CN112100887B - Method for calculating stress load of control rod of nuclear reactor control rod assembly - Google Patents
Method for calculating stress load of control rod of nuclear reactor control rod assembly Download PDFInfo
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- CN112100887B CN112100887B CN202010923315.9A CN202010923315A CN112100887B CN 112100887 B CN112100887 B CN 112100887B CN 202010923315 A CN202010923315 A CN 202010923315A CN 112100887 B CN112100887 B CN 112100887B
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Abstract
The invention discloses a method for calculating the stress load of a control rod of a nuclear reactor control rod assembly, which comprises the following steps: establishing a three-dimensional geometric model of the reactor single control rod assembly according to the real design parameters; carrying out structured meshing on the three-dimensional geometric model of the reactor single control rod assembly by using meshing software; compiling a subroutine script through a fortran language according to the calculation requirement; and importing the subprogram script and the established grid model into computational fluid dynamics software, setting specific boundary conditions and fluid working condition parameters, performing computational simulation, and performing simulation calculation through the computational fluid dynamics software. The invention can conveniently and flexibly simulate and calculate the stress condition of the control rods with different design parameters, and can simulate the stress load of the fuel rods in the fuel assembly by the same method, thereby avoiding other complicated work.
Description
Technical Field
The invention belongs to the technical field of single control rod assemblies of nuclear reactors, and particularly relates to a method for calculating the stress load of a control rod assembly of a nuclear reactor.
Background
The control rod assembly is a key component of the nuclear reactor and can improve or reduce the power of the reactor; realizing the rapid or emergency shutdown of the reactor, and keeping a certain hot shutdown reactivity margin; compensating the reactivity change caused by the transient xenon effect during power redistribution and variable working conditions; compensating for reactive losses caused by fuel and moderator temperature effects. Therefore, maintaining the control rod shape in a normal state is critical to the safety of the reactor. However, the geometry inside the control rod guide tubes is very complex, resulting in a complex flow field. The hydraulic pressure on the control rods can drive the control rods to generate high frequency vibration, thereby causing abrasion between the control rods and the guide clamps. Thus, the integrity of the control rods is compromised given that the control rod assemblies operate within the core of the nuclear reactor for extended periods of time. In addition, the cross flow in the control rod guide tube also increases the friction between the control rod and the control rod guide clip, increasing the rod drop time of the control rod, which is very dangerous when the reactor needs to be shut down as soon as possible in an accident situation. Also, when the control rods are bent under a long-term lateral flow environment, the control rods may not be smoothly inserted into the reactor core. Therefore, it is highly desirable to study the flow characteristics within the control rod guide tube, particularly the forces acting on the control rod guide tube.
Disclosure of Invention
In order to solve the problems in the prior art, the invention aims to provide a method for calculating the stress load of a control rod of a nuclear reactor control rod assembly, which can simulate and calculate the stress condition of the control rod under the condition of different design parameter control rod assemblies by using a method for writing a used subroutine script in a fortran language on the basis of the different design parameter control rod assemblies.
In order to achieve the purpose, the invention adopts the following technical scheme:
a method for calculating the stress load of the control rods of a nuclear reactor control rod assembly comprises the following steps:
step 1: using geometric model software to create a three-dimensional geometric model of the single control rod assembly of the reactor according to the real design parameters of the model to be calculated, wherein the three-dimensional geometric model comprises three continuous and close guide clamps, a section of complete control rod guide pipe and 24 control rods;
step 2: carrying out structured meshing on the reactor single control rod assembly three-dimensional geometric model obtained in the step 1 by using meshing software, wherein the method comprises the following steps:
step 2-1: importing the reactor single control rod assembly three-dimensional geometric model obtained in the step (1) into grid division software, and setting grid distribution rate, boundary type and boundary layer grid distribution rate parameters;
step 2-2: dividing the structured grids on the reactor single control rod assembly three-dimensional geometric model obtained in the step 1 through the generation function of the structured grids of the grid division software, and obtaining a single control rod assembly grid model;
and step 3: using a user-defined function tool in fluid mechanics calculation software, compiling a corresponding subprogram script by using a fortran language according to the requirements of calculation and analysis and specific parameters of a three-dimensional geometric model of a reactor single control rod assembly, defining the name and the data type of a required variable for calculating the stress condition of the surface of a control rod, calling the pressure value and the area of each divided region at the surface of the control rod in a flow field in a subprogram main body, multiplying the pressure value and the area to obtain the stress load of the region, calculating the total load and the load density on the basis of the stress load, and outputting and storing the data into a file;
and 4, step 4: and (3) after determining that the subprogram script written in the step (3) is error-free, importing the subprogram script and the single control rod assembly grid model obtained in the step (2) into computational fluid dynamics software, setting specific boundary conditions and fluid working condition parameters in the computational fluid dynamics software, and finally performing computational simulation.
And 5: and (4) processing the result calculated in the step (4) through a data analysis program to obtain a data file, and analyzing the obtained data file to obtain the load size, direction and density of the control rods at each angle and height along the axial direction.
Compared with the prior art, the invention has the following beneficial effects:
1) the stress condition of the control rod structure can be conveniently and quickly calculated under different control rod assembly design parameters; and the stress condition of the fuel rods in the fuel assembly can be calculated by the same method;
2) according to the method, the subprogram script is compiled through the fortran language according to the requirements of computational analysis, and people who know the subprogram script with certain knowledge can realize the subprogram script, so that the method is flexible and convenient;
3) the model is independent, the method is strong in universality, and the method can be suitable for different types of fluid mechanics calculation analysis programs.
Drawings
FIG. 1a is a guide card in a three-dimensional geometric model of a reactor single control rod assembly;
FIG. 1b is a drawing of a guide card and control rod in a three-dimensional geometric model of a reactor single control rod assembly;
FIG. 1c is a complete structure of a three-dimensional geometric model of a reactor single control rod assembly;
FIG. 2 is a control rod assembly grid model;
FIG. 3 is a flow chart of the method of the present invention.
Detailed Description
The present invention will be described in further detail below with reference to the flow chart of fig. 3, taking as an example a control rod assembly used in a typical pressurized water reactor.
A method for calculating the stress load of the control rods of a nuclear reactor control rod assembly comprises the following steps:
step 1: establishing a three-dimensional model by using a self-contained geometric model module in a salome platform, and creating a three-dimensional geometric model of the single control rod assembly of the reactor according to a real design, wherein the three-dimensional geometric model comprises the following steps: three consecutive and adjacent guide cards, a section of complete control rod guide tube and 24 control rods, as shown in fig. 1a, 1b and 1 c;
step 2: carrying out structured grid division and generation on the reactor single control rod assembly three-dimensional geometric model obtained in the step 1 by using a grid generation module carried by the salome platform, and specifically comprising the following steps:
step 2-1: importing the reactor single control rod assembly three-dimensional geometric model obtained in the step (1) into grid generation software, and setting grid distribution rate, boundary type and boundary layer grid distribution rate parameters, particularly refining grids near control rods and in a guide card area;
step 2-2: generating a structured grid on the three-dimensional geometric model of the single control rod assembly obtained in the step 1 through a generation function of the structured grid of grid generation software, and obtaining a grid model of the single control rod assembly, wherein the obtained grid model is shown in a figure 2;
and step 3: using a user-defined function tool in fluid mechanics calculation software, compiling a corresponding subprogram script by using a fortran language according to the requirements of calculation and analysis and specific parameters of a three-dimensional geometric model of a reactor single control rod assembly, in order to calculate the stress condition of the surface of a control rod, firstly defining the name and the data type of a required variable, then calling the pressure value and the area of each divided region at the surface of the control rod in a flow field in a subprogram main body, then multiplying the pressure value and the area to obtain the stress load of the region, compiling the stress angle of the calculation region on the basis of the calculation, calculating the stress size of each angle of the region, calculating the stress density of each angle of the region, calculating the total load size of the x-axis, the y-axis and the z-axis directions of the region, calculating the total load direction of the region and the like, and finally outputting and storing the data into a file;
and 4, step 4: reestablishing a simple geometric model and generating a grid, properly modifying the subprogram script, introducing the subprogram script into the code _ sature of computational fluid dynamics software CFD for calculation to determine that the subprogram script written in the step 3 has no error, introducing the subprogram script and the single control rod component grid model obtained in the step 2 into the code _ sature of computational fluid dynamics software, setting parameters such as specific boundary conditions and fluid working conditions in the software, and finally performing calculation simulation.
And 5: and (4) processing the result calculated in the step (4) by data analysis software paraview to obtain a data file, and analyzing the obtained data file to obtain the load size, direction and density of the control rods at each height at each angle along the axial direction.
The invention is not described in detail and is within the knowledge of a person skilled in the art.
Claims (1)
1. A method for calculating the stress load of a control rod assembly of a nuclear reactor is characterized by comprising the following steps:
step 1: using a self-contained geometric model module in an open source Salome platform, and creating a three-dimensional geometric model of the single control rod assembly of the reactor according to the real design parameters of the model to be calculated, wherein the three-dimensional geometric model comprises three continuous and close guide clamps, a section of complete control rod guide pipe and 24 control rods;
step 2: carrying out structured grid division on the reactor single control rod assembly three-dimensional geometric model obtained in the step 1 by using a grid generation module in an open source software Salome platform, wherein the method comprises the following steps:
step 2-1: importing the reactor single control rod assembly three-dimensional geometric model obtained in the step (1) into a grid generation module, and setting grid distribution rate, boundary type and boundary layer grid distribution rate parameters;
step 2-2: dividing the structured grids on the reactor single control rod assembly three-dimensional geometric model obtained in the step 1 through the generation function of the structured grids of the grid generation module, and obtaining a single control rod assembly grid model;
and step 3: using a user-defined function tool of open-source fluid mechanics calculation software Code _ Saturn, compiling a corresponding subprogram script by using a fortran language according to the requirements of calculation and analysis and specific parameters of a three-dimensional geometric model of a reactor single control rod assembly, firstly defining the name of a required variable and the data type of the required variable for calculating the stress condition of the surface of a control rod, then calling the pressure value and the area of each divided region at the surface of the control rod in a flow field in a subprogram main body, then multiplying the pressure value and the area to obtain the stress load of the region, calculating the total load and the load density on the basis, and finally outputting and storing the data into a file;
and 4, step 4: after determining that the subprogram script written in the step 3 is error-free, importing the subprogram script and the single control rod assembly grid model obtained in the step 2 into open-source fluid mechanics calculation software Code _ Saturn, then setting specific boundary conditions and fluid working condition parameters in the calculation fluid mechanics software, and finally performing calculation simulation;
and 5: and (4) processing the result calculated in the step (4) by using a post-processing module in the Salome platform of the open source software to obtain a data file, and analyzing the obtained data file to obtain the load size, direction and density of the control rods at each height at each angle along the axial direction.
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