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Hybrid computation method for acquiring few-group cross section parameters of fast neutron reactor

A hybrid computing and reactor technology, applied in computing, electrical digital data processing, special data processing applications, etc., can solve problems such as difficult to obtain results, and achieve the effect of avoiding approximation and ensuring accuracy

Active Publication Date: 2017-09-08
XI AN JIAOTONG UNIV
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Problems solved by technology

But when these values ​​are small, it is difficult to obtain accurate results, such as high-order neutron flux moments

Method used

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  • Hybrid computation method for acquiring few-group cross section parameters of fast neutron reactor
  • Hybrid computation method for acquiring few-group cross section parameters of fast neutron reactor
  • Hybrid computation method for acquiring few-group cross section parameters of fast neutron reactor

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Embodiment Construction

[0052] The present invention will be further described in detail below in conjunction with the drawings and specific embodiments:

[0053] The present invention combines the Monte Carlo method with the deterministic method, uses the Monte Carlo method to carefully consider the resonance effect of the fast reactor components, calculates the accurate multi-group microscopic total cross-section, fission cross-section, and elastic scattering cross-section of each nuclide, and uses The deterministic method is used to solve the elastic scattering cross sections of each order of fast reactor components and the neutron flux moments of each order, so as to merge the multi-group cross-sections into the few group cross-sections, such figure 1 As shown, the invention includes the following steps:

[0054] Step 1: For any fast reactor component to be calculated, read the geometric information of the component and the nuclide information of the corresponding material component;

[0055] Step 2: F...

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Abstract

The invention relates to a hybrid computation method for acquiring few-group cross section parameters of a fast neutron reactor. The hybrid computation method comprises the following steps: combining a Monte Carlo method with a certain theory method, finely considering the resonance effect of a fast reactor assembly by utilizing the Monte Carlo method, calculating precise multi-group microcosmic total cross section, fission cross section and elastic scattering cross section of each nuclide, solving various orders of elastic scattering cross sections and various orders of neutron flux moments of the fast reactor assembly by utilizing the certain theory method, and aggregating the multi-group cross section into the few-group cross section. The hybrid computation method provided by the invention is strong in universality and wide in application range, a high-precision few-group cross section of the fast reactor assembly can be produced, and precise and reliable cross section parameters are provided for a task of designing a nucleus of a reactor core.

Description

Technical field [0001] The invention relates to the field of nuclear reactor core design and nuclear reactor physical calculation, and is a hybrid calculation method for obtaining the parameters of a small group of fast neutron reactors. Background technique [0002] In order to quickly and accurately solve the core neutronics parameters, the method based on the "two-step method" has become the main method for fast reactor engineering calculations. The so-called "two-step method", the first step is to model and calculate the various component materials in the core, and obtain the neutron flux density distribution in the component to merge the small group uniform group cross section; the second step is The homogenization parameters calculated in the previous step are used to solve the core neutron transport equation to obtain physical quantities such as the effective core multiplication factor and core power distribution. [0003] The methods used to calculate the few group cross s...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06F19/00
CPCG16Z99/00
Inventor 郑友琦杜夏楠曹良志吴宏春
Owner XI AN JIAOTONG UNIV
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