A coupled multiscale and multiphysics simulation method for nuclear reactor triso fuel particles

A technology of fuel particles and multi-physics, applied in the fields of electrical digital data processing, instruments, design optimization/simulation, etc., can solve the problems of rough fission gas behavior processing, etc., and achieve the effect of reducing workload, independent model, and simple realization

Active Publication Date: 2021-10-19
XI AN JIAOTONG UNIV
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Problems solved by technology

In addition, the existing programs at home and abroad deal with the behavior of fission gas relatively roughly, basically adopting a single boundary condition, and failing to truly couple the fuel pellets and fuel particles

Method used

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  • A coupled multiscale and multiphysics simulation method for nuclear reactor triso fuel particles
  • A coupled multiscale and multiphysics simulation method for nuclear reactor triso fuel particles

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Embodiment Construction

[0033] Below in conjunction with accompanying drawing, the present invention is described in further detail:

[0034] Such as figure 1 As shown, a kind of multi-scale multi-physics coupling simulation method for nuclear reactor TRISO fuel particles of the present invention comprises the following steps:

[0035] Step 1: (1) Establish a zero-dimensional neutron burnup calculation model based on the volume fission rate, initial fuel density and time, and establish a zero-dimensional calculation domain, that is, only the time item, without establishing a geometric entity; (2) Establish a fuel pellet- The three-dimensional geometric model is used to calculate the amount of fission gas released. The specific method is as follows: assume that the fuel pellet is an ideal sphere, set a spherically symmetrical coordinate system, and eliminate the two spatial angle coordinates of elevation and azimuth in the spherically symmetrical coordinate system in order to reduce calculation consum...

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Abstract

The multi-scale multi-physics field coupling simulation method for nuclear reactor TRISO fuel particles, the steps are as follows: 1. Establish a zero-dimensional neutron burnup model, establish a one-dimensional geometric model, and establish a three-dimensional geometric model; 2. Set the solution domain at different scales, Initial conditions and boundary conditions; 3. Complete the calculation of neutron burnup at each time step, preliminarily calculate the release of fission gas in the one-dimensional geometric model of fuel pellets, and complete the calculation of heat transfer and mechanics in the three-dimensional geometric model of fuel particles Preliminary calculation; 4. Use the calculation results in the one-dimensional geometric model of fuel pellets in step 3 as the calculation input in the three-dimensional geometric model of fuel particles in the next time step, and use the calculation results in the three-dimensional geometric model of fuel particles in step 3 as the next step. The calculation input in the one-dimensional geometric model of the fuel pellet at the time step, the calculation results of heat transfer and mechanics are transferred to each other; 5. Repeat the coupling process of step 4 until the calculation converges, otherwise return to step 3 until the calculation converges.

Description

technical field [0001] The invention belongs to the technical field of method inventions, and in particular relates to a multi-scale and multi-physical field coupling simulation method for nuclear reactor TRISO fuel particles. Background technique [0002] In order to improve the safety performance of the reactor under accident conditions, the performance analysis of the new generation fuel is one of the key technical contents in the research and development process. Among various fuel design schemes, dispersed fuel elements have multiple effective barriers (TRISO particles and matrix) to enhance the containment capacity of fission products, so dispersed fuel is one of the important accident-tolerant fuel candidates. In the dispersed fuel element, TRISO fuel particles are dispersed in the matrix to form a columnar pellet. Under irradiation conditions, neutron burnup, fission gas release behavior, thermal properties (such as gap heat conduction, temperature distribution), mec...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G06F30/20G06F119/08G06F119/14
Inventor 巫英伟张程王阳阳秋穗正苏光辉田文喜
Owner XI AN JIAOTONG UNIV
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