Nuclear power station industrial steam supply model parameter verification method and computer device

Abstract

The invention provides a nuclear power station industrial steam supply model parameter verification method and a computer device, and the method comprises the steps: completely copying a unit main instrument control picture and logic related to a nuclear power station industrial steam supply power plant side heat exchange system to a simulation platform, communicating with the existing logic of the simulation platform, and generating an instrument control simulation model; supplementing and updating communication interfaces of the newly-added process system simulation model and the newly-added instrument control system simulation model; establishing a full-range operation condition, carrying out parameter static comparison by referring to the corresponding condition of the unit, and analyzing the difference; if the parameters are adjusted according to the design parameter adjustment scheme, the adjusted parameters are updated to the simulation platform process / instrument control simulation system. According to the method, the existing full-range simulation platform of the nuclear power plant is used for building the nuclear power plant industrial steam supply power plant side heat exchange system related model and carrying out parameter verification, so that the problem that the risk of field debugging in an operation unit is relatively large as the related model cannot cover a complete process system and an instrument control system of the power plant is solved.

Description

Technical Field

[0001] The present application belongs to the field of nuclear power simulation engineering technology, and specifically relates to a method and computer device for verifying parameters of an industrial steam supply model of a nuclear power plant. Background Art

[0002] As an important manifestation of the comprehensive utilization of nuclear energy in nuclear power plants, industrial steam supply in nuclear power plants has entered the stage of practical application. Industrial steam supply in nuclear power plants uses the main steam of nuclear power units as a heat source to heat desalted water to form industrial steam, which is then transported to steam-using enterprises through two newly built steam mains, providing a stable and reliable steam supply for industrial production.

[0003] To realize the above process, the original nuclear power unit operating parameters and process systems need to be adjusted. Based on the requirements of nuclear safety and unit operation stability, the design is verified by establishing relevant design models. Since the relevant models cannot cover the complete process system and instrumentation and control system of the power plant, the accuracy of the model design is difficult to guarantee, and the risk of on-site debugging of the operating unit is relatively high.

[0004] Therefore, it is necessary to study a verification method to improve the accuracy of model design verification, reduce the risk of on-site commissioning of the unit, and ensure the safe and stable operation of the nuclear power plant and its industrial steam supply system. Summary of the invention

[0005] In view of this, the embodiments of the present application are committed to providing a method and computer device for verifying the parameters of the industrial steam supply model of a nuclear power plant. By using the existing full-range simulation platform of the nuclear power plant, the relevant models of the heat exchange system on the power plant side of the industrial steam supply of the nuclear power plant are built and the parameters are verified, so as to solve the existing problems that the accuracy of the model design is difficult to guarantee due to the inability of the relevant models to cover the complete process system and instrumentation and control system of the power plant, and the risk of on-site debugging of the operating units is relatively high.

[0006] The first aspect of the present application provides a method for verifying the parameters of an industrial steam supply model of a nuclear power plant, which includes: completely copying the main instrumentation and control screen and logic of the unit involved in the heat exchange system on the power plant side of the industrial steam supply of the nuclear power plant to the simulation platform, connecting with the existing logic of the simulation platform, and generating an instrumentation and control simulation model; based on the communication interface between the process simulation model and the instrumentation and control simulation model of the existing full-range simulation platform of the nuclear power plant, supplementing and updating the communication interface between the newly added process system simulation model and the newly added instrumentation and control system simulation model; establishing a full-range operating condition based on the updated full-range simulation platform, and performing static parameter comparison with reference to the corresponding conditions of the unit, analyzing the differences, and proposing a design parameter adjustment plan, the full-range operating conditions include full power, various power platform conditions, design benchmark accident conditions, and steam-electric coordination conditions; if the parameters are adjusted according to the design parameter adjustment plan, the adjusted parameters are updated to the simulation platform process / instrumentation and control simulation system.

[0007] In a specific embodiment of the present application, a full-range operating condition is established based on an updated full-range simulation platform, and a static comparison of parameters is performed with reference to the corresponding conditions of the unit, and the differences are analyzed to propose a design parameter adjustment plan, including: establishing a comparison list of key parameters, curves, and data of the reference unit; establishing a full-range operating condition based on an updated full-range simulation platform; performing real-time operation for each condition, implementing dynamic testing, and using real-time data recording tools to fully record key parameters; after the dynamic test, obtaining corresponding operating curves or node data based on key parameters; comparing parameter designs and actual data, analyzing differences, and proposing design parameter adjustment plans.

[0008] In a specific embodiment of the present application, a full-range operating condition is established based on an updated full-range simulation platform, including: using the historical operating data of the reference unit as a reference to establish a full-power condition, freezing the condition after a preset period of stable operation, and keeping the key parameters and curves of the condition consistent with the historical operating data of the corresponding condition of the reference unit in the frozen state; based on the full-power condition, using the historical operating data of the reference unit as a reference to establish each power platform condition, freezing each power platform condition after a preset period of stable operation, and keeping the key parameters and curves of the condition consistent with the historical operating data of the corresponding condition of the reference unit in the frozen state; based on the full-power condition, using the historical operating data of the reference unit as a reference to establish each power platform condition, freezing each power platform condition after a preset period of stable operation, and keeping the key parameters and curves of the condition consistent with the historical operating data of the corresponding condition of the reference unit in the frozen state; For power conditions, the design benchmark accident conditions are established in combination with the operating procedures and specifications of the reference unit. During the operation of the design benchmark accident conditions, real-time operations are carried out according to the operating procedures and specifications, and the conditions are frozen after the end of the procedures. In the frozen state, the key parameters and curves of the design benchmark accident conditions are consistent with the historical operating data of the corresponding conditions of the reference unit; based on the full power conditions, the steam-electric coordination conditions are established in combination with the operating procedures and specifications of the reference unit. During the operation of the steam-electric coordination conditions, real-time operations are carried out according to the operating procedures and specifications, and the conditions are frozen after the end of the procedures. In the frozen state, the key parameters and curves of the steam-electric coordination conditions are consistent with the historical operating data of the corresponding conditions of the reference unit.

[0009] In a specific embodiment of the present application, if the parameters are adjusted according to the design parameter adjustment plan, the adjusted parameters are updated to the process / instrumentation control simulation system of the simulation platform, including: if the parameters are adjusted according to the design parameter adjustment plan, the parameter correction of the corresponding process / instrumentation control simulation system is implemented on the simulation platform through a graphical configuration tool, and the correction content is memoed; matching adjustments are implemented on both sides of the interface work for interface changes caused by the correction; compilation and downloading are implemented on related systems; adaptive adjustments are made to established working conditions; the above work is repeated for iterative verification; during the iterative verification process, if the parameters adjusted according to the design do not have a convergence trend, the correctness of the model design is considered and the verification is suspended.

[0010] The second aspect of the present application provides a computer device, which includes a processor and a memory. The processor is used to execute a nuclear power plant industrial steam supply model parameter verification method provided in the first aspect of the present application. The memory is used to store executable instructions of the processor.

[0011] The third aspect of the present application provides a computer-readable storage medium on which computer executable instructions are stored. When the executable instructions are executed by a processor, a method for verifying parameters of a nuclear power plant industrial steam supply model provided in the first aspect of the present application is implemented.

[0012] The fourth aspect of the present application provides a computer program product, including a computer program / instruction, which, when executed by a processor, implements a method for verifying parameters of an industrial steam supply model for a nuclear power plant provided in the first aspect of the present application.

[0013] The beneficial effect of the technical solution of this application is that: by conducting simulation breadth and depth analysis on the heat exchange system of the industrial steam supply power plant side of the nuclear power plant, through the support of advanced simulation modeling platform, using the existing full-range simulation platform of the nuclear power plant to build the relevant model of the heat exchange system of the industrial steam supply power plant side of the nuclear power plant, covering the complete process system and instrumentation and control system of the power plant, through the full-range simulation platform, the consistency of the model with the actual system is ensured, and the risks of poor model fidelity and inaccurate calculation caused by only building a simple mathematical model due to the technical platform and the model design and calculation only involving some important systems and failing to cover all related systems are avoided, which greatly improves the comprehensiveness and reliability of the verification. In addition, based on the existing full-range simulation platform of the nuclear power plant, a parameter verification method for the industrial steam supply model of the nuclear power plant is provided, which ensures the high fidelity of the benchmark environment, realizes the accurate setting, adjustment and verification of the model parameters through high-fidelity real-time and full-range operating conditions, realizes the accurate setting, adjustment and verification of key parameters, and conducts comprehensive verification through the simulation platform, which greatly reduces the need for on-site debugging on the actual unit, reduces the risk of on-site debugging, ensures the safe and stable operation of the nuclear power plant and its industrial steam supply system, and improves the accuracy of model design verification. BRIEF DESCRIPTION OF THE DRAWINGS

[0014] Figure 1 The figure is a flow chart of a method for verifying parameters of an industrial steam supply model for a nuclear power plant provided in one embodiment of the present application.

[0015] Figure 2 Shown is a system architecture diagram for implementing a method for verifying parameters of an industrial steam supply model for a nuclear power plant provided in one embodiment of the present application. DETAILED DESCRIPTION

[0016] The following will be combined with the drawings in the embodiments of the present application to clearly and completely describe the technical solutions in the embodiments of the present application. Obviously, the described embodiments are only part of the embodiments of the present application, not all of the embodiments. Based on the embodiments in the present application, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of this application.

[0017] At least one embodiment of the present application provides a method for verifying parameters of an industrial steam supply model of a nuclear power plant, based on nuclear power simulation technology, referring to Figure 1 and Figure 2 ,The parameter verification method of the nuclear power plant industrial steam supply model includes the following steps.

[0018] S1: Completely copy the main instrumentation and control screens and logic of the units involved in the heat exchange system of the industrial steam supply plant side of the nuclear power plant to the simulation platform, connect them with the existing logic of the simulation platform, and generate an instrumentation and control simulation model.

[0019] S2: Based on the communication interface between the process simulation model and the instrumentation and control simulation model of the existing full-range simulation platform of the nuclear power plant, the communication interface of the newly added process system simulation model and the newly added instrumentation and control system simulation model is supplemented and updated.

[0020] It should be noted that the reference Figure 2 ,The process system simulation model can be referred to as process model, and the ,instrumentation and control simulation model can be referred to as instrumentation and control ,model.

[0021] The above S1 and S2 use the existing full-range simulation platform of the nuclear power plant to realize the construction of industrial steam supply model, including process system, instrumentation and control system, third-party interface system, etc. With the support of advanced simulation modeling platform, the simulation model of industrial steam supply related process system is established in full range and with high fidelity, the logic and screen of the instrumentation and control system corresponding to the participating units are completely copied, the instrumentation and control model is generated, and the communication interface of the process and instrumentation and control model is established.

[0022] S3: Establish full-range operating conditions based on the updated full-range simulation platform, and perform static parameter comparison with the corresponding conditions of the unit, analyze the differences, and propose design parameter adjustment plans. Full-range operating conditions include full power, various power platform conditions, design benchmark accident conditions, and steam-electric coordination conditions.

[0023] The full range of operating conditions includes condition 1, condition 2…condition n, including but not limited to full power, other power platform conditions, design basis accident conditions and steam-electric coordination conditions.

[0024] For example, based on the updated full-range simulation platform, various power platforms, design basis accidents, and steam-electric coordination conditions are established, and key parameters are statically compared with the corresponding conditions of the reference unit. High fidelity, real-time, full-range, and accurate simulation of various conditions, including full power, various power platforms, design basis accidents, and steam-electric coordination conditions, enables accurate setting, adjustment, and verification of key parameters.

[0025] S4: If the parameters are adjusted according to the design parameter adjustment plan, the adjusted parameters are updated to the simulation platform process / instrumentation control simulation system.

[0026] According to the technical solution provided in the embodiment of the present application, by conducting a simulation breadth and depth analysis of the heat exchange system on the industrial steam supply plant side of the nuclear power plant, with the support of an advanced simulation modeling platform, the existing full-range simulation platform of the nuclear power plant is used to build relevant models of the heat exchange system on the industrial steam supply plant side of the nuclear power plant, covering the complete process system and instrumentation and control system of the power plant. Through the full-range simulation platform, the consistency of the model with the actual system is ensured, and the risks of poor model fidelity and inaccurate calculations caused by only building a simple mathematical model due to technical platform reasons and the model design and calculation only involving some important systems and failing to cover all related systems are avoided, thereby greatly improving the comprehensiveness and reliability of the verification.

[0027] In addition, based on the existing full-range simulation platform of the nuclear power plant, a parameter verification method for the industrial steam supply model of the nuclear power plant is provided, which ensures the high fidelity of the benchmark environment, and realizes the accurate setting, adjustment and verification of model parameters through high-fidelity real-time and full-range operating conditions, and realizes the accurate setting, adjustment and verification of key parameters. Through comprehensive verification on the simulation platform, the need for on-site commissioning on actual units is greatly reduced, the risk of on-site commissioning is reduced, the safe and stable operation of the nuclear power plant and its industrial steam supply system is ensured, and the accuracy of model design verification is improved. Therefore, by reducing the number and risk of on-site commissioning, the uncertainty and cost in the commissioning process are reduced, and the economic benefits of the industrial steam supply system of the nuclear power plant are improved.

[0028] In addition, since the interference of on-site debugging on the actual system is reduced, this method effectively improves the operational safety of the nuclear power plant and its industrial steam supply system, ensuring the long-term safe and stable operation of the nuclear power plant.

[0029] Furthermore, through real-time data recording and dynamic testing, the difference between the design parameters and the actual parameters can be discovered and adjusted in time, reducing errors and deviations, and improving the accuracy and reliability of verification. This method performs parameter verification on the simulation platform, which can not only verify the accuracy of the parameters, but also provide reliable data support and optimization solutions for subsequent designs, thus optimizing the entire design process.

[0030] The simulation platform is not only used for parameter verification, but also as an important tool for nuclear power plant personnel training. Through training in a simulation environment, operators can become familiar with system behaviors under various working conditions, improve their ability to deal with actual operations and emergencies, and further ensure the safe operation of nuclear power plants.

[0031] It should be noted that the embodiment of the present application verifies the accuracy of the parameters but does not verify the correctness of the model design.

[0032] In at least one embodiment of the present application, S31 to S35 are a specific implementation of the above S3.

[0033] S31: Establish a comparison list of key parameters, curves, and data for the reference unit.

[0034] S32: Establish full-range operating conditions based on the updated full-range simulation platform.

[0035] S33: Perform dynamic tests for each operating condition in real time and use real-time data logging tools to fully record key parameters.

[0036] It should be noted that usually record files can be converted into tables and curves through office software such as Excel for easy viewing.

[0037] S34: After the dynamic test is completed, the corresponding operation curve or node data is obtained based on the key parameters.

[0038] S35: Compare the parameter design and actual data, analyze the differences, and propose design parameter adjustment plans.

[0039] In the embodiment of the present application, real-time operation is performed based on the above-mentioned model and working conditions, dynamic testing is implemented, and key parameters are fully recorded using real-time data recording tools. The difference between the design parameters and the actual operating parameters is analyzed and adjusted. Through iterative recording, analysis, and adjustment, the final consistency of the design parameters and the actual operating parameters is achieved.

[0040] In at least one embodiment of the present application, S321 to S324 are a specific implementation of the above S32.

[0041] S321: Using the historical operating data of the reference unit as a reference, a full-power operating condition is established, and the operating condition is frozen after running stably for a preset period of time. In the frozen state, the key parameters and curves of the operating condition are consistent with the historical operating data of the corresponding operating condition of the reference unit.

[0042] S322: Based on the full-power condition, each power platform condition is established using the historical operating data of the reference unit as a reference. Each power platform condition is frozen after running stably for a preset period of time. When frozen, the key parameters and curves of each power platform condition are consistent with the historical operating data of the corresponding condition of the reference unit.

[0043] In some embodiments, the preset duration is approximately 1 hour.

[0044] S323: Based on the full-power condition, the design benchmark accident condition is established in combination with the operating procedures and specifications of the reference unit. During the operation of the design benchmark accident condition, real-time operation is carried out according to the operating procedures and specifications, and the condition is frozen after the end of the procedures. In the frozen state, the key parameters and curves of the design benchmark accident condition are consistent with the historical operating data of the corresponding condition of the reference unit.

[0045] S324: Based on the full-power condition, the steam-electric coordination condition is established in combination with the operating procedures and specifications of the reference unit. During the operation of the steam-electric coordination condition, real-time operation is carried out according to the operating procedures and specifications, and the condition is frozen after the procedure ends. In the frozen state, the key parameters and curves of the steam-electric coordination condition are consistent with the historical operating data of the corresponding condition of the reference unit.

[0046] In at least one embodiment of the present application, S41 to S46 are a specific implementation of the above S4.

[0047] S41: If the parameters are adjusted according to the design parameter adjustment plan, the parameters of the corresponding process / instrumentation and control simulation system are corrected through the graphical configuration tool on the simulation platform, and the correction content is marked with a memo.

[0048] S42: For the interface changes caused by the correction, matching adjustments are performed on both sides of the interface.

[0049] S43: Compile and download related systems.

[0050] S44: Make adaptive adjustments to established operating conditions.

[0051] S44 can ensure that the working conditions meet the requirements of stability, effectiveness, and continuous availability.

[0052] S45: Repeat the above work for iterative verification.

[0053] S46: During the iterative verification process, if the parameters adjusted according to the design do not have a convergence trend, the verification is suspended considering the correctness of the model design.

[0054] In the embodiments of the present application, the differences between the design parameters and the actual parameters are timely discovered and effectively adjusted through dynamic testing, iterative verification and modification. The model design verification is implemented through the simulation platform, and the final consistency between the design parameters and the actual operating parameters is achieved through the iterative recording, analysis and adjustment process, which significantly improves the accuracy and effectiveness of the model design, reduces the cost of on-site commissioning, improves the economic benefits of the industrial steam supply system of the nuclear power plant, and avoids equipment and control system damage caused by on-site commissioning of the operating unit and the safety risks of nuclear power plant operation.

[0055] At least one embodiment of the present application further provides a computer device, which includes a processor and a memory. The processor is used to execute a method for verifying parameters of an industrial steam supply model for a nuclear power plant provided in any of the above embodiments of the present application. The memory is used to store executable instructions of the processor, such as application programs. The number of processors can be one or more. The application program stored in the memory may include one or more modules, each of which corresponds to a set of instructions. In addition, the processor is configured to execute instructions to execute the above-mentioned method for verifying parameters of an industrial steam supply model for a nuclear power plant.

[0056] The computer device may also include a power supply component configured to manage power of the computer device, a wired or wireless network interface configured to connect the computer device to a network, and an input / output (I / O) interface. The computer device may operate based on an operating system stored in the memory, such as Windows Server 2003. TM , Mac OSX TM , Unix TM , Linux TM , FreeBSD TM or similar.

[0057] At least one embodiment of the present application further provides a computer-readable storage medium on which computer executable instructions are stored. When the executable instructions are executed by a processor, the nuclear power plant industrial steam supply model parameter verification method provided in any of the above embodiments of the present application is implemented.

[0058] A non-transitory computer-readable storage medium, when the instructions in the storage medium are executed by the processor of the computer device, enables the computer device to execute the above-mentioned method for verifying parameters of industrial steam supply model of nuclear power plant. The method for verifying parameters of industrial steam supply model of nuclear power plant is executed by an agent program.

[0059] Those of ordinary skill in the art will appreciate that the algorithmic steps of each example described in conjunction with the embodiments disclosed in this application can be implemented in electronic hardware, or a combination of computer software and electronic hardware. Whether these functions are performed in hardware or software depends on the specific application and design constraints of the technical solution. Professional and technical personnel can use different methods to implement the described functions for each specific application, but such implementation should not be considered to be beyond the scope of this application.

[0060] At least one embodiment of the present application further provides a computer program product, including a computer program / instruction, which, when executed by a processor, implements a method for verifying parameters of an industrial steam supply model for a nuclear power plant provided in any of the above embodiments of the present application.

[0061] If the above functions are implemented in the form of software functional units and sold or used as independent products, they can be stored in a computer-readable storage medium. Based on this understanding, the technical solution of the present application, or the part that contributes to the prior art or the part of the technical solution, can be embodied in the form of a computer program product, which is stored in a storage medium and includes several instructions for enabling a computer device (which can be a personal computer, server, or network device, etc.) to execute all or part of the steps of the parameter verification method of the industrial steam supply model of a nuclear power plant in each embodiment of the present application. The aforementioned storage medium includes: U disk, mobile hard disk, read-only memory (ROM), random access memory (RAM), disk or optical disk, and other media that can store program verification codes.

[0062] It should be noted that the combination of the various technical features in the embodiments of the present application is not limited to the combination described in the embodiments of the present application or the combination described in the specific embodiments, and all technical features described in the present application can be freely combined or combined in any way unless there is a contradiction between them.

[0063] As shown in this application and claims, unless the context clearly indicates an exception, the words "a", "an" and / or "the" do not refer to the singular and may also include the plural. Generally speaking, the term "comprising" only indicates that the steps and elements that have been clearly identified are included, and these steps and elements do not constitute an exclusive list. The method or device may also include other steps or elements.

[0064] The above description is only a preferred embodiment of the present application and is not intended to limit the present application. Any modifications, equivalent substitutions, etc. made within the spirit and principles of the present application shall be included in the protection scope of the present application.

Claims

1. A method for verifying parameters of industrial steam supply model of nuclear power plant, characterized in that: include: Completely copy the main instrumentation and control screens and logic of the units involved in the heat exchange system of the industrial steam supply power plant side of the nuclear power plant to the simulation platform, connect them with the existing logic of the simulation platform, and generate an instrumentation and control simulation model; Based on the communication interface between the process simulation model and the instrumentation and control simulation model of the existing full-range simulation platform of the nuclear power plant, the communication interface of the newly added process system simulation model and the newly added instrumentation and control system simulation model is supplemented and updated; Based on the updated full-range simulation platform, a full-range operating condition is established, and static parameter comparison is performed with reference to the corresponding operating conditions of the unit to analyze the differences and propose a design parameter adjustment plan. The full-range operating conditions include full power, various power platform conditions, design benchmark accident conditions and steam-electric coordination conditions; If the parameters are adjusted according to the design parameter adjustment plan, the adjusted parameters will be updated to the simulation platform process / instrumentation and control simulation system.

2. A method for verifying parameters of a nuclear power plant industrial steam supply model according to claim 1, characterized in that: Based on the updated full-range simulation platform, the full-range operating conditions are established, and static parameter comparison is performed with reference to the corresponding operating conditions of the unit, and the differences are analyzed to propose design parameter adjustment plans, including: Establish a comparison list of key parameters, curves, and data for reference units; Establish full-range operating conditions based on the updated full-range simulation platform; Perform dynamic tests for each operating condition in real time and use real-time data logging tools to fully record key parameters; After the dynamic test is completed, the corresponding operation curve or node data is obtained based on the key parameters; Compare the parameter design and actual data, analyze the differences, and propose design parameter adjustment plans.

3. A method for verifying parameters of industrial steam supply model of a nuclear power plant according to claim 2, characterized in that: Establish a full range of operating conditions based on the updated full range simulation platform, including: Using the historical operating data of the reference unit as a reference, a full-power operating condition is established, and the operating condition is frozen after a preset period of stable operation. In the frozen state, the key parameters and curves of the operating condition are consistent with the historical operating data of the corresponding operating condition of the reference unit; Based on the full power condition, the operating conditions of each power platform are established using the historical operating data of the reference unit as a reference. Each power platform condition is frozen after running smoothly for a preset period of time. In the frozen state, the key parameters and curves of each power platform condition are consistent with the historical operating data of the corresponding condition of the reference unit. Based on the full power condition, the design base accident condition is established in combination with the reference unit operating procedures and specifications. During the operation of the design base accident condition, the operation is carried out in real time according to the operating procedures and specifications, and is frozen after the end of the procedures. In the frozen state, the key parameters and curves of the design base accident condition are consistent with the historical operation data of the corresponding condition of the reference unit; Based on the full-power condition, the steam-electric coordination condition is established in combination with the operating procedures and specifications of the reference unit. During the operation of the steam-electric coordination condition, real-time operation is carried out according to the operating procedures and specifications and the condition is frozen after the end of the procedures. In the frozen state, the key parameters and curves of the steam-electric coordination condition are consistent with the historical operating data of the corresponding condition of the reference unit.

4. A method for verifying parameters of an industrial steam supply model for a nuclear power plant according to any one of claims 1 to 3, characterized in that: If the parameters are adjusted according to the design parameter adjustment plan, the adjusted parameters will be updated to the simulation platform process / instrumentation control simulation system, including: If the parameters are adjusted according to the design parameter adjustment plan, the corresponding process / instrumentation control simulation system parameter correction is implemented through the graphical configuration tool on the simulation platform, and the correction content is marked with a memo; For interface changes caused by the revision, matching adjustments are implemented on both sides of the interface work; Compile and download related systems; Adaptive adjustments to established operating conditions; Repeat the above work for iterative verification; During the iterative verification process, if the parameters adjusted according to the design do not have a convergence trend, the verification is suspended considering the correctness of the model design.

5. A computer device, characterized in that: include: A processor, configured to execute a method for verifying parameters of an industrial steam supply model for a nuclear power plant according to any one of claims 1 to 4; as well as A memory is used to store executable instructions of the processor.

6. A computer-readable storage medium having computer executable instructions stored thereon, characterized in that: When the executable instructions are executed by the processor, a method for verifying parameters of an industrial steam supply model for a nuclear power plant according to any one of claims 1 to 4 is implemented.

7. A computer program product comprising a computer program / instructions, characterized in that When the computer program / instructions are executed by a processor, a method for verifying parameters of an industrial steam supply model for a nuclear power plant according to any one of claims 1 to 4 is implemented.

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