Method for manufacturing fusion reactor multi-group shielding database based on Monte Carlo method

Abstract

The invention discloses a method for manufacturing a fusion reactor multi-group shielding database based on a Monte Carlo method. The method comprises the following steps: 1, processing an evaluation nuclear database into a continuous energy ACE format nuclear database; 2, adding information in all scattering reaction channels of each nuclide in the ACE format database to obtain a continuous energy scattering response coefficient database; 3, designing a simplified one-dimensional model according to the real three-dimensional structure of the fusion reactor; 4, calculating a simplified model based on the ACE format database and the continuous energy scattering response coefficient database by adopting a Monte Carlo method; 5, obtaining a multi-group high-order scattering cross section according to the obtained low-order flux, high-order flux and high-order scattering reaction rate; and 6, combining the multi-group high-order scattering cross section with the total cross section, the neutron generation cross section, the absorption cross section, the low-order scattering cross section and the response function library in the multi-group shielding database to generate a new fusion reactor multi-group shielding database. According to the database, fusion reactor radiation shielding calculation is more accurate, and the safety margin is reduced.

Description

technical field [0001] The invention relates to the fields of particle transport calculation and radiation shielding calculation, in particular to a method for preparing a fusion reactor multi-group shielding database based on a Monte Carlo method. Background technique [0002] In the fusion reactor design process, the radiation shielding calculation of the core and building is a key task. The current radiation shielding calculation adopts two mainstream methods: Monte Carlo method based on continuous energy database; deterministic method based on multi-group shielding database. The basic idea of ​​the deterministic method is to discretize the space, angle and energy, solve the discretized particle transport equation, and use the discrete grid distribution to approximate the continuous distribution. [0003] When using the deterministic method to solve the particle transport equation, the exit angle of the particle after each scattering can be processed according to the met...

AI Technical Summary

Problems solved by technology

First, the dimensions of high-order scattering reaction rates are more than those of other reaction rates. Under the same calculation conditions, the statistical fluctuations of high-order scattering reaction rates are larger and it is more difficult to converge

Second, in theory, the high-order scattering cross section should be obtained based on the high-order flux, but the current traditional statistical method is still based on the low-order flux to obtain the high-order scattering cross section, so the high-order scattering cross section obtained by the traditional statistical method has a systematic The resulting multi-group shielding database for fusion reactors is not accurate enough, so that more safety margins need to be considered in the design of radiation shielding for fusion reactors, reducing the economical efficiency of radiation shielding designs for fusion reactors

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