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Problems solved by technology

[0004] For the quasi-three-dimensional method of axial flux expansion, the difference relationship is introduced in the case of first-order approximation, resulting in the possibility of negative flux, which will affect the source term at the right end, resulting in instability in the iterative process

Method used

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  • Axial flux-based quasi-three-dimensional transport calculation method and system
  • Axial flux-based quasi-three-dimensional transport calculation method and system
  • Axial flux-based quasi-three-dimensional transport calculation method and system

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Embodiment 1

[0029] This embodiment 1 is a quasi-three-dimensional transport calculation method applied to the axial flux expansion. It deals with the negative flux at the boundary caused by the introduction of the difference relationship in the quasi-three-dimensional method for flux expansion. By setting the negative flux to zero, thereby Improve the numerical stability of the method.

[0030] In the quasi-three-dimensional transport calculation based on the characteristic line method, the spatial region is divided into several small regions, that is, the flat source region, and the neutron flux and neutron source items in each flat source region are approximately considered to be consistent; the neutron flux in the flat source region The quantity is the standard flux in the flat source region; the process of calculating the standard flux in the flat source region through the leakage item is to use the quasi-three-dimensional characteristic line method to solve the neutron transport equat...

Embodiment 2

[0038] Embodiment 2 is based on Embodiment 1, a quasi-three-dimensional transport calculation system based on axial flux expansion. The system uses the quasi-three-dimensional transport calculation method based on axial flux expansion in Example 1. Embodiment 2 The system specifically includes:

[0039] Equation establishment module: used to establish the three-dimensional neutron transport equation, the input items of the three-dimensional neutron transport equation are the CSG geometry module and section data of the advanced reactor.

[0040] Negative flux zeroing module: used to perform flux expansion in the axial direction by using the first-order differential form, and perform zeroing operation on the negative flux that appears;

[0041] Standard flux calculation module: used to calculate the axial and radial leakage items of each flat source area according to the boundary surface flux after zeroing, and calculate the standard flux of each flat source area according to th...

Embodiment 3

[0043] Embodiment 3 is based on Embodiment 1. Embodiment 3 provides a device, where the device includes: one or more processors;

[0044] The memory is used to store one or more programs, and when the one or more programs are executed by the one or more processors, the one or more processors execute a quasi-three-dimensional transport calculation method based on axial flux expansion.

[0045] Wherein, a quasi-three-dimensional transport calculation method based on axial flux expansion is performed according to the method steps in Embodiment 1. No more details here.

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Abstract

The invention discloses an axial flux-based quasi-three-dimensional transport calculation method and system, and the method comprises the steps: building a three-dimensional neutron transport equation, and enabling an input item of the three-dimensional neutron transport equation to be advanced reactor data; and in the axial direction, carrying out flux expansion in a first-order difference mode and zero setting operation on the appearing negative flux, calculating axial and radial leakage items of each flat source region according to the flux of the boundary surface after zero setting, and calculating the standard flux of each flat source region according to the axial and radial leakage items. The negative flux is zeroed, a boundary flow calculation leakage item is obtained through statistics after the negative flux is zeroed, and the standard flux of the flat source area is recalculated through the leakage item. Therefore, the situation that flow and flux are not matched due to simple zero setting, and calculation convergence is affected is avoided.

Description

technical field [0001] The invention relates to the fields of nuclear reactor core design and reactor physical numerical calculation, in particular to a quasi-three-dimensional 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...

Claims

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Application Information

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IPC IPC(8): G06F30/20G06F17/11G06F17/13G06F17/17G06F111/10
CPCG06F30/20G06F17/11G06F17/13G06F17/17G06F2111/10
Inventor 赵晨彭星杰赵文博张斌卢宗健于颖锐李庆
Owner NUCLEAR POWER INSTITUTE OF CHINA
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