CN113177335A

CN113177335A - Automatic generation method and system for large-scale grid of full reactor core structure of fast neutron reactor

Info

Publication number: CN113177335A
Application number: CN202110370148.4A
Authority: CN
Inventors: 王昭顺; 蒋章程; 胡长军; 邢龙岳
Original assignee: University of Science and Technology Beijing USTB
Current assignee: University of Science and Technology Beijing USTB
Priority date: 2021-04-07
Filing date: 2021-04-07
Publication date: 2021-07-27
Anticipated expiration: 2041-04-07
Also published as: CN113177335B

Abstract

The invention discloses a method and a system for automatically generating a large-scale grid of a fast neutron reactor full reactor core structure, wherein the method comprises the following steps: constructing a numerical reactor geometric file library so as to store geometric model files of different types of components and the geometric positions of the components in the reactor core; exporting a geometric model file of a required component from the geometric file library of the numerical reactor, and carrying out parallel grid division on the geometric model file of the single component to obtain grid data of the current component; and obtaining the required grid data of the fast reactor whole core or the multiple assemblies through coordinate geometric transformation based on the grid data of the current assemblies and the geometric positions of the current assemblies. The method can realize modeling of the reactor core structure and complete large-scale parallel grid generation, and the grid data is applied to finite element solving software so as to finally realize high-precision and high-efficiency simulation of the mechanical behavior of the reactor core structure.

Description

Automatic generation method and system for large-scale grid of full reactor core structure of fast neutron reactor

Technical Field

The invention relates to the fields of nuclear science and engineering technology, high-performance calculation, high-fidelity numerical simulation based on a supercomputer and finite element analysis, in particular to a method and a system for automatically generating a large-scale grid of a full reactor core structure of a fast neutron reactor.

Background

Under the effects of high temperature, fluid pressure, irradiation and the like, each part of the reactor core assembly can generate deformation of different degrees, and fuel rods inside the assembly can generate flow-induced vibration. These phenomena can cause cladding wear, loading and unloading difficulties, component breakage and fatigue damage to the core assembly. The method has great significance for guaranteeing the safe operation of the reactor by researching the assembly deformation and the fuel rod flow-induced vibration under different environments. Due to the arrangement particularity of the components in the reactor core, the distribution of the temperature, the irradiation, the pressure and the flow field around the components is very complex, and the solution is difficult to solve by adopting a theoretical analysis method. In practical engineering, finite element method is usually adopted for analytical solution.

The finite element method is to discretize a complex physical model into a finite number of grid cells, and this process is also called meshing. And then analyzing each grid cell, establishing a cell stiffness matrix, assembling the cell stiffness matrix into an overall stiffness matrix through coordinate transformation, and finally solving a numerical solution of the deformation condition of the analysis object by solving an overall stiffness equation. The grid division is an important link of finite element analysis and is a basis for realizing high-fidelity numerical simulation. In the process of grid division, the larger the grid density and the larger the grid quantity are, the closer the finally obtained numerical solution is to the true value, but the greater the demand on the internal and external memory resources of the computer is.

At present, the general grid division method is adopted, the whole grid division of the fast neutron reactor full reactor core geometric model cannot be efficiently realized, and grid data obtained by the division cannot be converted into an input file available for general finite element analysis and calculation software. Large-scale grid division based on a supercomputer is the basis for realizing high-fidelity numerical simulation of the mechanical behavior of the reactor core assembly. In order to realize the goal of high-fidelity numerical simulation, the number of the whole reactor core component grids needs to reach the scale of billions or even billions. In the traditional method, all components of the reactor core structure are subjected to integral geometric modeling, and a grid generation tool is used for carrying out integral grid division on the geometric model, so that the problem of low grid division efficiency caused by insufficient computer memory, overlarge grid file and other factors is solved.

Disclosure of Invention

The invention provides a method and a system for automatically generating a large-scale grid of a fast neutron reactor full core structure, which aim to solve the problem that the existing grid division method has insufficient memory when large-scale grid division is carried out.

In order to solve the technical problems, the invention provides the following technical scheme:

on one hand, the invention provides a method for automatically generating a large-scale grid of a full core structure of a fast neutron reactor, which comprises the following steps:

constructing a numerical reactor geometry file library, wherein the numerical reactor geometry file library comprises geometric model files of various components to be subjected to grid division and the geometric positions of the components in the reactor core;

exporting a geometric model file of the component needing meshing from the numerical reactor geometric file library, and carrying out parallel meshing on the single-component geometric model file to obtain the grid data of the current component;

and obtaining the required grid data of the fast reactor whole core or the multiple components through coordinate geometric transformation based on the grid data of the current components and the geometric positions of the current components in the core.

Further, the constructing a numerical reactor geometry file library includes:

performing primary GEO geometric modeling on each type of assembly in the fast neutron reactor core, and setting the coordinates of the bottom center point of the geometric model as origin coordinates to obtain geometric model files of each type of assembly;

numbering each component, and establishing a one-to-one mapping relation between the component numbers and the coordinates of the central points of the components;

and storing the geometric model files of the components of various types, the serial numbers of each component and the mapping relation between the component serial numbers and the coordinates of the central points of the components to obtain a numerical reactor geometric file library.

Further, deriving a geometric model file of the component to be gridded from the library of numerical reactor geometric files, comprising:

acquiring the serial number of a component needing to be subjected to grid division;

deriving a geometric model file of the component needing meshing from the numerical reactor geometric file library according to the acquired serial number of the component; wherein the same type of component only exports a single component geometric model file.

Further, the parallel meshing of the single-component geometric model file includes:

carrying out parallel grid division on the single-component geometric model file derived from the numerical reactor geometric file library by adopting a three-dimensional finite element grid generator Gmsh to generate an MSH grid file;

performing region decomposition and load balancing on the generated MSH grid file;

adding physical parameters to the grid file which completes the regional decomposition and the load balancing; wherein the physical parameters include boundary conditions, material properties, and initial conditions, the boundary conditions including displacement boundary conditions and force boundary conditions; the initial conditions include an initial displacement, an initial velocity, an initial acceleration, an initial temperature, and an initial state variable; the material properties include density, modulus of elasticity, poisson's ratio, and coefficient of thermal expansion.

Further, the grid data includes grid node data, grid cell data and various control parameters;

the grid node data is used for explaining the coordinates of each grid node;

the grid cell data is used for explaining which grid nodes each grid cell is composed of;

the control parameters are used to describe various parameter options that affect the problem solution, including boundary conditions, material properties, and initial conditions.

Further, obtaining the grid data of the required fast reactor whole core or the multiple assemblies through coordinate geometric transformation based on the grid data of the current assemblies and the geometric positions of the current assemblies in the core, and the method comprises the following steps:

acquiring grid data of a current assembly and the geometric position of the current assembly in the reactor core;

obtaining the grid data of the required fast reactor whole reactor core or multiple components through the movement and conversion of grid node coordinates, the conversion of grid node and grid unit numbers and the conversion of control parameters based on the grid data of the current components and the geometric positions of the current components in the reactor core;

outputting a full reactor core or multi-component large-scale grid file which accords with the actual condition and can be used for the mechanical numerical simulation of the fast neutron reactor structure through the Boolean operation of cross-over and complementation on the grid data, and automatically generating a grid data organization file; the grid data organization file is used for organizing the logical relationship of each grid file, and the logical relationship is input to the numerical reactor structural mechanics analysis and calculation software to carry out structural mechanics numerical simulation.

On the other hand, the invention also provides a fast reactor full core structure large-scale grid automatic generation system, which comprises:

the numerical reactor geometry file library is used for storing geometric model files of various types of components to be subjected to grid division and the geometric positions of the components in the reactor core;

the grid initial dividing and preprocessing module is used for exporting a geometric model file of the component needing to be subjected to grid division from the numerical reactor geometric file library, and performing parallel grid division on the single-component geometric model file to obtain grid data of the current component;

and the large-scale parallel grid data generation module is used for obtaining the required grid data of the fast reactor whole core or the multiple components through coordinate geometric transformation based on the grid data of the current components output by the grid initial division and preprocessing module and the geometric positions of the current components in the reactor core.

Further, the process for constructing the numerical reactor geometry file library comprises the following steps:

Further, the grid initial partitioning and preprocessing module is specifically configured to:

deriving a geometric model file of the component needing meshing from the numerical reactor geometric file library according to the acquired serial number of the component; wherein, the components of the same type only export a single component geometric model file;

Further, the grid data includes grid node data, grid cell data and various control parameters; the grid node data is used for explaining the coordinates of each grid node; the grid cell data is used for explaining which grid nodes each grid cell is composed of; the control parameters are used for explaining various parameter options influencing the problem solving, and the parameter options comprise boundary conditions, material properties and initial conditions; the massively parallel grid data generation module is specifically used for generating the grid data;

In yet another aspect, the present invention also provides an electronic device comprising a processor and a memory; wherein the memory has stored therein at least one instruction that is loaded and executed by the processor to implement the above-described method.

In yet another aspect, the present invention also provides a computer-readable storage medium having at least one instruction stored therein, the instruction being loaded and executed by a processor to implement the above method.

The technical scheme provided by the invention has the beneficial effects that at least:

the invention provides a large-scale grid (billion and billion grade) automatic generation method which is different from the traditional large-scale grid (billion and billion grade) automatic generation method which only uses grid generation tools (ANSYS Mesh, Gmsh, TetGen and the like) to carry out grid division for a fast neutron reactor structure mechanics numerical simulation, aiming at the reactor core structure, the large-scale grid automatic generation method provided by the invention fully utilizes the isomorphism of a fast reactor component, and automatically generates a full reactor core grid by using a grid file of a single component or a local component, thereby solving the problem of low billion and billion grade grid division efficiency caused by the limitation of computer memory resources and grid file sizes in the traditional grid division method. The invention provides a complete function of finite element analysis pretreatment, including a mesh division function, so that the generated full core mesh file can be directly used for solving finite element solving software.

Drawings

In order to more clearly illustrate the technical solutions in the embodiments of the present invention, the drawings needed to be used in the description of the embodiments will be briefly introduced below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is obvious for those skilled in the art to obtain other drawings based on these drawings without creative efforts.

Fig. 1 is a schematic flow chart of a method for automatically generating a large-scale grid of a fast neutron reactor full core structure according to an embodiment of the present invention;

FIG. 2 is a schematic diagram of geometric transformation of a component grid of the same type according to an embodiment of the present invention;

FIG. 3 is a schematic diagram of the data types of a GEO file;

FIG. 4 is a diagram of a GEO file data structure;

FIG. 5 is a schematic diagram of a fast reactor full core;

FIG. 6 is a flow chart of an implementation of a library of numerical reactor geometry files provided by an embodiment of the present invention;

fig. 7 is a schematic diagram of a large-scale mesh data expansion process provided in the embodiment of the present invention.

Detailed Description

In order to make the objects, technical solutions and advantages of the present invention more apparent, embodiments of the present invention will be described in detail with reference to the accompanying drawings.

First embodiment

The embodiment provides a method for automatically generating a large-scale grid of a fast neutron reactor full core structure, which can be realized by electronic equipment, and the electronic equipment can be a terminal or a server. As shown in fig. 1, the automatic large-scale grid generation method provided in this embodiment finally outputs a grid input file for analysis and calculation of a finite element solver through a numerical reactor geometry file library, a grid initial partitioning and preprocessing method, and a large-scale parallel grid data generation method. Specifically, the grid division concept is as follows:

1) allocating a serial number for each component of the whole reactor core, and inputting the serial number of the required component by filling a control card;

2) according to data input in the control card, a geometric model file of a required component is exported from a geometric file library, and the components of the same type only need to export a single component geometric model file;

3) carrying out parallel grid division on the single-component geometric model;

4) carrying out area decomposition and load balancing on the single-component grid data;

5) adding physical parameters such as boundary conditions, loads, initial conditions and the like to the single-component grid data;

6) outputting grid data of a plurality of components through coordinate geometric transformation; the coordinate geometric transformation is shown in fig. 2, and the geometric transformation mode includes: translation, rotation, mirroring, etc.;

7) and writing the grid data into different grid files, and organizing through the grid control files.

Based on the above thought, the execution flow of the large-scale grid automatic generation method of the embodiment is as follows:

s1, constructing a numerical reactor geometry file library, wherein the numerical reactor geometry file library comprises geometric model files of various components to be subjected to grid division and the geometric positions of the components in the reactor core;

the model files of all the components are written in a GEO format which is a model file format customized by a three-dimensional grid dividing tool Gmsh. The GEO geometric model file adopts a boundary representation method to construct a geometric model, has the characteristics of strong readability and easy manual editing, the data type of the GEO geometric model file is shown in figure 3, and the parameters of the geometric model can be specifically divided into 8 corresponding specific types, namely Point, Line, Circle, Line Loop, Plane Surface, Ruled Surface, Surface Loop and Volume. Data structure as shown in fig. 4, each data type includes integer data with a variable name ID. In addition to the ID, Point-type data also includes x, y, z three-dimensional coordinates; line type and Circle type data include pointer data to Point ID; the Line Loop type data includes pointer data pointing to a Line type or Circle type data ID; the Plane Surface type and Ruled Surface type data include pointer data pointing to a Line Loop type data ID; the Surface Loop type data includes pointer data pointing to Plane Surface type or Ruled Surface type data ID; the Volume type data includes pointer data to the Surface Loop type data ID.

Specifically, as shown in fig. 6, the implementation process for constructing the numerical reactor geometry file library is as follows:

the numerical reactor geometry file library adopts the standard size of a fast neutron reactor core structure, performs primary geometric modeling on each type of assembly, and sets the coordinates of the bottom center point of the geometric model as (0,0, 0). During the CAD modeling of various assemblies in the fast neutron reactor, only one of the various assemblies needs to be modeled by taking the coordinate of the central point as (0,0, 0).

Taking the experimental fast reactor CFER shown in fig. 5 as an example, 712 assemblies of 8 types of fuel assemblies, spent fuel assemblies, steel shielding assemblies, boron shielding assemblies, safety rod assemblies, adjusting rod assemblies, compensating rod assemblies and neutron source assemblies are respectively subjected to GEO geometric modeling.

The distribution mode of 712 fast reactor full core assemblies is multilayer regular hexagonal array, and has a central assembly, the two-dimensional center point coordinate of the central assembly is coordinate axis origin (0, 0), and the center distance of the adjacent assemblies is 61 mm. After each component is numbered, a fast reactor component positioning algorithm is designed to solve the coordinates of the central point of each component, a one-to-one mapping relation between the component numbers and the coordinates of the central points of the components is established, the coordinates of the central points of each component can be determined by using the fast reactor component positioning algorithm, and fixed numbers are distributed to each component. After the expression method of the coordinates of the central points of all the assemblies on each regular hexagonal array of the whole reactor core is determined, a 12-edge boundary line equation of the whole reactor core is constructed manually, so that the generated central points are ensured to be in the range.

After the coordinates of the center points of the 712 assemblies of the experimental fast reactor full core are determined by the method, each assembly is numbered according to the type of the assembly. By filling in the control card, the number set of the required components is input, and the required numerical reactor geometric file set and geometric position data can be derived from the numerical reactor geometric file library.

S2, exporting a geometric model file of the component needing to be subjected to meshing from the numerical reactor geometric file library, and carrying out parallel meshing on the single-component geometric model file to obtain the mesh data of the current component;

specifically, in this embodiment, the implementation process of S2 is as follows:

When the single-component geometric model is subjected to parallel grid division, a three-dimensional finite element grid generator Gmsh is called, a geometric file set derived from a geometric file library is subjected to parallel grid division, an MSH grid file customized by the Gmsh is generated, and single grid files of different types of components are output;

then calling interface programs of a ParMetis library and a Zoltan library by compiling Gmsh, carrying out regional decomposition and load balancing processing on the MSH grid file, dividing to obtain grid data of a plurality of partitions of each type of single component, and writing the obtained grid data into different grid files;

by writing a physical parameter loading program facing the MSH grid data structure, adding physical parameters necessary for finite element solution of boundary conditions, loads, initial conditions and the like to the grid subfile sets of the components of various types;

specifically, in the present embodiment, the physical parameters include: boundary conditions, initial conditions, material properties. Wherein the boundary conditions include: displacement boundary conditions and force boundary conditions; the initial conditions include: initial displacement, initial velocity, initial acceleration, initial temperature, and initial state variables; the material properties include: density, modulus of elasticity, poisson's ratio, and coefficient of thermal expansion.

And S3, obtaining the grid data of the required fast reactor whole core or the multi-component through coordinate geometric transformation based on the grid data of the current component and the geometric position of the current component in the core.

Specifically, in this embodiment, the step S3 is to write a large-scale grid data expansion program to automatically generate data from a single-component grid file to a multi-component grid file, or even a full core grid file. The flow is shown in fig. 7, a plurality of grid subfiles are read in parallel, and the number of output grid files is equal to the total number of processes, so that the linear increase of the number of grids and the number of grid subfiles is realized.

The grid data mainly comprises grid node data, grid unit data and various control parameters: the grid node data is used for explaining the coordinates of each grid node; the grid cell data is used for explaining which grid nodes each grid cell is composed of; the control parameters are used to describe various parameter options that affect the problem solution, including physical parameters such as boundary conditions, material properties, initial conditions, and the like.

After the grid subfile set added with the physical parameters is obtained, the grid subfile set and the geometric position data of a single component are read through a large-scale grid data expansion program, and the required grid data of the fast reactor full reactor core or the multiple components are output through the movement and conversion of grid node coordinates, the conversion of grid node and grid unit numbers and the conversion of control parameters.

By performing cross-over and compensation Boolean operation on the grid data, a full reactor core or multi-component large-scale grid file which accords with the actual condition and can be used for the structural mechanics numerical simulation of the fast neutron reactor is output, and a grid data organization file is automatically generated. The grid data organization file is used for organizing the logical relationship of each grid file, and the logical relationship is input into the numerical reactor structural mechanics analysis and calculation software to carry out structural mechanics numerical simulation.

The following describes the procedure used in the above steps:

1. fast reactor assembly positioning program (C + + description)

1) Center point coordinate data structure

typedef struct LR{

string l；

string r；

}LR；

Wherein:

l is an x-axis coordinate; and r is the y-axis coordinate. In the fast reactor full core assembly, the same type of assembly is moved and converted, and only the x-axis coordinate and the y-axis coordinate are required to be converted, so that the z-axis coordinate is not required to be set.

2) Fast reactor assembly positioning algorithm

Wherein:

the distribution mode of 712 assemblies of the whole reactor core is a multilayer regular hexagonal array, and a central assembly (an initial assembly, coordinates of a two-dimensional central point are coordinate axes origin (0, 0)) is arranged, and the center distance between adjacent fuel assemblies is 61 mm. Designing a related program, and expressing the coordinates of the center point of each component by using three layers of loop statements as follows:

and (3) first-layer circulation: starting from the initial assembly, the initial assembly is expanded outwards in sequence along a certain fixed direction, wherein the vertical line in fig. 4 is selected as the fixed direction, and the layer cycle can show the center point coordinate of a certain assembly in each layer of array layer by layer. The coordinate expression of the center point of the component in the fixed direction is as follows:

x＝0

y＝0.061i

wherein i is 0, 1, 2, ….

And (3) second-layer circulation: starting from the component with the maximum longitudinal coordinate value of the central point on the array of the layer, sequentially recursing along the edge where the clockwise direction is located, and the loop of the layer can represent the coordinates of the central points of all the components on the initial edge (the edge where all the nodes with the node coordinate rotation angle of 0 in the loop of the third layer) in the regular hexagon array one by one. The coordinate expression of the center point of the component on the initial edge is as follows:

x＝0.0305×sqrtl(3)j

y＝0.061i-0.0305j

wherein, i is 0, 1, 2, …, j is 0, 1, 2, ….

And a third layer of circulation: starting from a certain assembly on the first edge, carrying out coordinate rotation for 6 times in sequence around the origin of coordinates, wherein the rotation angles are respectively 0, pi/3, 2 pi/3, pi, 4 pi/3 and 5 pi/3, and the layer cycle can represent the coordinates of the central points of all assemblies on the layer array one by one. The coordinate rotation expression is:

x1＝x cosθ+y sinθ

y1＝-x sinθ+y cosθ

where θ is the rotation angle.

After the expression method of the coordinates of the central points of all the assemblies on each regular hexagonal array of the whole reactor core is determined, an equation of 12 boundary lines of the whole reactor core is constructed manually, so that the generated central points are ensured to be in the range.

2. Physical parameter adding program (C + + description)

1) Physical parameter-related data structure:

wherein:

group is the group number of the physical parameter; name is the alias of the physical parameter group; the mesh _ tag is a physical tag object; tags is a physical parameter set; element _ to _ tags is a hash table of the physical parameter set corresponding to the grid cell.

2) Physical parameter adding implementation method

Wherein:

and traversing each grid node/grid unit by creating a grid iterator, and traversing the corresponding physical parameter group in the hash table, thereby realizing the setting of the physical parameters.

3. Large-scale mesh data extension program (C + + description)

1) Program main function:

wherein:

inputting parameters: the mesh is an input single-component grid file; v _ num is the number of input mesh nodes; r _ num is the number of input grid cells; r _ num is the number of grid cell number offsets; f _ num is the number of the single-component grid partitions; an output file is an output mesh file. The program is realized based on MPI, the grids of different partitions are generated in parallel in a plurality of processes by using MPI related functions, and the high-efficiency generation of the large-scale grid of the whole core assembly can be realized by fully utilizing the computing nodes in the supercomputer.

2) Mesh node/cell data structure:

typedef struct Object{

string name；

string id；

string coords[4]；

vector<string>shared_part；

vector<string>physical_labels；

}Object；

wherein:

name is a mesh entity type, which can be a node (mesh node) and LTRSpace (tetrahedral mesh unit); id is the number in the grid entity component; if the type of the grid entity is a node, the coords are three-dimensional coordinates x, y and z of the grid node, and if the type of the grid entity is LTRSpace, the coords are four node ids forming the unit; shared _ part is a shared partition number set; physical _ labels is a set of physical tags.

Because the invention is used for generating large-scale grid data, the number of grid nodes/units and the number of shared partitions are quite large integers, and if int-type variables are adopted, unknown errors can occur during compiling and running on different machines, so string-type variables are adopted to represent the two types of numbers. When the two types of serial numbers are added, subtracted and multiplied in a program, a correlation function is written to realize the addition of large numbers and the multiplication of large numbers.

3) Data partitioning function:

Object split_objs(string&objs1)；

wherein:

the objs1 is a section of the mesh information data read in.

The function is used for reading the initial assembly MSH grid file data section and carrying out data segmentation on grid nodes and grid unit data according to the variable types in the grid node/unit structure body.

4) Grid node data geometric transformation function:

void change_point(ofstream&fout,Object&p,int&n,LR&lr)；

wherein:

fout is a file write variable; p is a segmented mesh node data segment; n is a partition number; lr is the center point coordinates of the component.

The function is used for reallocating the grid node numbers of the initial assembly, performing geometric transformation on all grid node coordinates according to read-in assembly center coordinates, and converting physical label data and shared partition data of the grid nodes.

The specific implementation method comprises the following steps: adding lr.l and lr.r to the data corresponding to the x and y coordinates of the grid node in the initial assembly MSH file; and reassigning the numbers of the nodes newly generated according to the geometric transformation of the coordinates according to the number of the node numbers in the MSH grid file of the initial component to ensure that the numbers of all the nodes are not repeated, for example: if the number of the grid nodes of the initial component is k and the read component partition number is n, the grid node numbers of all the components are 1-k, k + 1-2 k, 2k + 1-3 k, …, nk + 1-n +1 k respectively. And simultaneously, converting the physical label data and the shared partition data according to the read partition number n.

5) Grid cell data transfer function:

void change_element(ofstream&fout,Object&p,int&n)；

wherein:

fout is a file write variable; p is a segmented grid unit data segment; n is a partition number.

The function is used for reassigning the grid cell number of the initial component and copying and converting the physical tag data of the grid cell.

The specific implementation method comprises the following steps: the grid cells are reassigned numbers according to the number of cell numbers in the initial assembly MSH grid file to ensure that the numbers of all cells are not repeated, for example: if the number of the grid cells of the initial assembly is m and the read-in assembly partition number is n, the grid cell numbers of all the assemblies are 1-m, m + 1-2 m, 2m + 1-3 m, …, nm + 1-n +1 in sequence. And simultaneously, copying and converting the physical label data and the shared partition data according to the read partition number n.

6) Solving parameter setting:

before and after the data of the grid nodes and the grid units are written, necessary solving parameters are added according to the input requirements of finite element calculation software. This section is used to add the parameter options required for the input file (in file) of the finite element software OOFEM to the mesh file.

In summary, in the embodiment, the geometric information of different types of assemblies is described by constructing a numerical reactor geometry file library, and the geometric position of a single assembly in the reactor core is determined; carrying out initial grid division on the single-component geometric file, and carrying out region decomposition, load balancing and physical parameter setting on the obtained initial grid data; large-scale grid data for the full core or the multiple components is generated based on the single component grid data. According to the method of the embodiment, geometric modeling and initial meshing are carried out on a single assembly, all assembly meshes of the whole reactor core are automatically generated, and meanwhile, the obtained mesh files are converted into large-scale mesh input files which can be directly used by a general finite element solver, so that high-fidelity simulation of the mechanical behavior of the whole reactor core assembly of the reactor is realized.

Second embodiment

The embodiment provides an automatic large-scale grid generation system for a fast neutron reactor full core structure, as shown in fig. 1, the automatic large-scale grid generation system includes the following modules:

The automatic generation system of the fast reactor full core structure large-scale grid of the embodiment corresponds to the automatic generation method of the fast reactor full core structure large-scale grid of the first embodiment; the functions realized by each functional module in the automatic large-scale grid generation system of the fast reactor full core structure correspond to the flow steps in the method of the first embodiment one by one; therefore, it is not described herein.

Third embodiment

The present embodiment provides an electronic device, which includes a processor and a memory; wherein the memory has stored therein at least one instruction that is loaded and executed by the processor to implement the method of the first embodiment.

The electronic device may have a relatively large difference due to different configurations or performances, and may include one or more processors (CPUs) and one or more memories, where at least one instruction is stored in the memory, and the instruction is loaded by the processor and executes the method.

Fourth embodiment

The present embodiment provides a computer-readable storage medium, in which at least one instruction is stored, and the instruction is loaded and executed by a processor to implement the method of the first embodiment. The computer readable storage medium may be, among others, ROM, random access memory, CD-ROM, magnetic tape, floppy disk, optical data storage device, and the like. The instructions stored therein may be loaded by a processor in the terminal and perform the above-described method.

Furthermore, it should be noted that the present invention may be provided as a method, apparatus or computer program product. Accordingly, embodiments of the present invention may take the form of an entirely hardware embodiment, an entirely software embodiment or an embodiment combining software and hardware aspects. Furthermore, embodiments of the present invention may take the form of a computer program product embodied on one or more computer-usable storage media having computer-usable program code embodied in the medium.

Embodiments of the present invention are described with reference to flowchart illustrations and/or block diagrams of methods, terminal devices (systems), and computer program products according to embodiments of the invention. It will be understood that each flow and/or block of the flow diagrams and/or block diagrams, and combinations of flows and/or blocks in the flow diagrams and/or block diagrams, can be implemented by computer program instructions. These computer program instructions may be provided to a processor of a general purpose computer, embedded processor, or other programmable data processing terminal to produce a machine, such that the instructions, which execute via the processor of the computer or other programmable data processing terminal, create means for implementing the functions specified in the flowchart flow or flows and/or block diagram block or blocks.

These computer program instructions may also be stored in a computer-readable memory that can direct a computer or other programmable data processing terminal to function in a particular manner, such that the instructions stored in the computer-readable memory produce an article of manufacture including instruction means which implement the function specified in the flowchart flow or flows and/or block diagram block or blocks. These computer program instructions may also be loaded onto a computer or other programmable data processing terminal to cause a series of operational steps to be performed on the computer or other programmable terminal to produce a computer implemented process such that the instructions which execute on the computer or other programmable terminal provide steps for implementing the functions specified in the flowchart flow or flows and/or block diagram block or blocks.

It should also be noted that, in this document, the terms "comprises," "comprising," or any other variation thereof, are intended to cover a non-exclusive inclusion, such that a process, method, article, or terminal that comprises a list of elements does not include only those elements but may include other elements not expressly listed or inherent to such process, method, article, or terminal. Without further limitation, an element defined by the phrase "comprising an … …" does not exclude the presence of other like elements in a process, method, article, or terminal that comprises the element.

Finally, it should be noted that while the above describes a preferred embodiment of the invention, it will be appreciated by those skilled in the art that, once the basic inventive concepts have been learned, numerous changes and modifications may be made without departing from the principles of the invention, which shall be deemed to be within the scope of the invention. Therefore, it is intended that the appended claims be interpreted as including preferred embodiments and all such alterations and modifications as fall within the scope of the embodiments of the invention.

Claims

1. The method for automatically generating the large-scale grid of the full reactor core structure of the fast neutron reactor is characterized by comprising the following steps of:

2. The method for automatically generating the large-scale grid of the fast neutron reactor full core structure according to claim 1, wherein the constructing of the numerical reactor geometry file library comprises:

3. The method for automatically generating the large-scale grid of the fast neutron reactor full core structure according to claim 2, wherein deriving the geometric model file of the component to be gridded from the numerical reactor geometric file library comprises:

4. The method for automatically generating the large-scale grid of the fast neutron reactor full core structure according to claim 1, wherein the parallel grid division of the single-component geometric model file comprises the following steps:

5. The method for automatically generating the large-scale grid of the fast neutron reactor full core structure according to claim 1, wherein the grid data comprises grid node data, grid unit data and various control parameters;

the grid node data is used for explaining the coordinates of each grid node;

6. The method for automatically generating the large-scale grid of the fast reactor full core structure according to claim 5, wherein the step of obtaining the grid data of the required fast reactor full core or the required multiple components through coordinate geometric transformation based on the grid data of the current components and the geometric positions of the current components in the core comprises the following steps:

7. The utility model provides a large-scale grid automatic generation system of full reactor core structure of fast neutron reactor, its characterized in that, the large-scale grid automatic generation system of full reactor core structure of fast neutron reactor includes:

8. The fast neutron reactor full core structure large-scale grid automatic generation system of claim 7, wherein the construction process of the numerical reactor geometry file library comprises:

9. The system for automatically generating a large-scale grid of a fast neutron reactor full core structure according to claim 8, wherein the grid initial partitioning and preprocessing module is specifically configured to:

10. The system for automatically generating a large-scale grid of a fast neutron reactor full core structure of claim 7, wherein the grid data comprises grid node data, grid unit data and various types of control parameters; the grid node data is used for explaining the coordinates of each grid node; the grid cell data is used for explaining which grid nodes each grid cell is composed of; the control parameters are used for explaining various parameter options influencing the problem solving, and the parameter options comprise boundary conditions, material properties and initial conditions; the massively parallel grid data generation module is specifically used for generating the grid data;