Data visualization method based on neutron transport characteristic line theory

Abstract

The invention belongs to the field of nuclear reactor physical simulation and data visualization and specifically relates to a data visualization method based on a neutron transport characteristic line theory. The method comprises the steps of establishing a geometric model of a computing area through adoption of a method for establishing entity geometry, obtaining geometric entities by carrying out primary Boolean operation on a weighted curve, appointing a material serial number to each sealed geometric entity, and so on. According to the method, compact characteristic line fragment information produced in a characteristic line tracking process can be utilized fully and effectively, corresponding color RGB values are appointed to the characteristic line fragments, and the data is visualized based on characteristic line filling.

Description

technical field [0001] The invention belongs to the field of nuclear reactor physical simulation and data visualization, and in particular relates to a data visualization method based on neutron transport characteristic line theory. Background technique [0002] Solving the Boltzmann neutron transport equation is an essential content in the physical calculation of the nuclear reactor core, and the transport equation in the form of characteristic lines proposed by Askew in 1972 has the advantages of simple form and strong geometric adaptability, so in recent years The characteristic line method has found a large number of applications in neutron transport programs. [0003] This method requires a fine mesh division of the calculated area, usually the shape of the divided grid is irregular, and may be composed of various forms of curves, such as straight lines, arcs, ellipse, etc. Before performing time-consuming transportation calculations, users usually need to judge wheth...

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Problems solved by technology

Before performing time-consuming transportation calculations, users usually need to judge whether the geometric pre-processing conditions (such as material layout, flat source grid division, feature line tracking, etc.) meet the expected requirements, and then decide whether to continue to run the transportation calculation module. These irregular grids pose challenges to both the visualization of geometric preprocessing results and the visualization of calculation results

[0004] The traditional pixel visualization technology has its own advantages in data visualization, but it is mainly for pixel filling of regular closed areas. For reactor neutron transport calculations, a large number of irregular grids will make the traditional visualization method difficult to handle

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