An optimization method for nuclear cross-section data processing in Monte Carlo particle transport simulation

Abstract

The invention discloses a nuclear cross section data processing optimization method in MC (Monte Carlo) particle transport simulation. On the traditional MC particle transport simulation continuity point cross section processing and application method, energy grid points of all nuclides involved in the merging problem form a uniform energy grid, one time of searching is only needed to be conducted to the energy grid for each step of transport, the specific position of the current energy in each nuclide energy grid is directly found through a nuclide pointer array obtained through preprocessing, thus the operation of repetitively searching different energy grids of each nuclide in a material in the traditional method is avoided, the times of searching of the energy grid in MC particle transport calculation are greatly reduced and the calculation speed is improved on the premise that the calculation precision is not lost; and according to the distribution characteristics of nuclear data energy points, an energy segmentation concept is introduced to form a dual-layer searching mode of energy grids, thus the times of ineffective searching in areas with higher distribution density are reduced and the grid searching efficiency per time is improved.

Description

technical field [0001] The invention relates to a nuclear section data processing optimization method in Monte Carlo particle transport calculation, belonging 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 slow calculations when there are many nuclides, especially in b...

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Problems solved by technology

However, in the existing unified energy grid method, considering the calculation speed, calculation accuracy and memory overhead, there are usually two processing methods: one is usually to merge the energy grids of all nuclides in order to ensure the accuracy of the original nuclear data, And for all energy points, various cross-sections of all nuclides and various macroscopic cross-sections of each material are pre-calculated, and stored in memory for transportation calculations, so it will take up a very large memory, and even cannot be used because the required memory is too large Perform calculations; Another way to avoid large memory overhead is to customize a set of energy grids or simplify the energy grids of all nuclides instead of merging the energy grids of all nuclides when building a unified energy grid , such processing results in a partial loss of the precision of the original kernel data

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