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Multi-scale multi-physical field coupling simulation method for nuclear reactor TRISO fuel particles

A fuel particle, multi-physics technology, applied in electrical digital data processing, instrumentation, computer-aided design, etc., can solve problems such as rough handling of fission gas behavior, and achieve the effect of reducing workload, ensuring accuracy, and model independence

Active Publication Date: 2020-06-16
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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  • Multi-scale multi-physical field coupling simulation method for nuclear reactor TRISO fuel particles
  • Multi-scale multi-physical field coupling 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

A multi-scale multi-physical field coupling simulation method for nuclear reactor TRISO fuel particles comprises the following steps of rstablishing 1, a zero-dimensional neutron burnup model, a one-dimensional geometric model and a three-dimensional geometric model; 2, setting a solution domain, an initial condition and a boundary condition at different scales; 3, completing neutron burnup calculation in each time step length, preliminarily calculating fission gas release amount in the fuel pellet one-dimensional geometric model, and completing preliminary calculation of heat transfer and mechanics in the fuel particle three-dimensional geometric model; and 4, taking a calculation result in the one-dimensional geometric model of the fuel pellet in the step 3 as calculation input in the three-dimensional geometric model of the fuel pellet in the next time step length, wherein he calculation result in the fuel particle three-dimensional geometric model in the step 3 is used as calculation input in the fuel pellet one-dimensional geometric model of the next time step, and calculation results of heat transfer and mechanics are mutually transmitted; and 5, repeating the coupling process in the step 4 until the calculation is converged, otherwise, returning to the step 3 until the calculation is converged.

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 Applications(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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