CN114077763A - Nuclear power plant containment vessel structure determining method and device - Google Patents
Nuclear power plant containment vessel structure determining method and device Download PDFInfo
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Abstract
The invention provides a containment structure determination method and a containment structure determination device for a nuclear power plant, wherein the containment structure determination method comprises the following steps: determining an analysis model according to the arrangement information and the load information of the nuclear power plant; obtaining a displacement field of an analysis model under a target load according to the arrangement information of the nuclear power plant, the load information and the analysis model, wherein the load information comprises the target load; and determining the structure of the containment according to the displacement field. In the embodiment of the invention, the displacement field of the analysis model under the target load is obtained, and the containment structure of the nuclear power plant is determined according to the displacement field result obtained under the target load, so that the displacement field under each load action is solved only once without repeated solving. Compared with the prior art, the method has the advantages that when the load effect combination is sequentially and directly solved, the displacement field under the load effect can be repeatedly solved at least twice, labor and time costs are saved, and the problems of long design period and high design labor cost existing in the design of the containment structure of the nuclear power plant are solved.
Description
Technical Field
The invention relates to the technical field of nuclear power plants, in particular to a method and a device for determining a containment structure of a nuclear power plant.
Background
Nuclear power is used as an economic and efficient clean energy and is widely applied in the world. The raw materials required by nuclear power generation are extremely radioactive, and catastrophic consequences can be caused once leakage occurs, so that the structural design of a nuclear power plant as a base for producing nuclear power is stricter than the safety requirement of a common building design, and more loads need to be considered. Structural designers usually need to apply load on the structure, obtain the displacement field of the structure, obtain the stress field according to the displacement field, and then design the structural reinforcement according to the obtained stress field and the design specification. In the prior art, to solve the displacement field of a combined load, all loads of the combined load need to be added to the solution, and the displacement field under the action of a load can be repeatedly solved at least twice. The method can well meet the structural design of simple load, the displacement field under the action of one load can be solved at least twice repeatedly, the total solving time and manpower cannot be obviously influenced, but the method is used for the structural design of a nuclear power plant with complex load, the number of load combinations needing to be considered in the structural design of the nuclear power plant is at least more than 200, and by adopting the method, a lot of manpower and time need to be consumed, so that the problems of long design period and high design manpower cost exist.
Disclosure of Invention
The embodiment of the invention provides a containment structure determination method and device for a nuclear power plant, and solves the problems of long design period and high design labor cost of the containment structure design of the nuclear power plant.
The first aspect of the embodiment of the invention provides a containment structure determination method for a nuclear power plant, which comprises the following steps:
determining an analysis model according to the arrangement information and the load information of the nuclear power plant;
obtaining a displacement field of an analysis model under a target load according to the arrangement information of the nuclear power plant, the load information and the analysis model, wherein the load information comprises the target load;
and determining the structure of the containment according to the displacement field.
Optionally, the obtaining, according to the nuclear power plant arrangement information, the load information, and the analysis model, a displacement field of the analysis model under a target load, where the load information includes the target load, includes:
performing statics analysis according to the arrangement information and the load information of the nuclear power plant to obtain a first displacement field of an analysis model under the load action without considering inertia and damping effect;
carrying out thermal stress analysis according to the arrangement information and the load information of the nuclear power plant to obtain a second displacement field of the load of the analysis model under the action of temperature;
performing dynamic analysis according to the arrangement information and the load information of the nuclear power plant to obtain a third displacement field of the analysis model under the action of the earthquake;
and summing the first displacement field, the second displacement field and the third displacement field according to preset weight to obtain the displacement field.
Optionally, determining an analysis model according to the nuclear power plant arrangement information and the load information includes:
establishing a geometric model according to the nuclear power plant arrangement information and the load information;
and carrying out grid division on the geometric model to obtain an analysis model.
Optionally, the grid division is performed on the geometric model to obtain an analysis model, and the method includes:
carrying out mesh division on the geometric model to obtain an initial model;
carrying out structural statics analysis by using the initial model to obtain an analysis result;
adjusting the initial model according to the analysis result to obtain an intermediate model;
taking the intermediate model as an initial model, executing structural statics analysis by using the initial model to obtain an analysis result, adjusting the initial model according to the analysis result, and obtaining the intermediate model until the analysis result meets a preset condition;
and determining the finally obtained intermediate model as the analysis model.
A second aspect of an embodiment of the present invention provides a containment structure determination device for a nuclear power plant, including:
the first acquisition module is used for determining an analysis model according to the arrangement information and the load information of the nuclear power plant;
the second acquisition module is used for acquiring a displacement field of the analysis model under a target load according to the arrangement information of the nuclear power plant, the load information and the analysis model, wherein the load information comprises the target load;
and the determining module is used for determining the structure of the containment according to the displacement field.
Optionally, the second obtaining module includes:
the first obtaining submodule is used for carrying out statics analysis according to the arrangement information and the load information of the nuclear power plant to obtain a first displacement field of the analysis model under the load action without considering inertia and damping effect;
the second acquisition submodule is used for carrying out thermal stress analysis according to the arrangement information and the load information of the nuclear power plant to obtain a second displacement field of the load of the analysis model under the action of temperature;
the third acquisition submodule is used for performing dynamic analysis according to the arrangement information and the load information of the nuclear power plant to acquire a third displacement field of the analysis model under the action of the earthquake;
and the first determining submodule is used for summing the first displacement field, the second displacement field and the third displacement field according to preset weight to obtain the displacement field.
Optionally, the first obtaining module includes:
the establishing submodule is used for establishing a geometric model according to the nuclear power plant arrangement information and the load information;
and the obtaining submodule is used for carrying out grid division on the geometric model to obtain an analysis model.
Optionally, the obtaining sub-module includes:
carrying out mesh division on the geometric model to obtain an initial model;
carrying out structural statics analysis by using the initial model to obtain an analysis result;
adjusting the initial model according to the analysis result to obtain an intermediate model;
taking the intermediate model as an initial model, executing structural statics analysis by using the initial model to obtain an analysis result, adjusting the initial model according to the analysis result, and obtaining the intermediate model until the analysis result meets a preset condition;
and determining the finally obtained intermediate model as the analysis model.
A third aspect of embodiments of the present invention provides an electronic device, including a processor, a memory, and a computer program stored on the memory and executable on the processor, where the computer program, when executed by the processor, implements the steps in the method for determining a containment structure of a nuclear power plant according to the first aspect.
A fourth aspect of the embodiments of the present invention provides a readable storage medium, which stores a program that, when executed by a processor, implements the steps in the method for determining a containment structure of a nuclear power plant according to the first aspect.
In the embodiment of the invention, the displacement field of the analysis model under the target load is obtained, and the containment structure of the nuclear power plant is determined according to the displacement field result obtained under the target load, so that the displacement field under each load action is solved only once without repeated solving. Compared with the prior art, the method has the advantages that when the load effect combination is sequentially and directly solved, the displacement field under the load effect can be repeatedly solved at least twice, labor and time costs are saved, and the problems of long design period and high design labor cost existing in the design of the containment structure of the nuclear power plant are solved.
Drawings
In order to more clearly illustrate the technical solutions in the embodiments of the present invention, the drawings in the specification are described below, it is obvious that the drawings are only embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to the drawings without creative efforts.
FIG. 1 is one of flow charts of a nuclear power plant containment structure determination method provided by an embodiment of the invention;
FIG. 2 is a block diagram of a nuclear power plant containment structure determination apparatus provided by an embodiment of the present invention;
FIG. 3 is a block diagram of an electronic device provided by an embodiment of the invention;
FIG. 4 is a load diagram contemplated by embodiments of the present invention;
FIG. 5 is a combined graph of loading effects considered in the prior art;
fig. 6 is a second flowchart of a containment structure determination method for a nuclear power plant according to an embodiment of the present invention.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. On the basis of the embodiments of the present invention, all other embodiments obtained by a person of ordinary skill in the art without any inventive work are within the scope of the present invention.
In a first aspect, an embodiment of the present invention provides a containment structure determination method for a nuclear power plant, and referring to fig. 1 and fig. 6, the method may be applied to an electronic device, and includes:
102, obtaining a displacement field of an analysis model under a target load according to arrangement information of the nuclear power plant, the load information and the analysis model, wherein the load information comprises the target load;
and 103, determining the structure of the containment according to the displacement field.
In step 101, the nuclear power plant arrangement information includes location information of the nuclear power plant containment and usage requirements of the nuclear power plant containment. Load, refers to external forces and other factors that cause internal forces and deformation of a structure or component. For containment vessel of nuclear power plant, the load includes normalThe load caused by the pressure and the temperature generated by serious accidents, abnormal load, severe environmental load, extreme environmental load, and load caused by flying objects or external artificial events. As shown in fig. 4, the normal load includes a permanent load D, a live load L, a load F generated by a design prestress, etc., and the severe environmental load includes a load W applied to the containment vessel due to internal flooding and a seismic action E generated by an operational safety earthquake1For details, refer to fig. 4, which is not described herein.
In the embodiment of the invention, a geometric model can be established firstly according to the arrangement information and the load information of the nuclear power plant. When the geometric model is established, it should be understood that the containment structure of the nuclear power plant comprises a containment and an external water tank, the arrangement information of the nuclear power plant can be firstly input in the geometric model modeling, then one or more pieces of three-dimensional modeling software are selected, and the modeling is carried out according to the arrangement information and the load information of the nuclear power plant to obtain the geometric model.
Cell attributes may be defined and gridded according to the resulting geometric model. Cell attributes include cell type, material properties, cross-sectional properties, cell coordinates, and the like. The unit type comprises a solid unit and a shell unit, the concrete of the containment vessel is defined as the solid unit, the steel lining is defined as the shell unit, and the external water tank can be defined as the solid unit or the shell unit; the section characteristic of the concrete is a 3D (three-dimensional) deformation body, and the section characteristic of the steel lining is a 3D deformation body with a certain thickness value; the unit coordinate system of the containment cylinder part and the external water tank is unified with a cylindrical coordinate system taking the origin of the containment as the origin, and the unit coordinate system of the containment dome part is unified with a spherical coordinate system taking the sphere center as the origin. The grid division can be realized by selecting software and drawing up the grid size by combining computer configuration and personal engineering experience. When the grids are divided, the shell grids are divided into quadrilateral grids as much as possible, the body grids are divided into hexahedral grids as much as possible, and only the parts with less attention to the structure are triangular grids or tetrahedral grids.
The model after defining the unit attributes and carrying out the grid division can be subjected to structural statics analysis by selecting software with a structural analysis function, and the grid size of the model is adjusted according to an analysis result until a model which can ensure higher calculation precision and calculation efficiency is obtained, and the model can be determined as an analysis model.
In step 102, it is understood that in obtaining the displacement field of the analytical model under the target load, the analytical model should be adjusted according to different load types. Such as: when the load is calculated to enable the steel lining to be in the displacement field of the elastic stage, the analysis model can be directly determined as a first analysis sub-model without adjusting the analysis model, and the first analysis sub-model is used for calculating the load to enable the steel lining to be in the displacement field of the elastic stage; when the load is calculated to enable part of the steel lining to enter a displacement field of a plasticity stage, the steel lining unit entering the plasticity stage under the load needs to be deleted from the analysis model to obtain a second analysis sub-model, wherein the second analysis sub-model is used for calculating the load to enable part of the steel lining to enter the displacement field of the plasticity stage; when the displacement field under the temperature acting load is calculated, the unit attribute is modified into the thermal unit attribute on the basis of the analysis model to obtain a third analysis submodel, and the third analysis submodel is used for analyzing the displacement field under the temperature acting load; when a displacement field under the earthquake action load is calculated, on the basis of an analysis model, a mass unit is added or the material density is modified to consider the influence of an additional constant load and a converted active load on the earthquake response of the containment, and the mass unit is added or the material density of the wall of the water tank is modified to consider the influence of the water body in the external water tank on the earthquake response of the containment. The modified analysis model is a fourth analysis submodel, and the fourth analysis submodel is used for structural modal analysis, structural spectrum analysis or dynamic time course analysis; when the simulation of the prestressed tendons is considered, a unit for simulating the prestressed tendons is added on the basis of an analysis model to obtain a fifth analysis submodel, wherein in the fifth analysis submodel, the prestressed tendons and the concrete are usually modeled in a non-common node separation mode, the correlation action between the prestressed tendons and the concrete is simulated by setting coupling or constraint, the specific methods comprise a one-to-one corresponding coupling method, a constraint equation method and an arbitrary Lagrange-Eulerian method, and for a small model, the three methods have small difference between the calculation efficiency and the calculation result; for a large model, the one-to-one correspondence coupling method has low calculation efficiency, and the difference between the calculation efficiency of the constraint equation method and any Lagrange-Eulerian method and the calculation result is not large. And the fifth analysis submodel is used for structural prestress effect simulation analysis.
The loads borne by the containment vessel of the nuclear power plant comprise normal loads, abnormal loads, severe environmental loads, extreme environmental loads and other different types of loads. Each load is provided with an analysis model suitable for solving, the analysis models are the first analysis submodel, the second analysis submodel, the third analysis submodel, the fourth analysis submodel and the fifth analysis submodel, all the loads borne by the containment vessel of the nuclear power plant are respectively applied to the analysis models suitable for solving, and the displacement field under each load is solved in batch through programming.
And obtaining a load which can be solved by the analysis model in the displacement field of the analysis model under the target load as the target load of the analysis model, for example, the load which can be solved by the first sub-analysis model under the load action as the target load of the first sub-analysis model.
Specifically, as shown in fig. 6, a displacement field of the analysis model under the target load is obtained, and when it is determined that the loads except for the temperature effect, the earthquake effect and the prestress are applicable to the first sub-analysis model or the second sub-analysis model, the loads are sequentially applied to the first sub-analysis model to perform static solution to obtain the displacement field and the stress field of the entire containment vessel. And analyzing the displacement field and stress field results of the steel lining, and if the results show that the steel lining is partially yielded, applying the load to a second sub-analysis model for structural statics analysis. And then, calculating the displacement field of all loads borne by the containment vessel of the nuclear power plant under the corresponding analysis model through programming batch.
And summarizing the displacement fields of the loads, judging whether the obtained displacement field result of the loads is reasonable or not according to personal engineering experience, checking and correcting if the result is unreasonable, re-solving the displacement field of the loads, and determining the structure of the containment according to the obtained displacement field of the loads if the result is reasonable.
In step 103, determining the structure of the containment vessel according to the displacement fields means that the displacement fields under all loads are summed according to the corresponding weights of the displacement fields according to the design specifications of the nuclear power plant to obtain the displacement fields of the containment vessel of the nuclear power plant under the action of all the loads, and the weights are obtained by consulting the design specifications of the nuclear power plant. Calculating to obtain a stress field according to the displacement field of the containment vessel of the nuclear power plant under the action of all loads, then obtaining the internal force and the reinforcement area according to the obtained stress field, and finally designing the structural reinforcement according to the design specification of the nuclear power plant by referring to the internal force and the reinforcement area to determine the structure of the containment vessel. Since the process of finally determining the structure of the containment vessel from the displacement field is a common solving means in the existing structural design, the process will not be described in detail here.
In the embodiment of the invention, the displacement field of the analysis model under the target load is obtained, and the containment structure of the nuclear power plant is determined according to the displacement field result obtained under the target load, so that the displacement field under each load action is solved only once without repeated solving. Compared with the prior art, the method has the advantages that when the load effect combination is sequentially and directly solved, the displacement field under the load effect can be repeatedly solved at least twice, labor and time costs are saved, and the problems of long design period and high design labor cost existing in the design of the containment structure of the nuclear power plant are solved.
Referring to fig. 5, it is clear that in the prior art, when load effect combinations are directly solved in sequence, the displacement field under one load effect is solved at least twice repeatedly, for example, the permanent load D is solved once every time the permanent load D is solved. It should be understood that the meaning of the symbols in fig. 5 is the same as that of the symbols in fig. 4, and the description thereof is omitted.
Optionally, the obtaining, according to the nuclear power plant arrangement information, the load information, and the analysis model, a displacement field of the analysis model under a target load, where the load information includes the target load, includes:
performing statics analysis according to the arrangement information and the load information of the nuclear power plant to obtain a first displacement field of an analysis model under the load action without considering inertia and damping effect;
carrying out thermal stress analysis according to the arrangement information and the load information of the nuclear power plant to obtain a second displacement field of the load of the analysis model under the action of temperature;
performing dynamic analysis according to the arrangement information and the load information of the nuclear power plant to obtain a third displacement field of the analysis model under the action of the earthquake;
and summing the first displacement field, the second displacement field and the third displacement field according to preset weight to obtain the displacement field.
The statics analysis is used for calculating displacement, stress, strain and internal force of the containment vessel of the nuclear power plant under the load effect without considering inertia and damping effect.
The thermal stress analysis is a coupled field analysis of thermal analysis and structural statics analysis. When the node temperature (the node refers to the corner of the grid obtained by dividing the containment vessel of the nuclear power plant) is known, the node temperature can be directly applied to the corresponding node as a boundary condition to obtain a structural analysis result. When the node temperature is unknown, a structural thermal stress analysis structure can be indirectly obtained through two-step analysis, thermal analysis is firstly carried out, steady-state thermal analysis or transient thermal analysis can be selected according to requirements, the temperature field of the steady-state thermal analysis does not change along with time, and the transient thermal analysis reacts on the change relation of the temperature field along with time; and applying the obtained node temperature as a body load to a node in the structural analysis to obtain a structural analysis result. The results of thermal and structural analysis can also be obtained by using a coupling unit with temperature and displacement freedom, directly taking into account the thermo-structural coupling effect.
Performing dynamic analysis, namely performing modal analysis to obtain the structural dynamic characteristics under the action of earthquake, and then performing spectral analysis or transient dynamic analysis; and directly performing transient dynamics analysis under the action of the missile.
Adjusting the analysis model to respectively obtain a first displacement field of the analysis model under the load action without considering inertia and damping effect, a second displacement field of the analysis model under the temperature action and a third displacement field under the earthquake action, and summing the first displacement field, the second displacement field and the third displacement field according to preset weight according to the design specification of the nuclear power plant to obtain the displacement fields. The preset weight is determined by the design specification of the nuclear power plant and is not described herein.
Optionally, determining an analysis model according to the nuclear power plant arrangement information and the load information includes:
establishing a geometric model according to the nuclear power plant arrangement information and the load information;
and carrying out grid division on the geometric model to obtain an analysis model.
In the embodiment of the invention, according to the arrangement information and the load information of the nuclear power plant, the structural model can be simplified firstly, and then the geometric model is established according to the simplified result of the structural model. When the structural model is simplified, load paths need to be constructed and each structural member needs to be classified from a physical geometric layer. In the process of constructing the load path, any structural or non-structural requirements cannot interrupt the load path, and the joints among the structural components must also ensure that all structural internal forces required by the whole load path can be transmitted on the connecting points so as to ensure the integrity of the load path. Classifying the structural components from a physical geometry layer, judging which type the structural components belong to thin plates, thick plates, deep beams, common beams, thin walls, thick walls, short columns, long columns, common columns, inclined supports and the like, classifying the structural components, and selecting proper unit types for the structural components in the subsequent analysis model modeling to simulate. It should be noted that the structure is selectable, has no fixed mode, changes the load transmission path, and can be changed correspondingly.
When the geometric model is established, it should be understood that the containment structure of the nuclear power plant comprises a containment and an external water tank, the arrangement information of the nuclear power plant can be firstly input in the geometric model modeling, then one or more pieces of three-dimensional modeling software are selected, and the modeling is carried out according to the arrangement information and the load information of the nuclear power plant to obtain the geometric model.
Cell attributes may be defined and gridded according to the resulting geometric model. Cell attributes include cell type, material properties, cross-sectional properties, cell coordinates, and the like. The unit type comprises a solid unit and a shell unit, the concrete of the containment vessel is defined as the solid unit, the steel lining is defined as the shell unit, and the external water tank can be defined as the solid unit or the shell unit; the section characteristic of the concrete is a 3D (three-dimensional) deformation body, and the section characteristic of the steel lining is a 3D deformation body with a certain thickness value; the unit coordinate system of the containment cylinder part and the external water tank is unified with a cylindrical coordinate system taking the origin of the containment as the origin, and the unit coordinate system of the containment dome part is unified with a spherical coordinate system taking the sphere center as the origin. The grid division can be realized by selecting software and drawing up the grid size by combining computer configuration and personal engineering experience. When the grids are divided, the shell grids are divided into quadrilateral grids as much as possible, the body grids are divided into hexahedral grids as much as possible, and only the parts with less attention to the structure are triangular grids or tetrahedral grids.
The model after defining the unit attributes and carrying out the grid division can be subjected to structural statics analysis by selecting software with a structural analysis function, and the grid size of the model is adjusted according to an analysis result until a model which can ensure higher calculation precision and calculation efficiency is obtained, and the model can be determined as an analysis model.
Optionally, the grid division is performed on the geometric model to obtain an analysis model, and the method includes:
carrying out mesh division on the geometric model to obtain an initial model;
carrying out structural statics analysis by using the initial model to obtain an analysis result;
adjusting the initial model according to the analysis result to obtain an intermediate model;
taking the intermediate model as an initial model, executing structural statics analysis by using the initial model to obtain an analysis result, adjusting the initial model according to the analysis result, and obtaining the intermediate model until the analysis result meets a preset condition;
and determining the finally obtained intermediate model as the analysis model.
For the process, a piece of software capable of carrying out meshing is selected, the mesh size is drawn up by combining computer configuration and personal engineering experience, and the geometric model is subjected to meshing. When the grids are divided, the shell grids are divided into quadrilateral grids as much as possible, the body grids are divided into hexahedral grids as much as possible, and only the parts with less attention to the structure are triangular grids or tetrahedral grids.
Setting boundary conditions on the geometric model after grid division, wherein the setting rule of the boundary conditions is as follows: if the soil-knot interaction is considered, arranging a spring-damper unit simulating soil on the bottom surface of the raft foundation of the containment vessel; if the soil-knot interaction is not considered, the solid connection is arranged on the bottom surface of the raft foundation of the containment vessel.
And applying any voltage-sharing value to the geometric surface or grid node or grid surface of the whole inner wall of the containment vessel in the geometric model which is subjected to grid division and is set with the boundary condition so as to obtain the initial model.
And selecting a piece of software with a structure analysis function to perform structural statics analysis on the initial model to obtain an analysis result. If the analysis result is not converged, adjusting the grid size of the division geometric model in the initial model to obtain an intermediate model, taking the intermediate model as the initial model, executing structural statics analysis by using the initial model to obtain an analysis result, and adjusting the initial model according to the analysis result to obtain the intermediate model until the analysis result is converged.
And after the analysis result is converged, judging whether the converged analysis result is reasonable according to personal engineering experience, if not, adjusting the grid size of a geometric model divided in an initial model to obtain an intermediate model, taking the intermediate model as the initial model, executing structural statics analysis by using the initial model to obtain an analysis result, adjusting the initial model according to the analysis result to obtain the intermediate model, and determining the geometric model corresponding to the converged analysis result as the analysis model until the converged analysis result is normal.
In order to obtain an analysis model with a more accurate calculation result, the grid size sensitivity analysis can be further performed on the analysis model, and the calculation result precision can be different for different grid sizes under the same unit attribute, the same boundary condition and the same load. The smaller the mesh size is divided, the higher the calculation accuracy is; when the mesh size is divided larger, the calculation accuracy is worse. The method can program to parameterize the grid size, repeatedly iterate and calculate calculation results under different grid sizes until the calculation results and the calculation results in the last iteration are within a certain tolerance range, and then select a larger grid size from the grid sizes used in the current iteration calculation and the last iteration calculation to perform subsequent finite element analysis so as to ensure higher calculation precision and calculation efficiency.
Referring to fig. 2, fig. 2 is a structural diagram of a nuclear power plant containment structure determining apparatus according to an embodiment of the present invention, and as shown in fig. 2, a nuclear power plant containment structure determining apparatus 200 includes:
the first obtaining module 201 is configured to determine an analysis model according to the nuclear power plant arrangement information and the load information;
the second obtaining module 202 is configured to obtain a displacement field of the analysis model under a target load according to the nuclear power plant arrangement information, the load information, and the analysis model, where the load information includes the target load;
and the determining module 203 is used for determining the structure of the containment according to the displacement field.
Optionally, the second obtaining module 202 includes:
the first obtaining submodule is used for carrying out statics analysis according to the arrangement information and the load information of the nuclear power plant to obtain a first displacement field of the analysis model under the load action without considering inertia and damping effect;
the second acquisition submodule is used for carrying out thermal stress analysis according to the arrangement information and the load information of the nuclear power plant to obtain a second displacement field of the load of the analysis model under the action of temperature;
the third acquisition submodule is used for performing dynamic analysis according to the arrangement information and the load information of the nuclear power plant to acquire a third displacement field of the analysis model under the action of the earthquake;
and the first determining submodule is used for summing the first displacement field, the second displacement field and the third displacement field according to preset weight to obtain the displacement field.
Optionally, the first obtaining module 201 includes:
the establishing submodule is used for establishing a geometric model according to the nuclear power plant arrangement information and the load information;
and the obtaining submodule is used for carrying out grid division on the geometric model to obtain an analysis model.
Optionally, the obtaining sub-module includes:
carrying out mesh division on the geometric model to obtain an initial model;
carrying out structural statics analysis by using the initial model to obtain an analysis result;
adjusting the initial model according to the analysis result to obtain an intermediate model;
taking the intermediate model as an initial model, executing structural statics analysis by using the initial model to obtain an analysis result, adjusting the initial model according to the analysis result, and obtaining the intermediate model until the analysis result meets a preset condition;
and determining the finally obtained intermediate model as the analysis model.
The containment structure determination apparatus 200 of the nuclear power plant can implement each process implemented by the electronic device in the method embodiment of fig. 1, and is not described herein again to avoid repetition.
Referring to fig. 3, fig. 3 is a schematic structural diagram of another electronic device according to an embodiment of the present invention. As shown in fig. 3, the electronic device 300 includes: a processor 301, a memory 302 and a computer program stored on and executable on said memory 302, the various components in the electronic device 300 being coupled together by a bus system 303. It will be appreciated that the bus system 303 is used to enable communications among the components.
The processor 301 is configured to determine an analysis model according to the nuclear power plant arrangement information and the load information;
obtaining a displacement field of an analysis model under a target load according to the arrangement information of the nuclear power plant, the load information and the analysis model, wherein the load information comprises the target load;
and determining the structure of the containment according to the displacement field.
Further, the processor 301 is further configured to obtain a displacement field of the analysis model under a target load according to the nuclear power plant arrangement information, the load information, and the analysis model, where the load information includes the target load, and includes:
performing statics analysis according to the arrangement information and the load information of the nuclear power plant to obtain a first displacement field of an analysis model under the load action without considering inertia and damping effect;
carrying out thermal stress analysis according to the arrangement information and the load information of the nuclear power plant to obtain a second displacement field of the load of the analysis model under the action of temperature;
performing dynamic analysis according to the arrangement information and the load information of the nuclear power plant to obtain a third displacement field of the analysis model under the action of the earthquake;
and summing the first displacement field, the second displacement field and the third displacement field according to preset weight to obtain the displacement field.
Further, the processor 301 is further configured to establish a geometric model according to the nuclear power plant arrangement information and the load information;
and carrying out grid division on the geometric model to obtain an analysis model.
Further, the processor 301 is further configured to perform mesh division on the geometric model to obtain an initial model;
carrying out structural statics analysis by using the initial model to obtain an analysis result;
adjusting the initial model according to the analysis result to obtain an intermediate model;
taking the intermediate model as an initial model, executing structural statics analysis by using the initial model to obtain an analysis result, adjusting the initial model according to the analysis result, and obtaining the intermediate model until the analysis result meets a preset condition;
determining the intermediate model as the analytical model.
The electronic device 300 can implement the processes implemented by the electronic device in the foregoing embodiments, and in order to avoid repetition, the detailed description is omitted here.
The embodiment of the invention further provides a computer-readable storage medium, wherein a computer program is stored on the computer-readable storage medium, and when being executed by a processor, the computer program realizes each process of the containment structure determination method for a nuclear power plant, and can achieve the same technical effect, and in order to avoid repetition, the details are not repeated here. The computer-readable storage medium may be a Read-Only Memory (ROM), a Random Access Memory (RAM), a magnetic disk or an optical disk.
It should 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 apparatus 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 apparatus. 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 apparatus that comprises the element.
Through the above description of the embodiments, those skilled in the art will clearly understand that the method of the above embodiments can be implemented by software plus a necessary general hardware platform, and certainly can also be implemented by hardware, but in many cases, the former is a better implementation manner. Based on such understanding, the technical solutions of the present invention may be embodied in the form of a software product, which is stored in a storage medium (such as ROM/RAM, magnetic disk, optical disk) and includes instructions for enabling a terminal (such as a mobile phone, a computer, a server, or a network device) to execute the method according to the embodiments of the present invention.
The above description is only for the specific embodiments of the present invention, but the scope of the present invention is not limited thereto, and any person skilled in the art can easily conceive of the changes or substitutions within the technical scope of the present invention, and all the changes or substitutions should be covered within the scope of the present invention. Therefore, the protection scope of the present invention shall be subject to the protection scope of the claims.
Claims (10)
1. A nuclear power plant containment structure determination method is characterized by comprising the following steps:
determining an analysis model according to the arrangement information and the load information of the nuclear power plant;
obtaining a displacement field of an analysis model under a target load according to the arrangement information of the nuclear power plant, the load information and the analysis model, wherein the load information comprises the target load;
and determining the structure of the containment according to the displacement field.
2. The method for determining the containment structure of the nuclear power plant according to claim 1, wherein the obtaining a displacement field of the analysis model under a target load according to the arrangement information of the nuclear power plant, the load information and the analysis model, the load information including the target load comprises:
performing statics analysis according to the arrangement information and the load information of the nuclear power plant to obtain a first displacement field of an analysis model under the load action without considering inertia and damping effect;
carrying out thermal stress analysis according to the arrangement information and the load information of the nuclear power plant to obtain a second displacement field of the load of the analysis model under the action of temperature;
performing dynamic analysis according to the arrangement information and the load information of the nuclear power plant to obtain a third displacement field of the analysis model under the action of the earthquake;
and summing the first displacement field, the second displacement field and the third displacement field according to preset weight to obtain the displacement field.
3. The method for determining the containment structure of the nuclear power plant according to claim 1, wherein the determining an analysis model according to the arrangement information and the load information of the nuclear power plant comprises:
establishing a geometric model according to the nuclear power plant arrangement information and the load information;
and carrying out grid division on the geometric model to obtain an analysis model.
4. The method for determining the containment structure of the nuclear power plant according to claim 3, wherein the gridding the geometric model to obtain the analytical model comprises:
carrying out mesh division on the geometric model to obtain an initial model;
carrying out structural statics analysis by using the initial model to obtain an analysis result;
adjusting the initial model according to the analysis result to obtain an intermediate model;
taking the intermediate model as an initial model, executing structural statics analysis by using the initial model to obtain an analysis result, adjusting the initial model according to the analysis result, and obtaining the intermediate model until the analysis result meets a preset condition;
and determining the finally obtained intermediate model as the analysis model.
5. A containment structure determination device for a nuclear power plant, comprising:
the first acquisition module is used for determining an analysis model according to the arrangement information and the load information of the nuclear power plant;
the second acquisition module is used for acquiring a displacement field of the analysis model under a target load according to the arrangement information of the nuclear power plant, the load information and the analysis model, wherein the load information comprises the target load;
and the determining module is used for determining the structure of the containment according to the displacement field.
6. The nuclear power plant containment structure determination apparatus of claim 5, wherein the second acquisition module comprises:
the first obtaining submodule is used for carrying out statics analysis according to the arrangement information and the load information of the nuclear power plant to obtain a first displacement field of the analysis model under the load action without considering inertia and damping effect;
the second acquisition submodule is used for carrying out thermal stress analysis according to the arrangement information and the load information of the nuclear power plant to obtain a second displacement field of the load of the analysis model under the action of temperature;
the third acquisition submodule is used for performing dynamic analysis according to the arrangement information and the load information of the nuclear power plant to acquire a third displacement field of the analysis model under the action of the earthquake;
and the first determining submodule is used for summing the first displacement field, the second displacement field and the third displacement field according to preset weight to obtain the displacement field.
7. The nuclear power plant containment structure determination apparatus of claim 5, wherein the first obtaining module includes:
the establishing submodule is used for establishing a geometric model according to the nuclear power plant arrangement information and the load information;
and the obtaining submodule is used for carrying out grid division on the geometric model to obtain an analysis model.
8. The nuclear power plant containment structure determination apparatus of claim 7, wherein the acquisition submodule is configured to:
carrying out mesh division on the geometric model to obtain an initial model;
carrying out structural statics analysis by using the initial model to obtain an analysis result;
adjusting the initial model according to the analysis result to obtain an intermediate model;
taking the intermediate model as an initial model, executing structural statics analysis by using the initial model to obtain an analysis result, and adjusting the initial model according to the analysis result to obtain the intermediate model until the analysis result meets a preset condition;
and determining the finally obtained intermediate model as the analysis model.
9. An electronic device comprising a processor, a memory and a computer program stored on the memory and executable on the processor, the computer program, when executed by the processor, implementing the steps in the nuclear power plant containment structure determination method according to any one of claims 1 to 4.
10. A readable storage medium, characterized in that the readable storage medium has stored thereon a program which, when being executed by a processor, carries out the steps of the nuclear power plant containment structure determination method according to any one of claims 1 to 4.
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