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A Continuum Energy Point Monte Carlo Particle Transport Method Based on Multi-Group Imaginary Sections

A particle transport and Monte Carlo technology, applied in the field of atomic energy science, can solve problems such as complex processing, loss of nuclear data accuracy, and easy misoperation, and achieve the effects of low memory overhead, good calculation speed, and less memory

Active Publication Date: 2018-10-26
HEFEI INSTITUTES OF PHYSICAL SCIENCE - CHINESE ACAD OF SCI
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Problems solved by technology

In this method, the energy points in the unified energy grid will be reduced a lot (more than 50%), but there are still many, and the processing is complicated, and it is easy to misuse and cause the loss of nuclear data accuracy

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  • A Continuum Energy Point Monte Carlo Particle Transport Method Based on Multi-Group Imaginary Sections

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Embodiment Construction

[0028] Such as figure 1 Shown, the realization process of the present invention includes the following contents:

[0029] 1. Preprocessing the continuous energy point nuclear data read from the nuclear database in the Monte Carlo particle transport simulation is achieved through the following steps:

[0030] In the first step, the multi-group unified energy grid array adopts the multi-group unified energy grid array given by the user or built in the program, which is recorded as MultiGErgArray[N MG ], where N MG Indicates the number of grids in the multi-group unified energy grid array (N MG 50-400 is recommended);

[0031] The second step, the establishment of multi-group nuclide pointer array: compare the energy grid array EryArray of each single nuclide i i [N i ], N i Indicates the number of grids, and the multi-group unified energy grid array MultiGErgArray[N MG ], find out that each energy point MultiGErgArray[j] in the multigroup unified energy grid array is in t...

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Abstract

The invention relates to a continuous-energy-point Monte Carlo particle transport method based on multi-group virtual sections. According to the method, a multi-group unionized energy grid is constructed, and section data of materials and nuclides corresponding to the multi-group unionized energy grid are calculated in advance, so that people can acquire various section data needed for transport calculation by only searching the multi-group unionized energy grid one time in each transport, and calculation time is shortened greatly. The normal nuclide continuous-energy grid is of thousands or even more energy points, and the quantity of grid points in the common unionized energy grid method is up to hundreds of thousands and even millions, but the multi-group unionized energy grid is of a small quantity of grid points, and accordingly, internal storage is reduced while single search time is shortened, calculation time is saved, and loss of calculation precision is avoided.

Description

technical field [0001] The invention relates to a continuous energy point Monte Carlo particle transport method based on multi-group imaginary sections, and belongs to the field of atomic energy science and technology. Background technique [0002] The Monte Carlo (MC) method is currently the most commonly used method in particle transport simulation. MC particle transport simulation obtains relevant cross-sectional data of various reactions between particles and matter from the nuclear data of continuous energy point cross-sections to guide various sampling processes in the transport process. The energy grid division of continuous energy points of different nuclides is different. In MC calculation, it is necessary to search the energy grid of each nuclide frequently according to the incident energy to find the corresponding grid index to obtain the corresponding cross section. . These frequent grid searches lead to very slow calculations when there are many nuclides, espe...

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G06F17/50
CPCG16Z99/00
Inventor 郝丽娟吴宜灿胡丽琴宋婧孙光耀
Owner HEFEI INSTITUTES OF PHYSICAL SCIENCE - CHINESE ACAD OF SCI
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