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Double non-uniform space self-screen effect correction method, device, equipment and medium

A non-uniformity and self-screening technology, which is applied in the field of nuclear reactor cores, can solve problems such as the inability to correct double non-uniformity space self-screening effects, and achieve the effect of improving accuracy

Active Publication Date: 2022-03-25
NUCLEAR POWER INSTITUTE OF CHINA
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  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0004] The technical problem to be solved by the present invention is that the existing deterministic method based on the multi-group structure cannot correct the dual non-uniform spatial self-shielding effect of randomly distributed media fuel elements, so the present invention provides a dual non-uniform spatial self-screening effect. The screen effect correction method is applied in the traditional pressurized water reactor core design neutronics calculation software to realize the correction of the double non-uniform space self-screen effect of the randomly distributed dielectric fuel elements and improve the accuracy of neutron calculations

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  • Double non-uniform space self-screen effect correction method, device, equipment and medium
  • Double non-uniform space self-screen effect correction method, device, equipment and medium
  • Double non-uniform space self-screen effect correction method, device, equipment and medium

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Embodiment 1

[0043] Such asfigure 1 As shown, the present invention provides a double non-uniform space self-screen effect correction method, which specifically includes the following steps:

[0044] S10: Calculate the number of all neutrons escaping from the fuel surface and the number of neutrons that enter the adjacent fuel cell and collide in the moderator after escaping from the fuel surface through the Monte Carlo method , to get the Dankov factor.

[0045] Specifically, count the number of all neutrons that escape from the fuel surface as the first data, and count the number of neutrons that escape from the fuel surface and enter the adjacent fuel cells without any collisions in the moderator as For the second data, the ratio of the second data to the first data is used as the Dankov factor.

[0046] S20: Acquiring the neutron escape probability, and correcting the neutron escape probability based on the Dankov factor, so as to correct the double non-uniformity of the neutron reson...

Embodiment 2

[0068] Such as Figure 4 As shown, the difference between this embodiment and Embodiment 1 is that a double non-uniform space self-screen effect correction device is provided, including:

[0069] The Monte Carlo method processing module 10 is used to calculate the number of all neutrons escaping from the fuel surface and entering into the adjacent fuel cell without any collision in the moderator after escaping from the fuel surface through the Monte Carlo method The number of colliding neutrons is calculated to obtain the Dankov factor.

[0070] The Dankov factor correction module 20 is used to obtain the neutron escape probability, and correct the neutron escape probability based on the Dankov factor, so as to correct the double non-uniformity of the neutron resonance calculation.

[0071] The equivalent homogeneous processing module 30 is used to equivalent the randomly distributed medium region to a homogenized medium according to the fact that the escape probability of ne...

Embodiment 3

[0086] This embodiment provides a computer device, which may be a server, and its internal structure diagram may be as follows Figure 5 shown. The computer device includes a processor, memory, network interface and database connected by a system bus. Wherein, the processor of the computer device is used to provide calculation and control capabilities. The memory of the computer device includes a computer-readable storage medium and an internal memory. The computer readable storage medium stores an operating system, computer programs and databases. The internal memory provides an environment for the operation of the operating system and computer programs in the computer-readable storage medium. The database of the computer equipment is used to store the data involved in a double non-uniform space self-screen effect correction method. The network interface of the computer device is used to communicate with an external terminal via a network connection. When the computer pr...

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Abstract

The invention discloses a double non-uniform space self-shielding effect correction method, device, equipment and medium. The method uses the Monte Carlo method to calculate the number of all neutrons escaping from the fuel surface and the number of neutrons after escaping from the fuel surface. Calculate the number of neutrons that collide with the adjacent fuel cells without any collisions in the fuel to obtain the Dankov factor, and then use the Dankov factor to correct the neutron escape probability to correct the neutron resonance calculation double inhomogeneity; according to the fact that the escape probability of neutrons in the random distribution medium region remains unchanged before and after uniformity, the random distribution medium region is equivalent to a homogenized medium; based on the macroscopic cross-section of each subregion of dispersed particles and matrix, and the Calculate the equivalent cross-section of the homogenized medium with the corresponding volume fraction and space self-shielding factor, so as to correct the double non-uniformity of the neutron transport calculation, and realize the correction of the double non-uniformity space self-shielding effect of the randomly distributed medium fuel elements, Improve the accuracy of neutron calculations.

Description

technical field [0001] The invention relates to the technical field of nuclear reactor cores, in particular to a method, device, equipment and medium for correcting double non-uniform space self-shielding effects. Background technique [0002] The safety of nuclear fuel under accident conditions has been paid more and more attention. In order to improve the safety of nuclear reactors, a design that disperses fuel particles in non-fissile matrix materials has emerged, called random distribution medium fuel elements. From the perspective of neutronics calculation, the key difference between fuel elements with randomly distributed media and traditional fuel elements is that fuel particles are dispersed in the matrix in the form of randomly distributed media, and a definite geometric definition cannot be obtained. The fuel cells in the randomly distributed medium fuel element have inhomogeneity on the macroscopic scale (fuel, cladding, moderator), and on the microscopic scale (m...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G06F30/25G06F111/08
CPCG06F30/25G06F2111/08
Inventor 娄磊秦冬姚栋王连杰于颖锐柴晓明彭星杰李庆陈长刘同先李满仓秦雪唐霄李司南
Owner NUCLEAR POWER INSTITUTE OF CHINA
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