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

A database and fusion reactor technology, applied in database design/maintenance, special data processing applications, electrical digital data processing, etc., can solve problems such as reducing the economy of fusion reactor radiation shielding design, systematic deviation, and difficulty in convergence

Active Publication Date: 2021-11-05
XI AN JIAOTONG UNIV
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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-orde

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

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Embodiment Construction

[0050] Below in conjunction with accompanying drawing and specific embodiment the present invention is described in further detail:

[0051] Such as figure 1 Shown, the present invention a kind of method based on Monte Carlo method to make fusion reactor multi-group shielding database, the steps are as follows:

[0052] Step 1: Use the nuclear database processing software to process the evaluation nuclear database, such as the ENDF database, into a continuous energy database, namely the ACE format database. The main work of general processing is divided into three parts. Firstly, under the premise of satisfying the linear interpolation, the information in the evaluation core database is compressed; secondly, the data in the indistinguishable resonance area is processed into a probability table; finally, other data are copied from the evaluation core database and stored in the ACE format database. In the ACE format database, the number of energy grids can reach tens of thousa...

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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...

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Application Information

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IPC IPC(8): G06F16/21G06F16/2458G06F17/18
CPCG06F16/212G06F16/2462G06F17/18Y02E30/10
Inventor 贺清明李捷黄金龙曹良志吴宏春
Owner XI AN JIAOTONG UNIV
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