CN113901029B - Unified modeling method and system supporting multi-specialized computing software of reactor core - Google Patents

Unified modeling method and system supporting multi-specialized computing software of reactor core Download PDF

Info

Publication number
CN113901029B
CN113901029B CN202111203668.2A CN202111203668A CN113901029B CN 113901029 B CN113901029 B CN 113901029B CN 202111203668 A CN202111203668 A CN 202111203668A CN 113901029 B CN113901029 B CN 113901029B
Authority
CN
China
Prior art keywords
software
calculation
model
data
core
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Active
Application number
CN202111203668.2A
Other languages
Chinese (zh)
Other versions
CN113901029A (en
Inventor
袁光辉
刘�东
芦韡
卢忝余
刘盈
曹国海
郑丹晨
于洋
尹强
潘俊杰
强胜龙
卢川
张文鑫
王雅峰
庞勃
杨洪
孙卓
刘松亚
罗骞
闫于均
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Nuclear Power Institute of China
Original Assignee
Nuclear Power Institute of China
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Nuclear Power Institute of China filed Critical Nuclear Power Institute of China
Priority to CN202111203668.2A priority Critical patent/CN113901029B/en
Publication of CN113901029A publication Critical patent/CN113901029A/en
Application granted granted Critical
Publication of CN113901029B publication Critical patent/CN113901029B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • GPHYSICS
    • G06COMPUTING; CALCULATING OR COUNTING
    • G06FELECTRIC DIGITAL DATA PROCESSING
    • G06F16/00Information retrieval; Database structures therefor; File system structures therefor
    • G06F16/20Information retrieval; Database structures therefor; File system structures therefor of structured data, e.g. relational data
    • G06F16/21Design, administration or maintenance of databases
    • G06F16/211Schema design and management
    • G06F16/212Schema design and management with details for data modelling support
    • GPHYSICS
    • G06COMPUTING; CALCULATING OR COUNTING
    • G06FELECTRIC DIGITAL DATA PROCESSING
    • G06F11/00Error detection; Error correction; Monitoring
    • G06F11/30Monitoring
    • G06F11/32Monitoring with visual or acoustical indication of the functioning of the machine
    • G06F11/323Visualisation of programs or trace data
    • GPHYSICS
    • G06COMPUTING; CALCULATING OR COUNTING
    • G06FELECTRIC DIGITAL DATA PROCESSING
    • G06F30/00Computer-aided design [CAD]
    • G06F30/20Design optimisation, verification or simulation

Landscapes

  • Engineering & Computer Science (AREA)
  • Theoretical Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • General Physics & Mathematics (AREA)
  • Data Mining & Analysis (AREA)
  • Databases & Information Systems (AREA)
  • Computer Hardware Design (AREA)
  • Evolutionary Computation (AREA)
  • Geometry (AREA)
  • Quality & Reliability (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention discloses a unified modeling method and a system supporting multi-specialized computing software of a reactor core, comprising the following steps: performing standardized processing on the reactor core data; carrying out association synchronization on the standardized data and each software calculation model according to the reference relation between the reactor core data and each software calculation model, and obtaining association data information between the standardized data and the software calculation model based on the association synchronization; and acquiring data information required by core calculation software corresponding to any software calculation model from the standardized data, forming an input file of the software calculation model in the core calculation software, executing calculation by the core calculation software according to the input file, and synchronously displaying the real-time state of the core calculation software operation calculation. The invention realizes unified and centralized management and unified and centralized visual display of various software calculation models, improves the modeling accuracy and modeling efficiency of the reactor core calculation model, and further improves the development efficiency of the nuclear reactor.

Description

Unified modeling method and system supporting multi-specialized computing software of reactor core
Technical Field
The invention relates to the field of nuclear reactor engineering software development, in particular to a unified modeling method and system supporting multi-specialized computing software of a reactor core.
Background
The numerical calculation of the nuclear reactor involves multidisciplinary and large amount of calculation software, and the traditional numerical calculation flow is that a designer respectively constructs a calculation model aiming at different software based on a text or text template mode, then uses corresponding calculation software to carry out numerical calculation, finally generates a grid visualization model based on a specially developed data conversion tool and completes analysis of result data in a post-processing tool. The great amount of manpower required to complete the construction and modification of the computational model in this process is particularly difficult to examine the computational model prior to actual computation, and the lack of computational data analysis tools integrated with computational model modeling tools limits further improvements in reactor design efficiency.
With the increasing economic and safety requirements of reactors, core numerical calculations are becoming increasingly important throughout the reactor design segment. How to accurately and efficiently complete the construction of a numerical calculation model and the visual analysis of calculation data becomes a key commonality problem in the development process of numerical calculation software of a reactor.
Disclosure of Invention
The invention aims to provide a unified modeling method and a system for supporting multi-specialized reactor core computing software, which solve the problems of accurately and efficiently completing the construction of a reactor core numerical computing model and the visual analysis of computing data.
The invention is realized by the following technical scheme:
A unified modeling method supporting multi-specialized computing software of a reactor core comprises the following steps: s1: carrying out standardization processing on the reactor core data to obtain standardized data; s2: according to the reference relation between the reactor core data and each software calculation model, carrying out association synchronization on the standardized data and each software calculation model, and obtaining association data information between the standardized data and the software calculation model based on the association synchronization; s3: based on the associated data information, obtaining data information required by core calculation software corresponding to any software calculation model from the standardized data, forming an input file of the software calculation model in the core calculation software, and executing calculation by the core calculation software according to the input file and synchronously displaying the real-time state of the operation calculation of the core calculation software.
In the prior art, nuclear reactor numerical computation involves multiple disciplines and a large amount of computation software, and a traditional numerical computation flow is that a designer constructs software computation models for different software based on text or text template modes respectively, and then uses corresponding computation software to perform numerical computation, so that the computation process is complex and numerous. The invention relates to a unified modeling method supporting multi-specialized computing software of a nuclear reactor core, which is characterized in that all the original data of the reactor are standardized from the original data of the nuclear reactor so as to adapt to various different types of core computing software and different software computing models in each core computing software, and the data uniformity is realized on the data layer of the reactor. And on the one hand, any software calculation model can be extracted or constructed from the standardized data at any time based on the information of the associated synchronization, and the constructed software calculation model can be existing in the prior art or can be adjusted according to the needs of actual scenes. On the other hand, the input files required by any software calculation model in any core calculation software are obtained from the standardized data according to the associated synchronous information, namely, the input files of any software calculation model in the core calculation software are also obtained from the standardized data. The input file is sent into the core calculation software corresponding to the constructed software calculation model to perform operation calculation, and then real-time synchronous display and visualization are performed on the operation process and operation result of the output software calculation model in the corresponding core calculation software, so that different professions and different core calculation software calculation data are all single in source from standardized data, data required by construction of the different software calculation models are also from standardized data, and the associated synchronization among the software calculation models of different professional core calculation software, and the associated synchronization among different reactor core data and various software calculation models are realized. Meanwhile, the constructed software calculation model can be adjusted and modified at any time, so that the operation of technicians is facilitated, and the model calculation requirements under different actual scenes are met. In general, the invention unifies the parameters of the software calculation model structure and the input data of the software calculation model to form standardized data so as to uniformly manage and call the standardized data and realize uniform modeling for different specialized reactor core calculation software.
Furthermore, the standardized data also comprises parameterized information of the software calculation model, wherein the parameterized information is obtained after parameterizing any software calculation model. The standardized data includes parameterized information of the software computing models, that is, data which can refer to or characterize each software computing model is extracted after parameterizing the structure data and the type data of each software computing model. The parameterized data of the software calculation model are classified into standardized data through parameterization processing, so that the association synchronization and unified integrated management of different software calculation models are realized.
Further, any software calculation model is constructed based on the parameterized information or adjusted by the parameterized information. Based on the parameterized data information, a specific structure of the software computing model can be deduced, so that the software computing model is obtained by the parameterized information. Meanwhile, the existing software calculation model can be adjusted according to the needs of different actual scenes so as to better adapt to the needs of actual work, and the purpose of adjusting the constructed software calculation model can be achieved only by adjusting the parameterized information when the software calculation model is constructed by using the parameterized information in the standardized data.
Further, the step of synchronously displaying the real-time state of the running calculation of the software calculation model specifically includes: constructing a calculation software gridding model based on the input file, and constructing a visual standard model according to the calculation software gridding model; and displaying the process data and the result data of the software calculation model operation calculation in real time through the visual standard model. And constructing a calculation software gridding model according to the input file, and constructing a visual standard model through the calculation software gridding model. And displaying the process data and the result data of the running calculation of the software calculation model in real time through the visual standard model. The visual standard model is correspondingly constructed according to the conditions of different types of software calculation models, so that real-time display of different software calculation models is realized, and different aspects or fine degrees of display can be performed according to the requirements of different application scenes. Because the software calculation model is constructed through unified standardized data, unified and centralized management of different types of software calculation models is realized through unified reuse of the standardized data, and unified and centralized management of different visual standard models is also indirectly realized.
Further, the software computation model includes: a reactor physical model, a reactor thermal model, and a reactor fuel model.
Further, the software computation model includes: RMC model, KYLIN-II model, CORTH model, FUPAC model.
In a second implementation manner of the present invention, a unified modeling system supporting multi-specialized computing software for a core includes: the storage unit is used for storing standardized reactor core data and parameterized software calculation model data, namely standardized data; the software calculation model construction unit is used for establishing various software calculation models according to the association relation between the software calculation model and the standardized data; an input file generating unit for generating input files of various software calculation models according to the association relation between the software calculation models and the standardized data; the operation calculation unit is used for acquiring data information required by core calculation software corresponding to any software calculation model from the storage unit, forming an input file of the software calculation model in the core calculation software, and executing calculation by the core calculation software according to the input file; and the visual display unit is used for visually displaying the process data and the result data which are calculated by the operation calculation unit.
Furthermore, the storage format of the data in the storage unit adopts an HDF5 format, the reactor core data comprises a hierarchical structure unified description of a reactor model number, a loading number, a fuel assembly number and an assembly element number, and parameterized software calculation model data comprises references and association relations among all software calculation models.
In a third implementation manner, the invention provides a computer device, which includes a memory, a processor, and a computer program stored in the memory and capable of running on the processor, wherein the processor implements the unified modeling method supporting multi-specialized computing software of a reactor core when executing the computer program.
In a fourth implementation manner of the present invention, a computer readable storage medium stores a computer program, where the computer program when executed by a processor implements the unified modeling method supporting multi-specialized computing software for a core as described above.
Compared with the prior art, the invention has the following advantages and beneficial effects:
the method realizes unified and centralized management and unified and centralized visual display of various software calculation models corresponding to various reactor core calculation software, can greatly improve the usability of the reactor numerical calculation software, the modeling and data analysis efficiency of the calculation model, and improves the reusability of the calculation model data, and finally improves the development capability of the reactor model. The accuracy and modeling efficiency of the reactor core calculation model are improved, the development efficiency of the nuclear reactor is further improved, and good economic benefits and social benefits are achieved.
Drawings
In order to more clearly illustrate the technical solutions of the exemplary embodiments of the present invention, the drawings that are needed in the examples will be briefly described below, it being understood that the following drawings only illustrate some examples of the present invention and therefore should not be considered as limiting the scope, and that other related drawings may be obtained from these drawings without inventive effort for a person skilled in the art. In the drawings:
FIG. 1 is a logic block diagram of embodiment 3 of the present invention;
FIG. 2 is a layered structure diagram of embodiment 3 of the present invention;
FIG. 3 is a layered structure diagram of embodiment 3 of the present invention;
FIG. 4 is a data flow diagram of embodiment 3 of the present invention;
Fig. 5 is a business flow chart of embodiment 3 of the present invention.
Detailed Description
For the purpose of making apparent the objects, technical solutions and advantages of the present invention, the present invention will be further described in detail with reference to the following examples and the accompanying drawings, wherein the exemplary embodiments of the present invention and the descriptions thereof are for illustrating the present invention only and are not to be construed as limiting the present invention.
Example 1
The embodiment 1 is a unified modeling method supporting multi-specialized computing software of a reactor core, comprising the following steps:
S1: carrying out standardization processing on the reactor core data to obtain standardized data;
S2: carrying out association synchronization on the standardized data and each software calculation model according to the reference relation between the reactor core data and each software calculation model, and obtaining association data information between the standardized data and the software calculation model based on the association synchronization;
s3: based on the associated data information, data information required by core calculation software corresponding to any software calculation model is obtained from the standardized data, an input file of the software calculation model in the core calculation software is formed, the core calculation software performs calculation according to the input file, and real-time states of the core calculation software running calculation are synchronously displayed.
In the prior art, numerical calculation of nuclear reactors involves multidisciplinary and massive core calculation software, and a traditional numerical calculation flow is that a designer constructs software calculation models for different core calculation software based on text or text template modes respectively, and then uses corresponding core calculation software to perform numerical calculation, so that the calculation process is complex and various. That is, there are a number of different core calculation software, such as: RMC, KYLIN-II, CORTH, FUPAC, there are a number of software computing models such as: a reactor physical model, a reactor thermal model, and a reactor fuel model. The input data of different core calculation software and the input parameters of different software calculation models have the same data information and different data information.
The invention relates to a unified modeling method supporting multi-specialized computing software of a nuclear reactor core, which is characterized in that all the original data of the reactor are standardized from the original data of the nuclear reactor so as to adapt to various different types of core computing software and different software computing models in each core computing software, and the data uniformity is realized on the data layer of the reactor. And on the one hand, any software calculation model can be extracted or constructed from the standardized data at any time based on the information of the associated synchronization, and the constructed software calculation model can be existing in the prior art or can be adjusted according to the needs of actual scenes. On the other hand, the input files required by any software calculation model in any core calculation software are obtained from the standardized data according to the associated synchronous information, namely, the input files of any software calculation model in the core calculation software are also obtained from the standardized data. The input file is sent into the core calculation software corresponding to the constructed software calculation model to perform operation calculation, and then real-time synchronous display and visualization are performed on the operation process and operation result of the output software calculation model in the corresponding core calculation software, so that different professions and different core calculation software calculation data are all single in source from standardized data, data required by construction of the different software calculation models are also from standardized data, and the associated synchronization among the software calculation models of different professional core calculation software, and the associated synchronization among different reactor core data and various software calculation models are realized. Meanwhile, the constructed software calculation model can be adjusted and modified at any time, so that the operation of technicians is facilitated, and the model calculation requirements under different actual scenes are met. In general, the invention unifies the parameters of the software calculation model structure and the input data of the software calculation model to form standardized data so as to uniformly manage and call the standardized data and realize uniform modeling for different specialized reactor core calculation software.
The standardized data also comprises parameterized information of the software calculation model, wherein the parameterized information is obtained by parameterizing any software calculation model. The standardized data includes parameterized information of the software computing models, that is, data which can refer to or characterize each software computing model is extracted after parameterizing the structure data and the type data of each software computing model. The parameterized data of the software calculation model are classified into standardized data through parameterization processing, so that the association synchronization and unified integrated management of different software calculation models are realized.
Based on the parameterized information or adjusting the parameterized information, any software calculation model is constructed. According to the parameterized data information, the specific structure of the software calculation model can be reversely deduced, and the software calculation model is reversely obtained through the parameterized information. Meanwhile, the structure of the existing software calculation model can be adjusted according to the needs of different actual scenes, so that the method can better adapt to the needs of actual work, and the purpose of adjusting the constructed software calculation model can be achieved only by adjusting parameterized information when the software calculation model is reversely constructed by parameterized information in standardized data.
The method for synchronously displaying the real-time state of the running calculation of the software calculation model specifically comprises the following steps: constructing a calculation software gridding model based on the input file, and constructing a visual standard model according to the calculation software gridding model; and displaying the process data and the result data of the running calculation of the software calculation model in real time through the visual standard model. And constructing a calculation software gridding model according to the input file, and constructing a visual standard model through the calculation software gridding model. And displaying the process data and the result data of the running calculation of the software calculation model in real time through the visual standard model. The visual standard model is correspondingly constructed according to the conditions of different types of software calculation models, so that real-time display of different software calculation models is realized, and different aspects or fine degrees of display can be performed according to the requirements of different application scenes. Because the software calculation model is built through unified standardized data, unified and centralized management of different types of software calculation models is realized through unified reuse of the standardized data, and unified and centralized management of different visual standard models is also indirectly realized.
The software calculation model in this embodiment 1 includes at least: a reactor physical model, a reactor thermal model, and a reactor fuel model. Each model is in turn simulated by a plurality of core calculation software tools, including: RMC, KYLIN-II, CORTH, FUPAC, etc.
The RMC is a core Monte Care calculation analysis program developed by combining the characteristics of flexible geometric structure, complex neutron spectrum, various material components, high anisotropism, high leakage (certain specific conditions) and the like of advanced and new concept reactor design, and is a physical calculation core of a numerical analysis platform of a multi-physical multi-size coupled nuclear energy system.
KYLIN-II is a neutron grid program with independent intellectual property which is independently developed by Chinese nuclear power research institute, the program adopts a characteristic line method to carry out complex geometric neutron transport calculation, adopts a subgroup method to carry out resonance treatment, and adopts a generalized coarse grid finite difference acceleration method to accelerate a seed transport solving process.
CORTH is core thermodynamic subchannel calculation analysis software independently developed by China nuclear power research institute, adopts a four-way uniform flow model with a sliding speed ratio, can describe single-phase flow and two-phase flow of a series of connected or disconnected subchannels under a steady-state working condition, and is mainly used for thermodynamic hydraulic analysis of a reactor core or a experiment with a heating rod bundle.
FUPAC is fuel performance analysis software independently developed by Chinese nuclear power research institute, which can simulate the thermal/mechanical behavior of the fuel rod during the irradiation period inside the reactor core, and calculate the change of thermal/mechanical parameters along with the irradiation history. The method can be used for verifying whether the performance of the fuel rod under I, II operating conditions meets the design rule requirements or not and providing a fuel initial state for accident analysis.
Example 2
Embodiment 2 is a unified modeling system supporting multi-specialty computing software for a core, based on embodiment 1, comprising:
the storage unit is used for storing standardized reactor core data and parameterized software calculation model data, namely standardized data;
The software calculation model construction unit is used for building various software calculation models according to the association relation between the software calculation models and the standardized data;
The input file generating unit is used for generating input files of various software calculation models according to the association relation between the software calculation models and the standardized data;
The operation calculation unit is used for acquiring data information required by core calculation software corresponding to any software calculation model from the storage unit, forming an input file of the software calculation model in the core calculation software, and executing calculation by the core calculation software according to the input file;
And the visual display unit is used for visually displaying the process data and the result data which are calculated by the operation calculation unit.
The storage unit in this embodiment 2 may be a disk file, and the specific working process of the unified modeling system in this embodiment 2 is the same as that of the method in embodiment 1, and will not be described herein again.
Example 3
The embodiment 3 is a unified modeling method and system supporting multi-specialized core calculation software, and is further presented on the basis of the embodiment 1, so as to solve the problems of low modeling efficiency and difficult error checking of numerical core calculation models of various specialized nuclear reactors.
The method of this embodiment 3 includes:
The reactor core calculation data are uniformly stored in a standard mode, and single sources of the calculation data and the associated synchronization of the data of different software calculation models are realized by establishing a reference relation between the software calculation models; the unified model storage method uses HDF5 as a data storage format, the nuclear reactor core calculation data is uniformly described in a hierarchical structure of a reactor model number, a loading number, a fuel assembly number and an assembly element number, and references among models are established through IDs. The logical structure of this embodiment 3 is shown in fig. 1.
Using a data middleware to perform data exchange among system function modules and unified access of core software calculation model data; and the data middleware loads a nuclear reactor core unified calculation model from the HDF5 disk file, stores the unified calculation model into the HDF5 disk file and provides partial data reading and editing operation interfaces of the unified calculation model. The hierarchical structure of the system function modules is shown in fig. 2, and the hierarchical structure is shown in fig. 3.
Using an extensible plug-in mechanism to automatically extract data required by different professional computing software and generate corresponding input files; and the extensible plug-in mechanism uses a mode based on an XML configuration file to configure the data processing plug-ins meeting the professional requirements of different nuclear reactor computing according to the needs.
Unified and integrated management of different types of model data is realized by using an integrated calculation model structure tree and a dynamic attribute panel; and the nuclear reactor calculation model structure tree is used for carrying out hierarchical unified management on data such as geometry, materials, software control parameters and the like of a calculation model, and corresponding attribute data operation interfaces are automatically loaded according to different types of data nodes.
A parameterized three-dimensional interactive modeling method of the reactor core is used, and the real-time state of a reactor core software calculation model is synchronously displayed. The parameterized interactive modeling method provides parameterized definition based on nuclear reactor engineering semantics, and combines the symmetrical structure characteristics of a nuclear reactor core and a fuel assembly to perform three-dimensional discrete display on the nuclear reactor core structure by using a structured grid. In the method provided in this embodiment 3, in the field of numerical computation and analysis of the nuclear reactor core, unified modeling and data analysis software supporting multi-specialized computation software of the core is developed, and a parameterized three-dimensional interactive modeling method is adopted, so that the modeling and data management modes of the original core computation model are improved, and the modeling precision and the modeling efficiency of the core computation model are improved.
For the method development of this embodiment 3, the data flow is shown in fig. 4, the service flow is shown in fig. 5, and the method includes:
1. A unified computing model (Unified Calculation Model, UCM) is constructed that is not directly related to the specific computing software. UCM includes a description of the geometry of the computational model, material properties of the geometry, and nuclide properties of the corresponding material. The geometric structure description of the UCM consists of a parameter model and a visual model, wherein the parameter model adopts parameters closely related to engineering semantics to describe the geometric structure (such as the core block radius, the air gap thickness, the cladding outer diameter and the assembly height of a rod type fuel element), the visual model adopts discrete grids to describe the display data of the geometric model, and the description contents of the discrete grids comprise node coordinates, unit composition rules, node data, unit data and the like.
2. Defining the control parameters of the computing software. Software control parameters (e.g., convergence criteria, computational grid partitioning, etc.) are calculated for UCM associations via attribute attachment patterns.
3. A computing software input file is generated. And automatically generating a calculation grid according to UCM related to control parameters of calculation software, and finally generating a calculation input file with complete data items and corresponding description formats.
4. And (3) three-dimensional visual analysis of the calculated data. And (3) according to the calculation grid generated in the step (S3), generating a corresponding post-processing grid visualization model by combining result data obtained by calculation software, and realizing three-dimensional visualization analysis of the calculation model by using a grid model visualization processing tool (such as VTK).
The system of this embodiment 3 includes:
the unified model access unit is used for storing the reactor core unified calculation model into a disk file, loading the unified calculation model from the disk file and providing a reading interface of the specified data of the unified calculation model;
The calculation model data structure management unit is used for carrying out hierarchical management on the unified reactor core calculation model in a tree structure mode and providing a property editing function of node data;
the computational model parameterized modeling unit is used for performing parameterized modeling of the software computational model in a mode of matching with the core symmetrical structure;
and the three-dimensional interactive display unit is used for carrying out three-dimensional interactive display on the reactor core computing model.
The system of this embodiment 3 adopts a parameterized mode to model the core calculation model uniformly, and on the basis of the uniform model, combines different calculation specialized control parameters to automatically generate a corresponding software calculation model. The correlation relevance is maintained by the reference of different specialized software calculation models, so that the calculation data of different software are ensured to be synchronous and single in source. And uniformly modeling the reactor core pretreatment model and the reactor core pretreatment model, performing three-dimensional interactive visual analysis on the integrated environment, and displaying the uniform calculation model in different fine degrees according to different application scenes. By means of visual analysis means for providing result data for designers in an integrated mode, the analysis efficiency of calculation data can be improved, the modeling accuracy and modeling efficiency of a reactor core calculation model can be improved, the development efficiency of a nuclear reactor can be further improved, efficient three-dimensional display of large-scale grid data of the reactor core can be realized, visual analysis of calculation result data can be ensured, and good economic benefits and social benefits can be achieved.
Example 4
This example 4 is based on example 1. Embodiment 4 provides an apparatus comprising: one or more processors;
And a memory for storing one or more programs that, when executed by the one or more processors, cause the one or more processors to perform a unified modeling method that supports multi-specialty computing software for the core.
Wherein a unified modeling method supporting core multi-specialty computing software is performed according to the method steps in embodiment 1. And will not be described in detail herein.
Example 5
Embodiment 5 based on embodiment 1, embodiment 5 provides a unified modeling method supporting multi-specialty calculation software of a core, which is implemented when the program is executed by a processor.
Wherein a unified modeling method supporting core multi-specialty computing software is performed according to the method steps in embodiment 1. And will not be described in detail herein.
The foregoing description of the embodiments has been provided for the purpose of illustrating the general principles of the invention, and is not meant to limit the scope of the invention, but to limit the invention to the particular embodiments, and any modifications, equivalents, improvements, etc. that fall within the spirit and principles of the invention are intended to be included within the scope of the invention.

Claims (8)

1. The unified modeling method supporting the multi-specialized computing software of the reactor core is characterized by comprising the following steps of:
S1: carrying out standardization processing on the reactor core data to obtain standardized data;
s2: according to the reference relation between the reactor core data and each software calculation model, carrying out association synchronization on the standardized data and each software calculation model, and obtaining association data information between the standardized data and the software calculation model based on the association synchronization;
S3: based on the associated data information, acquiring data information required by core calculation software corresponding to any software calculation model from the standardized data, forming an input file of the software calculation model in the core calculation software, and executing calculation by the core calculation software according to the input file and synchronously displaying the real-time state of the operation calculation of the core calculation software;
the software calculation model is a reactor physical model, a reactor thermal model and a reactor fuel model which are obtained by simulation by a reactor core calculation software tool RMC, KYLIN-II, CORTH or FUPAC.
2. The unified modeling method supporting multi-specialized computing software for a reactor core of claim 1, wherein the standardized data further comprises parameterized information of a software computing model, and the parameterized information is information obtained by parameterizing any software computing model.
3. The unified modeling method supporting multi-specialty computing software for a core of claim 2, wherein any software computing model is constructed based on or adjusted to the parameterized information.
4. The unified modeling method supporting multi-specialty core computing software according to claim 1, wherein said synchronously displaying real-time status of the core computing software operation computation specifically comprises:
constructing a calculation software gridding model based on the input file, and constructing a visual standard model according to the calculation software gridding model; and displaying the process data and the result data of the software calculation model operation calculation in real time through the visual standard model.
5. A unified modeling system supporting multi-specialty computing software for a core, comprising:
the storage unit is used for storing standardized reactor core data and parameterized software calculation model data, namely standardized data;
The software calculation model construction unit is used for establishing various software calculation models according to the association relation between the software calculation model and the standardized data;
an input file generating unit for generating input files of various software calculation models according to the association relation between the software calculation models and the standardized data;
The operation calculation unit is used for acquiring data information required by core calculation software corresponding to any software calculation model from the storage unit, forming an input file of the software calculation model in the core calculation software, and executing calculation by the core calculation software according to the input file;
the visual display unit is used for visually displaying the process data and the result data which are calculated by the operation calculation unit;
the software calculation model is a reactor physical model, a reactor thermal model and a reactor fuel model which are obtained by simulation by a reactor core calculation software tool RMC, KYLIN-II, CORTH or FUPAC.
6. The unified modeling system supporting multi-specialty computing software for a reactor core of claim 5, wherein the storage format of the data in the storage unit is in HDF5 format, the core data comprises a hierarchical unified description of reactor model number, charge number, fuel assembly number, assembly element number, and parameterized software computing model data comprises references and associations between software computing models.
7. A computer device comprising a memory, a processor and a computer program stored in the memory and executable on the processor, wherein the processor implements the unified modeling method of supporting multi-specialty core computing software of any of claims 1 to 4 when the computer program is executed.
8. A computer readable storage medium storing a computer program, wherein the computer program when executed by a processor implements the unified modeling method supporting multi-specialty computing software of any of claims 1 to 4.
CN202111203668.2A 2021-10-15 2021-10-15 Unified modeling method and system supporting multi-specialized computing software of reactor core Active CN113901029B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202111203668.2A CN113901029B (en) 2021-10-15 2021-10-15 Unified modeling method and system supporting multi-specialized computing software of reactor core

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202111203668.2A CN113901029B (en) 2021-10-15 2021-10-15 Unified modeling method and system supporting multi-specialized computing software of reactor core

Publications (2)

Publication Number Publication Date
CN113901029A CN113901029A (en) 2022-01-07
CN113901029B true CN113901029B (en) 2024-06-18

Family

ID=79192332

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202111203668.2A Active CN113901029B (en) 2021-10-15 2021-10-15 Unified modeling method and system supporting multi-specialized computing software of reactor core

Country Status (1)

Country Link
CN (1) CN113901029B (en)

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104298836A (en) * 2014-11-06 2015-01-21 中国科学院合肥物质科学研究院 Reactor core iterative design system based on Monte Carlo calculation
CN107402976A (en) * 2017-07-03 2017-11-28 国网山东省电力公司经济技术研究院 Power grid multi-source data fusion method and system based on multi-element heterogeneous model

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108647931A (en) * 2018-04-08 2018-10-12 中国电建集团河北省电力勘测设计研究院有限公司 A kind of digital coordination design method of UHV transmission line
CN109359433B (en) * 2018-12-04 2022-08-30 中国核动力研究设计院 Automation method for reactor core refueling design
CN111061922A (en) * 2019-12-13 2020-04-24 智器云南京信息科技有限公司 Data visualization processing method, system, terminal equipment and storage medium
CN112685911A (en) * 2021-01-12 2021-04-20 湖南大学 Material calculation framework, method and system and computer equipment
CN113076684B (en) * 2021-02-23 2022-09-20 中国核动力研究设计院 Intelligent calculation method for transient parameters in rod adjusting process of nuclear reactor core
CN113177335B (en) * 2021-04-07 2022-06-24 北京科技大学 Automatic generation method and system for large-scale grid of full reactor core structure of fast neutron reactor

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104298836A (en) * 2014-11-06 2015-01-21 中国科学院合肥物质科学研究院 Reactor core iterative design system based on Monte Carlo calculation
CN107402976A (en) * 2017-07-03 2017-11-28 国网山东省电力公司经济技术研究院 Power grid multi-source data fusion method and system based on multi-element heterogeneous model

Also Published As

Publication number Publication date
CN113901029A (en) 2022-01-07

Similar Documents

Publication Publication Date Title
CN106873987B (en) Modelica-based multi-person collaborative modeling system
CN107844424A (en) Model-based testing system and method
Liu Fast industrial product design method and its application based on 3D CAD system
CN106650149B (en) Modelica model-based runtime fault injection system and method
CN112906272B (en) Reactor steady-state physical thermal full-coupling fine numerical simulation method and system
Li et al. CAD modeling study on FLUKA and OpenMC for accelerator driven system simulation
Jayaram et al. Reorganizing CAD assembly models (as-designed) for manufacturing simulations and planning (as-built)
CN113901029B (en) Unified modeling method and system supporting multi-specialized computing software of reactor core
Du et al. Development of cosVMPT and application of creating 3D neutronics model for 360-degree CFETR
Fiorina et al. Creation of an OpenFOAM fuel performance class based on FRED and integration into the GeN-foam multi-physics code
Yu The parametric design and intelligent assembly system based on the secondary development of solidworks
CN115587480A (en) Digital simulation method and digital simulation device
Ma et al. Research on 3D Digital Modeling of Power Grid and the Practical Key Technologies based on GIM
Li et al. Using procedure recovery approach to exchange feature-based data among heterogeneous CAD systems
Wang et al. Development of a hybrid parallelism Monte Carlo transport middleware on mesh geometry
Henares et al. Definition of a transparent constraint-based modeling and simulation layer for the management of complex systems
Kai Design and implementation of the whole process collaborative system for software development
CN102156705A (en) CAD (Computer Aided Design) document loading method and device
Zhang et al. Architecture design of intelligent assembly system based on complex system
Krol et al. Solving PDEs in modern multiphysics simulation software
Xia et al. Life balance-considered matching optimization method for remanufactured parts
Cerroni et al. CFD and Neutron codes coupling on a computational platform
Lu et al. Visualization of reactor core based on triangular mesh method
Li et al. Assembly pin factor parameterization method based on the proper orthogonal decomposition
Jing et al. Demand Analysis of Wind Turbine System Based on MBSE

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant