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Method and device for reconstructing burn-up characteristics of reactor core lattice cells

A cell and burn-up technology, applied in the field of nuclear power, can solve the problems of low core transportation calculation efficiency, achieve the effects of high speed, small calculation amount, and improve accuracy and efficiency

Active Publication Date: 2021-02-09
NUCLEAR POWER INSTITUTE OF CHINA
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  • Claims
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Problems solved by technology

However, the calculation efficiency of core transport is low, and it has not yet been widely used in reactor engineering
The accuracy and efficiency of calculation of core burnup characteristics need to be improved urgently

Method used

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  • Method and device for reconstructing burn-up characteristics of reactor core lattice cells
  • Method and device for reconstructing burn-up characteristics of reactor core lattice cells
  • Method and device for reconstructing burn-up characteristics of reactor core lattice cells

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Embodiment Construction

[0050] The present invention will be described in further detail below in conjunction with the accompanying drawings and specific embodiments.

[0051] figure 1It is a flow chart of a method for reconfiguring the burnup characteristics of a core cell according to an exemplary embodiment. The method can be executed by a terminal device. For example, the terminal device can be a server, a desktop computer, a notebook computer, a tablet computer, etc., and the terminal device can also be, for example, a user device, a vehicle-mounted device, or a wearable device. The type of is not limited. Such as figure 1 As shown, the method includes:

[0052] Step 100, divide the core assembly into multiple segments in the axial direction.

[0053] For example, the core assembly can be formed by a plurality of equal-length cells arranged in parallel, and the core assembly can be divided into a plurality of rectangular segments of the same size along the axial direction, and each segment c...

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Abstract

The invention belongs to the technical field of nuclear power, and particularly relates to a reconstruction method and device for burn-up characteristics of reactor core lattice cells. The neutron flux of each energy group in each segment divided in the axial direction of the reactor core assembly and the microscopic cross section of each energy group are determined by adopting a neutron diffusionmodel, and microscopic burnup calculation of a lattice cell level fine grid is carried out on the reactor core by adopting a modulation method. And thus, parameters such as the microscopic reaction rate and the important nuclide nucleon density in the lattice cell can be obtained more accurately. Compared with a neutron transport model, the neutron diffusion model is small in calculation amount and high in speed, so that a large number of calculation resources can be saved, efficient calculation can be realized, parameters such as the microcosmic reaction rate and the important nuclide nucleon density in a lattice cell can be obtained more accurately, and the accuracy and efficiency of reactor core burn-up characteristic calculation are greatly improved.

Description

technical field [0001] The invention belongs to the technical field of nuclear power, and in particular relates to a method and device for reconfiguring the fuel consumption characteristics of a core cell. Background technique [0002] Reactor core design is an important aspect of reactor design. The current nuclear power reactor core design calculation still adopts a "two-step method", that is, the component transportation calculation is carried out first, and the homogenization rate under different fuel depths and various states of the component level is obtained. Group parameters, the core interpolates the minority group cross-section according to the actual state, and performs neutron diffusion calculations to obtain parameters such as the neutron flux density, power distribution, and nucleon density in each area of ​​the core. However, the computational efficiency of core transport is low, and it has not yet been widely used in reactor engineering. The accuracy and eff...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06F30/20G06F119/06
CPCG06F30/20G06F2119/06
Inventor 安萍汤琪芬芦韡柴晓明李庆刘东郭凤晨马永强赵文博卢宗健孙伟秦志红涂晓兰曾辉汪量子刘启伟
Owner NUCLEAR POWER INSTITUTE OF CHINA
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