An accelerated method for high-fidelity spatio-temporal electron dynamics calculations

A neutron dynamics and neutron technology, which is applied in the field of nuclear reactor core design and nuclear safety, can solve the problems of shortening the calculation time of the calculation process, reducing the number of time steps, and long calculation time, etc.

Active Publication Date: 2019-11-26
XI AN JIAOTONG UNIV
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Problems solved by technology

[0007] In order to overcome the problems of the above-mentioned prior art and solve the problem that the calculation time of high-fidelity space-time neutron dynamics calculations is too long, the purpose of this invention is to propose a method for accelerating high-fidelity space-time neutron dynamics calculations. Under the premise of ensuring the calculation accuracy, it can greatly reduce the number of time steps for high-fidelity spatiotemporal subdynamics calculations, and at the same time reduce the calculation time on each time step, thereby greatly shortening the calculation time of the entire calculation process

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  • An accelerated method for high-fidelity spatio-temporal electron dynamics calculations
  • An accelerated method for high-fidelity spatio-temporal electron dynamics calculations
  • An accelerated method for high-fidelity spatio-temporal electron dynamics calculations

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Embodiment Construction

[0265] The present invention is described in detail below in conjunction with accompanying drawing and specific embodiment:

[0266] Step 1: If figure 2 As shown in the core criticality calculation flow chart, the criticality calculation of the nuclear reactor is carried out, and the one-step direct transport calculation is adopted to obtain the neutron flux density of each energy group and each flat source region and the neutron flux density in each flat source region when the nuclear reactor is in the critical state. The density of each group of delayed neutron precursor nuclei, specifically includes the following steps:

[0267] 1) Read the original multi-group macroscopic section and kinetic parameter information of each nuclide from the section library;

[0268] 2) Read the geometric information and calculation conditions of the nuclear reactor from the input card;

[0269] 3) Establish a calculation model according to the geometric information in the input card: first...

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Abstract

The invention relates to an acceleration method for high fidelity space-time neutron dynamic calculation. The acceleration method comprises the following steps: firstly, calculating neutron flux density and pioneer nucleus concentration of a reactor in a clinical state by adopting a one-step method; secondly, executing cross section disturbance, and starting to carry out space-time neutron dynamic calculation; thirdly, carrying out transporting calculation in a large time step by using a one-step method, and obtaining estimated neutron flux density; and fourthly, carrying out CMFD calculation in a medium time step, accelerating by adopting a global acceleration factor method, carrying out point-reactor calculation in the minimum time step, correcting the amplitude of coarse mesh flux by using point-reactor amplitude, and then updating the neutron flux density of a fine mesh by using the updated coarse mesh amplitude. The acceleration method provided by the invention has the advantages that time steps of the high fidelity space-time neutron dynamic calculation can be greatly reduced while guaranteeing the calculation accuracy, the calculation time on each time step is also reduced, and the time consumed by calculation of the whole calculation process is greatly shortened.

Description

technical field [0001] The invention relates to the technical field of nuclear reactor core design and nuclear safety, in particular to an acceleration method for high-fidelity spatiotemporal electron dynamics calculation. Background technique [0002] The analysis of transient and accident conditions of PWR nuclear power plants has long been based on the point reactor model that does not consider the influence of space. The so-called point reactor model believes that the power change of the entire nuclear reactor has nothing to do with the spatial location. Obviously, the point reactor model is not suitable for power distribution. Distortion, such as bouncing rod accidents, falling rod accidents, breach accidents in the main steam pipeline, etc. In recent years, with the rapid development of computer technology, a three-dimensional spatiotemporal electron dynamics calculation method has been developed on the basis of the point-pile model, which has taken into account the sp...

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G06F17/50
CPCG16Z99/00
Inventor 刘宙宇王博曹良志吴宏春
Owner XI AN JIAOTONG UNIV
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