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GPU acceleration method based on fine neutron space-time dynamics lattice Boltzmann method

A space-time dynamics and neutron technology, applied in the field of GPU acceleration, can solve problems such as low parallel efficiency, inconspicuous acceleration effect, and difficult implementation

Active Publication Date: 2020-10-16
SUN YAT SEN UNIV
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Problems solved by technology

[0004] In order to solve the problems of large-scale GPU parallel computing difficulty and low parallel efficiency, the present invention proposes a GPU acceleration technology based on the lattice Boltzmann method of fine neutron spatiotemporal dynamics, which applies the lattice Boltzmann method to neutron spatiotemporal dynamics problem and apply it to GPU accelerated calculation. Without changing the grid density and other conditions, it can greatly improve the calculation speed, quickly simulate the space-time distribution of neutron fluence rate in nuclear reactors, and overcome the traditional numerical method in GPU acceleration. The disadvantages of difficulty in realization and inconspicuous acceleration effect in calculation make reactor fine neutron spatiotemporal dynamics calculation play a more important role in the field of nuclear reactor design and safety analysis

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Embodiment 1

[0081] A GPU acceleration method based on fine neutron spatiotemporal dynamics lattice Boltzmann method, the GPU acceleration method comprising:

[0082] Step 1. Calculation of nuclear reactor steady-state multi-group diffusion equations. The lattice Boltzmann method is used to calculate the diffusion of non-uniform cores, and the neutron fluence rate distribution and delayed emission in different spatial positions and different energy groups of nuclear reactors under steady-state conditions are obtained. Concentration distribution of daughter precursor nuclei;

[0083] Step 2. Adjust the reactor system to a critical state, and calculate the associated neutron diffusion equation of the reactor through critical state related parameters, and then perform normalized calculation on the associated neutron diffusion equation of the reactor to obtain the associated neutron diffusion equation in the reactor under the critical initial state. The normalized distribution of the sub-fluen...

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Abstract

The invention provides a GPU acceleration method based on a fine neutron space-time dynamics lattice Boltzmann method, and belongs to the technical field of nuclear reactor design and safety analysis.The method comprises the following steps: carrying out diffusion calculation on a non-uniform reactor core on multi-core GPU equipment by adopting a lattice Boltzmann method to obtain neutron fluencerate distribution and delayed neutron precursor concentration distribution in different spatial positions and different energy groups of a nuclear reactor under a steady state condition; and then, solving the quasi-static space-time kinetic equation by adopting a lattice Boltzmann method to obtain the space-time distribution condition of the neutron scalar fluence rate at different moments and the distribution of the delayed neutron precursor concentration at different positions at different moments. According to the acceleration method, the difficulty of large-scale parallel calculation of the reactor can be reduced, and meanwhile, the calculation speed of the neutron space-time dynamics problem of the reactor is greatly increased; the defects that a traditional method is complex in implementation, high in cost and low in acceleration efficiency are overcome.

Description

technical field [0001] The invention relates to a GPU acceleration method based on fine neutron space-time dynamics lattice Boltzmann method, and belongs to the technical field of nuclear reactor design and safety analysis. Background technique [0002] In the current nuclear reactor design and safety analysis, it is often necessary to study the changes in the fine power distribution of the nuclear reactor under external disturbance conditions such as control rod movement to verify whether the reactor design can meet the safety indicators under different transient conditions. Based on this, it is necessary to analyze the reactor Perform fine transient spatio-temporal dynamics analysis on the operating state. With the continuous development of computer technology and numerical simulation methods, the fine space-time dynamic calculation of large-scale neutron diffusion in the whole core has become one of the mainstream research methods. The fine neutron diffusion calculation ...

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Application Information

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IPC IPC(8): G06F9/50G06F17/11G06T1/20
CPCG06T1/20G06F9/505G06F17/11Y02E30/30
Inventor 马宇
Owner SUN YAT SEN UNIV
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