MBSE-based nuclear reactor architecture design method

Abstract

The embodiment of the invention relates to the technical field of nuclear reactors, in particular to a nuclear reactor architecture design method based on MBSE, which comprises the following steps: S1, performing demand analysis on a nuclear reactor according to the power supply and heat supply capacity demand of the nuclear reactor, and determining the model requirement of the nuclear reactor; s2, performing function analysis on the nuclear reactor according to the model requirement of the nuclear reactor, and determining all sub-function components of the nuclear reactor and interfaces among the sub-functions; s3, performing logic analysis on the nuclear reactor according to all the sub-functions of the nuclear reactor and the interfaces among the sub-functions, and determining the system equipment composition of the nuclear reactor, the internal and external interfaces of the system equipment and the index parameters of the system equipment; and S4, determining a design scheme of the nuclear reactor according to the composition of the system equipment of the nuclear reactor, the internal and external interfaces of the system equipment and the index parameters of the system equipment. According to the embodiment of the invention, efficient and reasonable nuclear reactor design guidance can be provided, and the design efficiency of the nuclear reactor can be improved.

Description

Technical Field

[0001] The embodiments of the present application relate to the field of nuclear reactor technology, and specifically to a nuclear reactor architecture design method based on MBSE. Background Art

[0002] The statements herein merely provide background information related to the present application and do not necessarily constitute prior art.

[0003] A nuclear reactor is a typical complex system involving multiple professions and disciplines. The traditional document-based design method is difficult to cope with the rapid design iteration brought about by changes in demand scenarios. Design information is scattered in documents and various software, making it difficult to establish a unified data source traceability chain and realize simulation verification of early solutions. Summary of the invention

[0004] A brief overview of the present application is provided below in order to provide a basic understanding of certain aspects of the present application. It should be understood that this overview is not an exhaustive overview of the present application. It is not intended to identify the key or important parts of the present application, nor is it intended to limit the scope of the present application. Its purpose is merely to present certain concepts in a simplified form as a prelude to a more detailed description discussed later.

[0005] In response to the above problems, an embodiment of the present application provides a nuclear reactor architecture design method based on MBSE, which may include: S1. According to the power supply and heating capacity requirements of the nuclear reactor, perform a demand analysis on the nuclear reactor to determine the model requirements of the nuclear reactor; S2. According to the model requirements of the nuclear reactor, perform a functional analysis on the nuclear reactor to determine all sub-function components of the nuclear reactor and interfaces between sub-functions; S3. According to all sub-functions of the nuclear reactor and interfaces between sub-functions, perform a logical analysis on the nuclear reactor to determine the system equipment composition of the nuclear reactor, the internal and external interfaces of the system equipment, and the index parameters of the system equipment; S4. According to the system equipment composition of the nuclear reactor, the internal and external interfaces of the system equipment, and the index parameters of the system equipment, determine the design scheme of the nuclear reactor.

[0006] The method provided in the embodiment of the present application can carry out demand analysis according to the power supply and heating capacity requirements to determine the model requirements of the nuclear reactor, and can also carry out functional analysis according to the model requirements of the nuclear reactor to determine all sub-function components of the nuclear reactor and the interfaces between the sub-functions. After that, it can also carry out logical analysis of the nuclear reactor according to all the sub-functions of the nuclear reactor to determine the system equipment composition of the nuclear reactor, the internal and external interfaces of the system equipment and the index parameters of the system equipment. Finally, it can determine the design scheme of the nuclear reactor according to the system equipment composition of the nuclear reactor, the internal and external interfaces of the system equipment and the index parameters of the system equipment, so as to provide efficient and reasonable method guidance for the design of the nuclear reactor, which is conducive to improving the design efficiency of the nuclear reactor.

[0007] The MBSE-based nuclear reactor architecture design method provided in the embodiment of the present application executes overall design processes such as business scenario analysis, requirement definition, function decomposition, system equipment composition, and solution trade-offs through a graphical language and model-driven approach, assists in the definition of design requirements, system equipment composition, and interface division, can perform indicator traceability verification, and support the overall design optimization and iteration of nuclear reactors. BRIEF DESCRIPTION OF THE DRAWINGS

[0008] Other objects and advantages of the present application will become apparent from the following description of the embodiments of the present application with reference to the accompanying drawings, and will help to provide a comprehensive understanding of the present application.

[0009] Figure 1 It is a flow chart of the MBSE-based nuclear reactor architecture design method provided in an embodiment of the present application.

[0010] Figure 2 It is a flow chart of using a model to perform architectural design modeling on a nuclear reactor provided in an embodiment of the present application.

[0011] Figure 3 It is a flow chart of analyzing the requirements of a reactor using a model provided in an embodiment of the present application.

[0012] Figure 4 It is a schematic diagram of the dynamic interaction scenario of power operation.

[0013] Figure 5 It is a schematic diagram of the external interface of the power operation dynamic interaction scenario.

[0014] Figure 6 It is a flow chart of analyzing the function of a reactor using a model provided in an embodiment of the present application.

[0015] Figure 7 It is a schematic diagram of a functional flow analysis of a nuclear reactor power generation function provided in an embodiment of the present application.

[0016] Figure 8 It is a schematic diagram of a scenario in which the coolant provides a power sub-function failure response provided in an embodiment of the present application.

[0017] Fig. 9 It is a schematic diagram of the sub-function interaction scenario in the nuclear reactor power operation scenario.

[0018] Fig.10 It is a flow chart of using a model to perform logical analysis on a nuclear reactor provided in an embodiment of the present application.

[0019] Fig.11 It is a schematic diagram of a nuclear reactor system equipment composition model provided according to an embodiment of the present application.

[0020] Fig.12 It is a schematic diagram of a nuclear reactor power operation logic interaction scenario model provided according to an embodiment of the present application.

[0021] Fig.13 It is a schematic diagram of the internal and external interface model of a nuclear reactor in an embodiment of the present application.

[0022] Description of reference numerals:

[0023] 1000. Nuclear reactor;

[0024] 100. Reactor core system; 200. Primary loop system; 210. Main pump; 220. Heat exchanger; 230. Impurity removal device; 300. Power conversion system; 400. Waste heat discharge system;

[0025] 31. Power generation control command; 32. Power generation adjustment command; 33. Power generation command; 34. Electric energy; 35. Seawater; 36. Waste heat; 37. Status monitoring feedback information; 38. Initial startup power supply;

[0026] 101. Command interface; 102. Status interface; 103. Water source interface; 104. Power interface; 105. Output power interface; 106. Waste heat discharge interface;

[0027] 13. Operating personnel; 15. Power supply; 16. Power grid; 17. Ocean.

[0028] It should be noted that the drawings are not necessarily drawn to scale, but are merely shown in a schematic manner that does not affect the reader's understanding. DETAILED DESCRIPTION

[0029] Exemplary embodiments of the present application will be described below in conjunction with the accompanying drawings. For the sake of clarity and conciseness, not all features of the actual implementation are described in the specification. However, it should be understood that many implementation-specific decisions must be made in the process of developing any such actual implementation in order to achieve the developer's specific goals, such as meeting those constraints related to the system and business, and these constraints may vary from implementation to implementation. In addition, it should be understood that although the development work may be very complex and time-consuming, it is only a routine task for those skilled in the art who benefit from the content of this application.

[0030] It is also necessary to explain here that, in order to avoid obscuring the present application due to unnecessary details, only the device structure and / or processing steps closely related to the scheme according to the present application are shown in the accompanying drawings, while other details that are not very relevant to the present application are omitted.

[0031] See also Figure 1 and Figure 2 The embodiment of the present application provides a nuclear reactor architecture design method based on MBSE, which may include: S1. According to the power supply and heating capacity requirements of the nuclear reactor, perform demand analysis on the nuclear reactor to determine the model requirements of the nuclear reactor; S2. According to the model requirements of the nuclear reactor, perform functional analysis on the nuclear reactor to determine all sub-function components of the nuclear reactor and interfaces between sub-functions; S3. According to all sub-functions of the nuclear reactor and interfaces between sub-functions, perform logical analysis on the nuclear reactor to determine the system equipment composition of the nuclear reactor, the internal and external interfaces of the system equipment, and the index parameters of the system equipment; S4. According to the system equipment composition of the nuclear reactor, the internal and external interfaces of the system equipment, and the index parameters of the system equipment, determine the design scheme of the nuclear reactor.

[0032] The method provided in the embodiment of the present application can carry out demand analysis according to the power supply and heating capacity requirements to determine the model requirements of the nuclear reactor, and can also carry out functional analysis according to the model requirements of the nuclear reactor to determine all sub-function components of the nuclear reactor and the interfaces between the sub-functions. After that, it can also carry out logical analysis of the nuclear reactor according to all the sub-functions of the nuclear reactor to determine the system equipment composition of the nuclear reactor, the internal and external interfaces of the system equipment and the index parameters of the system equipment. Finally, it can determine the optimal design scheme of the nuclear reactor according to the system equipment composition of the nuclear reactor, the internal and external interfaces of the system equipment and the index parameters of the system equipment, so as to provide efficient and reasonable method guidance for the design of the nuclear reactor, which is conducive to improving the design efficiency of the nuclear reactor.

[0033] In some embodiments, step S1 may include: S11. Determine the mission scenarios of the entire life cycle stages of the nuclear reactor based on the power supply and heating capacity requirements of the nuclear reactor; S12. Determine the stakeholders of each mission scenario of the nuclear reactor corresponding to each life cycle stage based on the mission scenarios of the entire life cycle stages of the nuclear reactor; S13. Determine the stakeholder needs of the nuclear reactor based on the stakeholders of each mission scenario of the nuclear reactor corresponding to each life cycle stage; S14. Perform dynamic interactive scenario analysis based on the mission scenarios of the entire life cycle stages of the nuclear reactor and the stakeholder needs of the nuclear reactor to determine the model requirements of the nuclear reactor.

[0034] The above embodiment is essentially to determine the model of the nuclear reactor based on the nuclear reactor demand analysis. The above demand analysis method can carry out demand analysis according to the power supply and heating capacity demand, taking into account the entire life cycle stage of the nuclear reactor, determine the task scenarios of all life cycle stages, and determine the stakeholders according to the task scenarios of all life cycle stages, and then determine the stakeholder needs according to the stakeholders of each task scenario, and perform dynamic scenario interaction analysis to determine the model requirements of the nuclear reactor, which is conducive to a more comprehensive analysis of the needs of the nuclear reactor, and determine clearer and more complete nuclear reactor requirements, thereby providing clear design goals for the designers of the nuclear reactor, so as to avoid the designed nuclear reactor from not covering all needs or some needs being ignored, etc.

[0035] In the demand analysis of related technologies, stakeholders are directly identified based on the entire life cycle. Compared with identifying stakeholders based on the entire life cycle, the demand analysis method of the embodiment of the present application starts with the analysis of the task scenarios of the entire life cycle. The method of using scenarios can more accurately and comprehensively identify stakeholders, and then sort out the needs of stakeholders. In addition, the embodiment of the present application performs dynamic scenario interaction analysis from the perspective of the full life cycle task scenarios, and can comprehensively identify the external interfaces that the nuclear reactor should meet in various scenarios, thereby more comprehensively sorting out the model requirements of the nuclear reactor.

[0036] In some embodiments, step S11 includes step S111 and step S112. S111, determining the entire life cycle stages of the nuclear reactor according to the power supply and heating capacity requirements of the nuclear reactor; S112, determining the mission scenarios of the entire life cycle stages of the nuclear reactor according to the entire life cycle stages of the nuclear reactor.

[0037] In some embodiments, all life cycle stages of the nuclear reactor in step S111 may include: a procurement stage, a deployment stage, an operation stage, a support stage, and a withdrawal stage.

[0038] In some embodiments, all life cycle stages can be further divided according to the nuclear reactor mission requirements. For example, the acquisition stage may include the manufacturing stage and the purchasing stage; the deployment stage may include the installation stage, the commissioning stage, and the test stage; the operation stage may include the start-up stage and the power increase stage; the support stage may include the maintenance stage; and the exit stage may include the decommissioning stage.

[0039] In some embodiments, in step S112, when determining the corresponding mission scenario for each life cycle stage, the mission scenario can be determined based on the five life cycle stages of acquisition, deployment, operation, support, and exit, considering that the nuclear reactor "does something" in each life cycle stage.

[0040] Specifically, the task scenarios corresponding to the procurement stage include: transportation scenarios, etc.; the task scenarios corresponding to the deployment stage include: assembly and integration scenarios, debugging and testing scenarios, etc.; the task scenarios corresponding to the operation stage include: start-up scenarios, power increase scenarios, power operation scenarios, etc.; the task scenarios corresponding to the support stage include: maintenance scenarios, etc.; the task scenarios corresponding to the exit stage include: decommissioning scenarios, etc.

[0041] In some embodiments, in step S12, stakeholder identification may be performed based on various mission scenarios of the nuclear reactor to determine all stakeholders of the nuclear reactor.

[0042] Specifically, the identified stakeholders may include transportation regulatory authorities related to transportation scenarios, installers and nuclear safety regulatory authorities related to assembly and integration scenarios, and nuclear safety regulatory authorities, operators, surrounding residents, external environment, and oceans related to power operation scenarios. When identifying stakeholders for each mission scenario corresponding to each life cycle stage of a nuclear reactor, the integrity of the stakeholders should be ensured to avoid missing any stakeholders.

[0043] In some embodiments, step S12 may include: clustering and abstracting high-level stakeholders according to the same type of stakeholders from stakeholders of each task scenario in all life cycle stages based on their relationship with the nuclear reactor.

[0044] In some embodiments, in step S12, before clustering and abstracting high-level stakeholders according to the same type of stakeholders, it also includes: eliminating unnecessary stakeholders according to the task requirements of the nuclear reactor. In some embodiments, after determining all stakeholders of each task scenario corresponding to each life cycle stage, unnecessary stakeholders can be eliminated in combination with the task requirements of the nuclear reactor. For example, in the power operation scenario, the stakeholder of the surrounding residents is identified. In combination with the actual application scenario, if there are no residents around the operation site, this stakeholder is considered to be removed.

[0045] In some embodiments, when clustering and abstracting, attention should be paid to the uniformity of the number, and the number of high-level stakeholders is generally 7±2. In some embodiments, the high-level stakeholders of the cluster may be regulators, and the low-level stakeholders may be nuclear safety regulators, environmental protection departments, transportation regulatory departments, etc. In some embodiments, the above method can be implemented using a model.

[0046] In some embodiments, in step S13, a stakeholder demand analysis is performed on stakeholders of each task scenario corresponding to each life cycle stage of the nuclear reactor to determine the demands of each stakeholder of the nuclear reactor.

[0047] In some embodiments, for example, the stakeholders of the assembly and integration scenario in the deployment phase may be installers, and the installer requirements may be requirements for the installers to reserve installation space for the nuclear reactor, and the installation size may be proposed to be no less than a certain size; the stakeholders of the power operation scenario in the operation phase may be the environmental protection department, and the environmental protection department requirements may be requirements for the environmental protection department to require that the emissions of nuclear reactor waste gas, waste liquid, and waste solid do not exceed a specific threshold value; the stakeholders of the power operation scenario may also be users, and the user requirements may be requirements for users to require that the nuclear reactor can provide a certain amount of electrical energy; the stakeholders of the maintenance scenario in the support phase may be maintenance personnel, and the maintenance personnel requirements may be requirements for the maintenance personnel to reserve maintenance space for the nuclear reactor, and the size of the maintenance space may be no less than a certain size; the stakeholders of the decommissioning scenario in the exit phase may be the decommissioning support department, and the decommissioning support department requirements may be requirements for the decommissioning support department to reserve a disassembly and assembly interface for the nuclear reactor.

[0048] In some embodiments, step S14 includes step S141 and step S142. S141. According to the mission scenarios of all life cycle stages of the nuclear reactor, dynamic scenario interaction analysis is performed to define the external interface of the nuclear reactor. S142. According to the stakeholder needs and external interface of the nuclear reactor, the model requirements of the nuclear reactor are determined.

[0049] In some embodiments, in step S142, the requirements of stakeholders may be converted into model requirements of nuclear reactors or the external interface may be converted into model requirements of nuclear reactors to determine the model requirements of nuclear reactors. For example, the user's requirement that the nuclear reactor can provide a certain amount of electrical energy may be converted into the power generated by the nuclear reactor, or the waste heat discharge interface may be converted into an external interface requirement that the nuclear reactor must have to discharge waste heat to the external environment.

[0050] In some embodiments, step S2 may include: S21. Determine the top-level functions of the nuclear reactor according to the requirements of the nuclear reactor model; S22. Perform a functional flow analysis on each top-level function and decompose the top-level function into multiple sub-functions; S23. Perform a sub-function failure analysis on the multiple sub-functions decomposed from the top-level functions and identify new sub-functions; S24. Determine the composition of all sub-functions of the nuclear reactor based on the functional flow analysis and sub-function failure analysis; S25. Perform a sub-function interaction scenario analysis based on the task scenarios and all sub-functions of the entire life cycle stage of the nuclear reactor to determine the interfaces between all sub-functions of the nuclear reactor.

[0051] The above-mentioned embodiments are essentially based on the analysis of nuclear reactor functions to determine all sub-functions of a nuclear reactor and the interfaces between all sub-functions. The functional analysis method provided in the embodiments of the present application, taking the model requirements of the nuclear reactor as input, can more comprehensively determine all top-level functions of the nuclear reactor, and can more reasonably perform functional decomposition from the two aspects of functional flow analysis (corresponding to normal scenarios) and sub-function failure analysis (corresponding to abnormal scenarios), thereby more comprehensively determining the functional composition of the nuclear reactor; and the method provided in the embodiments of the present application can more comprehensively determine the functional interface of the nuclear reactor through sub-function interaction scenario analysis, which can lay the foundation for the subsequent reasonable division of the nuclear reactor system and the division of equipment composition.

[0052] The method provided in the embodiment of the present application can more comprehensively determine the functional interface of the nuclear reactor through functional interaction scenario analysis, and can lay the foundation for the subsequent reasonable division of the nuclear reactor system and the division of equipment components.

[0053] The method provided in the embodiment of the present application is composed according to all functions. Through the analysis of sub-function interaction scenarios, the interfaces between sub-functions can be comprehensively determined. Combined with the external interfaces determined by the demand analysis, the internal and external functional interfaces of the nuclear reactor can be analyzed. At the same time, through the analysis of sub-function interaction scenarios, it is verified that the full-cycle task scenarios are met, thereby ensuring that the functional analysis process can meet the demand analysis process of the nuclear reactor.

[0054] In some embodiments, the model requirements of the nuclear reactor in step S21 may include: nuclear reactor function requirements, nuclear reactor performance requirements, nuclear reactor interface requirements, etc.

[0055] The corresponding nuclear reactor functional requirements include: for example, the power generation of the nuclear reactor is xx, the nuclear reactor can discharge waste heat, the nuclear reactor can operate and control, etc.; the corresponding nuclear reactor performance requirements include: for example, the weight of the nuclear reactor is xx, the size of the nuclear reactor is xx, the reliability of the nuclear reactor is xx, the life of the nuclear reactor is xx, etc.; the corresponding interface requirements include: for example, the nuclear reactor needs to have an interface for discharging waste heat to the external environment, the nuclear reactor needs to have an interface for power supply and distribution, etc. Identify the top-level functions such as power generation function, safety function, operation control function, etc. from the nuclear reactor functional requirements.

[0056] In some embodiments, in step S22, when performing function flow analysis on each top-level function to decompose it into multiple sub-functions, the top-level function can be decomposed layer by layer until the bottom-level sub-function can be assigned to an entity for implementation.

[0057] In some embodiments, the multiple sub-functions decomposed from the top-level function include both the multiple sub-functions decomposed from the top-level function according to the type of the action object and the multiple sub-functions decomposed from the top-level function according to the change of the action object or the process scenario.

[0058] In some embodiments, step S22 may include: decomposing the top-level function into multiple sub-functions according to the type of the object of action. For example, decomposing the energy providing function into providing mechanical energy, providing thermal energy, providing electrical energy, etc. according to the type of the object of action.

[0059] In some embodiments, step S22 may further include: decomposing the top-level function into multiple sub-functions according to the changes in the object of action or the process scenario. Figure 7 For example, the top-level function "power generation function" is subjected to functional flow analysis, and the power generation function is decomposed into heat generation function, heat transfer function, thermoelectric conversion function and waste heat discharge function. Furthermore, the heat transfer function can be decomposed into a series of functions related to material change processes, such as providing power to the coolant and low-temperature flow of the coolant.

[0060] In some embodiments, step S22 may further include: performing sub-function analysis based on the sub-functions to determine the missing sub-functions. When performing sub-function analysis to determine the missing sub-functions, each sub-function may be analyzed from the four dimensions of "who, where, what, and to what extent" to determine the missing sub-functions. The sub-functions are continuously optimized through this iterative process. For example, based on the analysis of the coolant cryogenic flow sub-function, the missing sub-functions such as coolant gas coverage and coolant impurity removal are identified.

[0061] In some embodiments, step S23 may further include: performing sub-function failure analysis according to the sub-functions to determine the sub-functions that need to be added. For example, after the power supply function fails, a waste heat removal function needs to be added.

[0062] In some embodiments, in step S23, performing sub-function failure analysis based on the sub-functions, and determining the sub-functions that need to be added may include: S231, determining sub-function failure modes for multiple sub-functions decomposed from the top-level functions; S232, determining the safety impact of each sub-function failure on the nuclear reactor based on the sub-function failure modes; S233, determining whether it is necessary to add new sub-functions to reduce the safety impact of sub-function failure on the nuclear reactor based on the safety impact of sub-function failure on the nuclear reactor; S234, when it is determined that new sub-functions need to be added, constructing sub-function failure response scenarios; S235, determining new sub-functions based on the sub-function failure response scenarios.

[0063] In some embodiments, step S24 also includes sorting out all the sub-functional components of the nuclear reactor based on the sub-functionalities analyzed from the functional flows, such as heat generation function, heat transfer function, thermoelectric conversion function, waste heat discharge function, providing power to the coolant, low-temperature flow of the coolant, etc., as well as the functions analyzed from the sub-functional failures, such as the residual heat extraction function.

[0064] In some embodiments, step S25 also includes: performing interaction analysis between the sub-functions based on the task scenarios and all sub-functions of the entire life cycle stages of the nuclear reactor. The entire life cycle stages of the nuclear reactor may include: procurement stage, deployment stage, operation stage, support stage and exit stage.

[0065] Specifically, the task scenarios corresponding to the procurement stage include: transportation scenarios, etc.; the task scenarios corresponding to the deployment stage include: assembly and integration scenarios, debugging and testing scenarios, etc.; the task scenarios corresponding to the operation stage include: start-up scenarios, power increase scenarios, power operation scenarios, etc.; the task scenarios corresponding to the support stage include: maintenance scenarios, etc.; the task scenarios corresponding to the exit stage include: decommissioning scenarios, etc.

[0066] Take the sub-function interaction scenario in the power operation scenario as an example. Fig. 9 As shown, the coordination between each sub-function is analyzed to meet the power operation scenario. For example, with nuclear fuel as input, nuclear reaction heat is generated, and nuclear reaction heat and nuclear reactor radiation are output; with nuclear reaction heat as input, nuclear reaction heat generation and nuclear reaction heat generation reception interact with each other, and nuclear reaction heat generation reception, heat transfer, and heat output interact with each other, and heat transfer energy is output; with heat transfer energy as input, heat transfer and heat transfer reception interact with each other, and heat transfer reception, heat energy conversion to mechanical energy, and mechanical energy conversion to electrical energy interact with each other, and heat energy and electrical energy are output; with thermoelectric conversion output heat energy as input, heat transfer reception interacts with heat reception, and heat reception and waste heat discharge interact with each other, and waste heat is output.

[0067] According to the above sub-function interaction scenarios, determine the interfaces between sub-functions such as nuclear fuel interface, nuclear reaction radiation interface, nuclear reaction heat interface, thermal energy interface, mechanical energy interface, electrical energy interface, waste heat interface, etc.

[0068] Fig.10 is a flow chart of using a model to perform logical analysis on a nuclear reactor according to an embodiment of the present application. Fig.10 In some embodiments, step S3 may include: S31. Combining and distributing all sub-functions of the nuclear reactor to determine the system equipment composition of the nuclear reactor, and the system equipment composition of the nuclear reactor corresponds to the system equipment composition of the nuclear reactor; S32. According to the interaction scenarios of all sub-functions of the nuclear reactor and the system equipment composition of the nuclear reactor, a logical interaction scenario analysis is performed to enable the system equipment composition of the nuclear reactor to meet the task scenarios of all life cycle stages of the nuclear reactor; S33. According to the logical interaction scenario, an interface analysis is performed on the system equipment of the nuclear reactor to determine the internal and external interfaces of the system equipment of the nuclear reactor; S34. According to the logical interaction scenario, the correlation relationship of the key indicators of the nuclear reactor is analyzed to sort out the correlation relationship of the key indicators of the nuclear reactor as a whole, the system, and the equipment; S35. According to the said key indicator correlation relationship, the indicator decomposition is performed to determine the indicator parameters of the nuclear reactor system equipment.

[0069] The above-mentioned embodiment is essentially to determine the internal and external interfaces of the system equipment of the nuclear reactor based on the nuclear reactor logic analysis, and determine the index parameters of the system equipment of the nuclear reactor. The system equipment composition of the nuclear reactor (i.e., the structural configuration of the nuclear reactor) is determined according to all the sub-functions of the nuclear reactor. By performing a logical interaction scenario analysis on the system equipment composition of the nuclear reactor, the interfaces between the various system equipment can be comprehensively analyzed. Combined with the external interface of the demand analysis, all the internal and external interfaces of the nuclear reactor can be analyzed; at the same time, through the logical interaction scenario analysis, it can be verified that each sub-function interaction scenario is met, thereby verifying that the mission scenario of the entire life cycle is met, so as to ensure that the system equipment composition of the nuclear reactor and the internal and external interfaces of the system equipment are reasonable and meet the user's requirements or application scenarios.

[0070] The method provided in the embodiments of the present application can take into account the mission scenarios of all life cycle stages of a nuclear reactor, so that when the mission scenarios change, the composition of the nuclear reactor system equipment can quickly respond to the changes, thereby facilitating the determination of the system equipment composition and interfaces of the nuclear reactor, accelerating the overall design iteration, and improving the efficiency of nuclear reactor design; the method provided in the embodiments of the present application also optimizes the system equipment composition by performing logical interaction scenario analysis, thereby making the logical design of the nuclear reactor more reasonable.

[0071] In some embodiments, step S31 includes step S311 and step S312: S311, allocating all sub-functions of the nuclear reactor to multiple devices of the nuclear reactor, wherein each sub-function is implemented by one device, each device can implement at least one sub-function, and all devices can implement all sub-functions of the nuclear reactor; S312, allocating all devices to multiple nuclear reactor systems to determine the system equipment composition of the nuclear reactor.

[0072] In some embodiments, in step S311, when a sub-function is allocated to more than one device, the sub-function needs to be further decomposed until each of the decomposed sub-functions can be allocated to a device respectively.

[0073] In the process of combining and allocating all sub-functions to the logical structure, the principle to be followed is: one device can undertake multiple sub-functions, but one sub-function corresponds to at most one device. If one sub-function corresponds to multiple devices, the sub-function needs to be further decomposed until one sub-function corresponds to at most one device.

[0074] In some embodiments, in step S311, all sub-functions of the nuclear reactor are allocated to multiple devices according to the number and mode of interaction inside and outside the device. Specifically, there are two bases in the sub-function combination allocation process: (1) the number of interactions inside the device is large, while the number of interactions with the outside of the device is small; (2) the interaction mode inside the device is similar, and the interaction mode with the outside of the device is quite different. In some embodiments, for example, the nuclear reactor sub-function is allocated to the fuel assembly, the coolant power supply sub-function is allocated to the pump, the low-temperature coolant flow and high-temperature coolant flow are allocated to the coolant pipeline, the coolant and working fluid side heat exchange sub-function is allocated to the heat exchanger, the low-temperature working fluid flow and high-temperature working fluid flow sub-functions are allocated to the working fluid pipeline, and the working fluid working sub-function is allocated to the steam turbine, etc.

[0075] In some embodiments, in step S312, all the equipment determined in step S311 can be divided into multiple systems in combination with the composition characteristics of the nuclear reactor system, thereby determining the system equipment composition of the nuclear reactor. For example, the main pump, heat exchanger and other equipment are allocated to the primary loop system, and the nuclear reactor is composed of the nuclear reactor core system, the primary loop system, the power conversion system, the waste heat discharge system and the like.

[0076] In some embodiments, step S32 may include: performing a logical interaction scenario analysis based on the interfaces between all sub-functions of the nuclear reactor and the system equipment composition of the nuclear reactor to verify whether the system equipment composition of the nuclear reactor meets the mission scenarios of all life cycle stages of the nuclear reactor. If the system equipment composition of the nuclear reactor does not meet the mission scenarios of all life cycle stages of the nuclear reactor, then re-determine the system equipment composition of the nuclear reactor until it meets the mission scenarios of all life cycle stages of the nuclear reactor.

[0077] In some embodiments, step S33 may include: performing interface analysis on the system equipment of the nuclear reactor according to the logical interaction scenario to determine the interaction between the nuclear reactor system equipment; and determining the internal and external interfaces of the nuclear reactor system equipment according to the interaction between the nuclear reactor system equipment.

[0078] In some embodiments, the internal and external interfaces of the nuclear reactor, such as the external interface of the reactor core system, include a nuclear fuel interface, a nuclear reaction radiation interface, etc.; the internal interface between the reactor core system and the primary loop includes a thermal energy interface, a coolant interface, etc.; the internal interface between the primary loop system and the power conversion system includes a thermal energy interface, etc.; the external interface of the power conversion system includes an electrical energy interface, etc.; the internal interface between the power conversion system and the waste heat discharge system includes a thermal energy interface, a mechanical force interface, etc.; the external interface of the waste heat discharge system includes a waste heat interface, etc.

[0079] In some embodiments, step S4 may include: S41, selecting equipment and determining a variety of alternative design schemes based on the functions, interfaces, and index parameters to be achieved by the system equipment of the nuclear reactor; S42, weighing the alternative design schemes based on the various alternative design schemes and determining the optimal design scheme for the nuclear reactor.

[0080] In some embodiments, the nuclear reactor architecture design method can be implemented using model-based system engineering. The nuclear reactor design methods in related technologies are mostly carried out in the form of documents. This design method is difficult to cope with the rapid iteration of design caused by changes in demand scenarios, and it is difficult to establish a unified data source traceability chain to achieve simulation verification of early design solutions. The method provided in the embodiments of the present application is implemented using model-based system engineering, which can adapt to the rapid iteration of the design by updating the model. At the same time, it can also carry out simulation verification of the design method through the model, support the definition of nuclear reactor design requirements, system equipment composition and interface division, and indicator traceability verification, which is conducive to improving the rationality of nuclear reactor design and improving the design efficiency of nuclear reactors.

[0081] The process of using the model to analyze the needs of the reactor provided in the embodiment of the present application is as follows: Figure 3 In some embodiments, step S1 may further include: steps S101 to S107.

[0082] S101. Construct a nuclear reactor life cycle model using a SysML state machine diagram. The nuclear reactor life cycle model uses the SysML state machine diagram to represent all life cycle stages of the nuclear reactor.

[0083] S102. According to the nuclear reactor life cycle model, determine the task scenarios of all life cycle stages of the nuclear reactor, and use SysML module definition diagram / use case diagram to construct the task scenario model of the nuclear reactor.

[0084] S103. According to the task scenario model of each life cycle stage of the nuclear reactor, determine the stakeholders of the task scenario model corresponding to each life cycle stage of the nuclear reactor, and use the SysML module definition diagram to construct the stakeholder model of each task scenario corresponding to each life cycle stage of the nuclear reactor.

[0085] S104. Determine stakeholder requirements based on the stakeholder model of the nuclear reactor corresponding to the task scenarios of each life cycle stage, and construct the stakeholder requirement model using the SysML requirement diagram.

[0086] S105. According to the task scenario model of the nuclear reactor, determine the dynamic interaction process between the stakeholders and the nuclear reactor, and use the SysML sequence diagram to build a dynamic interaction scenario model.

[0087] S106. Perform dynamic interaction scenario analysis according to the dynamic interaction scenario model, determine the external interface of the nuclear reactor, and construct the external interface model using the SysML internal block diagram.

[0088] S107. Determine the model requirements of the nuclear reactor according to the stakeholder requirement model and the external interface model, and construct a model requirement model of the nuclear reactor using a SysML requirement diagram / requirement list.

[0089] Specifically, in step S101, the power supply and heating capacity requirements of the nuclear reactor can be used as input to identify the life cycle stages of the nuclear reactor, and the life cycle can be divided into five categories: procurement, deployment, operation, support, and exit. According to the mission requirements of the nuclear reactor, the five life cycles are further divided, such as the procurement stage is divided into the manufacturing stage, the procurement stage, etc., the deployment is divided into the installation stage, the commissioning stage, the test stage, etc., the operation is divided into the start-up stage, the power increase stage, etc., the support is divided into the maintenance stage, etc., and the exit is divided into the decommissioning stage, etc. The nuclear reactor life cycle stages represented by the SysML state machine diagram (i.e., the nuclear reactor life cycle model is constructed using the SysML state machine diagram) are used as output.

[0090] In some embodiments, in step S102, when determining the task scenarios corresponding to each life cycle stage, it is possible to consider the nuclear reactor "doing something" in each life cycle stage based on the five life cycle stages of acquisition, deployment, operation, support and exit, identify task scenarios, such as assembly and integration scenarios, debugging and test scenarios, reactor criticality scenarios, power increase scenarios, power operation scenarios, maintenance scenarios, etc., and use SysML module definition diagrams / use case diagrams to represent them.

[0091] In step S102, the life cycle represented by the SysML state machine diagram can be used as input to obtain the task scenario represented by the SysML module definition diagram / use case diagram, such as transportation scenario, assembly integration scenario, debugging test scenario, stack start-up scenario, power increase scenario, maintenance scenario, decommissioning scenario, etc.

[0092] In some embodiments, in step S103, the obtained stakeholders can be clustered and abstracted into high-level stakeholders according to the same type of stakeholders. Specifically, the nuclear reactor life cycle stage represented by the SysML state machine diagram can be used as input, and based on the task scenarios of the five life cycle stages of the nuclear reactor, such as procurement, deployment, operation, support, and exit, stakeholders can be identified, such as the transportation regulatory department related to the transportation scenario, the installers and nuclear safety regulatory department related to the assembly integration scenario, the nuclear safety regulatory department, operators, surrounding residents, external environment, ocean, etc. related to the power operation scenario, to ensure the integrity of the stakeholders, and use the SysML module definition diagram to build a stakeholder model for each task scenario. The nuclear reactor stakeholders represented by the SysML module definition diagram are used as output.

[0093] Afterwards, a large number of stakeholders were obtained through task scenario identification. Not all stakeholders are directly related to nuclear reactors. Combined with the nuclear reactor model task, unnecessary stakeholders were eliminated.

[0094] After screening the stakeholders, the obtained stakeholders can be clustered and abstracted. Specifically, for stakeholders of the same type, high-level stakeholders are clustered and abstracted. An important requirement for clustering is the uniformity of quantity, and generally 7±2 high-level stakeholders are appropriate. For example, the high-level stakeholders of the cluster are regulators, and the low-level stakeholders are nuclear safety regulators, environmental protection departments, transportation regulators, etc.

[0095] In some embodiments, step S103 may further include: establishing a traceability relationship that reflects the association between the nuclear reactor life cycle and stakeholders, and using the SysML general matrix to construct a traceability matrix model of the nuclear reactor life cycle and stakeholders.

[0096] Specifically, in step S104, the nuclear reactor stakeholders represented by the SysML module definition diagram may be used as input, the stakeholder requirements may be defined using the stakeholder requirements template, and the stakeholder requirements model may be represented by a SysML requirement diagram as output.

[0097] When defining stakeholder requirements, the stakeholder requirements template can be used to define stakeholder requirements. The stakeholder requirements template can be: <stakeholder> (who) should be able to / need to <do / get> (what or how) at <life cycle stage> (when and / or where) with <expected performance level> (degree). Nuclear reactor stakeholder requirements can be shown in Table 1.

[0098] Table 1 Examples of stakeholder needs

[0099]

[0100] In some embodiments, step S104 may further include: using a SysML general matrix to construct a traceability matrix model between stakeholders and their requirements, where the traceability matrix model may reflect the associated traceability relationship between stakeholders and their requirements.

[0101] In some embodiments, in step S105, the task scenario model of the entire life cycle stage and the stakeholder demand model are used as inputs, and the dynamic interaction process between the stakeholders and the nuclear reactor is analyzed using a SysML sequence diagram.

[0102] In some embodiments, taking the power operation dynamic interaction scenario as an example, the dynamic interaction process between stakeholders and the nuclear reactor is analyzed, such as Figure 4 As shown, the operator 13 sends a power generation control instruction 31 to the nuclear reactor 1000; the power supply 15 can provide the nuclear reactor 1000 with an initial startup power supply 38; the ocean 17 can provide seawater 35 to the nuclear reactor 1000; the nuclear reactor 1000 receives the power generation control instruction 31, and outputs a power generation adjustment instruction 32 and a power generation instruction 33 to itself according to the power generation control instruction 31, so as to adjust the power generation and generate electricity, and then the nuclear reactor 1000 outputs electric energy 34 to the power grid 16, and discharges waste heat 36 to the ocean 17; the nuclear reactor 1000 can also send status monitoring feedback information 37 to the operator 13.

[0103] In step S106, the external interface of the nuclear reactor can be determined based on the dynamic interaction process between the stakeholders and the nuclear reactor, and the external interface model can be constructed using the SysML internal block diagram to determine the external interface of the nuclear reactor, such as the command interface, status interface, output power interface, waste heat discharge interface, water source interface, power supply interface, etc.

[0104] In some embodiments, taking the external interface of the power operation dynamic interaction scenario as an example, the schematic diagram of the external interface of the nuclear reactor is determined as follows: Figure 5 As shown, the operator 13 can send instructions to the nuclear reactor 1000 through the instruction interface 101; the nuclear reactor 1000 can send status information to the operator 13 through the status interface 102; the power supply 15 can provide power to the nuclear reactor 1000 through the power supply interface 104; the ocean 17 can provide water to the nuclear reactor 1000 through the water source interface 103; the nuclear reactor 1000 transfers heat to the ocean 17 through the waste heat discharge interface 106; the nuclear reactor 1000 outputs electrical energy to the power grid 16 through the output power interface 105.

[0105] In some embodiments, in step S107, after determining the external interface, the stakeholder requirement model represented by the SysML requirement diagram and the external interface model represented by the SysML internal block diagram are used as inputs to construct the model requirement model of the nuclear reactor using the SysML requirement diagram / requirement list. The model requirement model of the nuclear reactor can be constructed using the SysML requirement diagram / requirement list as output.

[0106] In some embodiments, when using the SysML requirement list to construct a model requirement model for a nuclear reactor, the requirements of stakeholders and external interfaces of the nuclear reactor can be sorted out to determine the model requirements of the nuclear reactor. Specifically, the requirements of stakeholders can be converted into the model requirements of the nuclear reactor. For example, if a user requires that the nuclear reactor can provide electrical energy xx (corresponding to the requirements of stakeholders), the requirement can be converted into the power generation of the nuclear reactor xx (corresponding to the model requirements of the nuclear reactor). For another example, the nuclear reactor needs to have an interface for discharging waste heat to the external environment.

[0107] In some embodiments, the model requirements of the sorted nuclear reactors can be classified with reference to the demand classification method, for example, they can be divided into functional requirements, performance requirements, interface requirements, etc. Among them, the functional requirements may include that the power generation power of the nuclear reactor is a certain power, the nuclear reactor can discharge residual heat, and the nuclear reactor can operate and control; the performance requirements may include the weight of the nuclear reactor, the size of the nuclear reactor, the reliability requirements of the nuclear reactor, and the life of the nuclear reactor; the interface requirements may include that the nuclear reactor must have an interface for discharging waste heat to the external environment, and the nuclear reactor must have an interface for power supply and distribution. Examples of model requirements for nuclear reactors are shown in Table 2.

[0108] Table 2 Examples of model requirements for nuclear reactors

[0109]

[0110] In some embodiments, step S107 may further include: using SysML general matrix to construct a traceability matrix model of nuclear reactor model requirements and stakeholder requirements; the traceability matrix model may reflect the associated traceability relationship between the reactor model requirements and stakeholder requirements.

[0111] The method provided according to the embodiment of the present application can finally output a dynamic interaction scenario model represented by a SysML sequence diagram and a model requirement of a nuclear reactor represented by a SysML requirement diagram / requirement list.

[0112] The demand analysis method of the embodiment of the present application establishes the associated traceability of task scenarios, stakeholders, stakeholder requirements, and model requirements throughout the entire life cycle, so that the model requirements of the nuclear reactor can be changed when user requirements or application scenarios change.

[0113] The process of analyzing the function of a reactor using a model provided in the embodiment of the present application is as follows: Figure 6 In some embodiments, step S2 may further include: steps S201 to S210.

[0114] S201. Determine the top-level functions of the nuclear reactor according to the model requirement model of the nuclear reactor, and construct the top-level functional model of the nuclear reactor using the SysML use case diagram / module definition diagram.

[0115] S202. Perform function flow analysis based on the top-level function model of the nuclear reactor, build a function flow model using SysML activity diagram, and decompose the top-level function into multiple sub-functions.

[0116] S203, performing sub-function analysis according to the sub-functions, building a sub-function analysis model using a SysML module definition diagram, and determining the missing sub-functions.

[0117] S204. Determine sub-function failure modes based on multiple sub-functions decomposed from the top-level functions and omitted sub-functions in combination with nuclear reactor engineering design experience.

[0118] S205. Determine the safety impact of each sub-function failure on the nuclear reactor based on the sub-function failure mode.

[0119] S206. Determine whether it is necessary to add a new sub-function to reduce the safety impact of the sub-function failure on the nuclear reactor based on the impact of the sub-function failure on the nuclear reactor.

[0120] S207. When it is determined that a new sub-function needs to be added, a sub-function failure response scenario model is constructed using a SysML activity diagram; and based on the function failure response scenario model, a newly added sub-function is determined.

[0121] S208. Determine all sub-function components of the nuclear reactor according to the function flow model, the sub-function analysis model and the sub-function failure response scenario model, and construct a model of all sub-function components of the nuclear reactor, i.e., a nuclear reactor function architecture model, using a SysML module definition diagram.

[0122] S209. Perform sub-function interaction scenario analysis based on the task scenario model corresponding to all life cycle stages of the nuclear reactor and all sub-function composition models of the nuclear reactor, and construct a sub-function interaction scenario model using SysML activity diagrams / internal block diagrams.

[0123] S210. According to the sub-function interaction scenario model, the interface information between each sub-function is identified, the interfaces between all sub-functions of the nuclear reactor are determined, and the interface models of all sub-functions are constructed using the SysML internal block diagram / state machine diagram.

[0124] In some embodiments, step S201 may further include: establishing an associative traceability relationship between the nuclear reactor model requirements and the top-level functions, and constructing a traceability matrix model of the nuclear reactor model requirements and the top-level functions using the SysML general matrix.

[0125] The embodiment of the present application uses the model requirements of the nuclear reactor as input, identifies the top-level functions of the nuclear reactor, and can clearly establish the correlation and traceability relationship between the demand analysis and the functional analysis.

[0126] The embodiments of the present application provide guidance for the implementation of nuclear reactor function modeling and analysis by establishing a model-based nuclear reactor function analysis method to support nuclear reactor demand function allocation tracing, function dynamic scenario demonstration, etc.

[0127] Specifically, in step S201, the model requirements of the nuclear reactor represented by the SysML requirement diagram / requirement list can be used as input to identify top-level functions, such as power generation function, safety function, operation control function, etc., and the top-level functional model of the nuclear reactor represented by the SysML use case diagram / module definition diagram can be used as output.

[0128] In some embodiments, in step S202, the top-level functional model of the nuclear reactor represented by the SysML use case diagram / module definition diagram is used as input, functional decomposition is performed in the form of functional flow, and the functional flow model constructed using the SysML activity diagram is used as output.

[0129] In some embodiments, step S202 may further include: decomposing according to the type of the object of action, such as decomposing the energy providing function into providing mechanical energy, providing thermal energy, providing electrical energy, etc.

[0130] In some embodiments, step S202 may further include: decomposing according to the change of the object of action or the process scenario, such as decomposing the power generation function of a nuclear reactor into heat generation, heat transfer, thermoelectric conversion, and waste heat discharge, such as Figure 7 As shown. The heat transfer function can be further decomposed into a series of material change processes such as the coolant providing power and the coolant flowing at low temperature.

[0131] In some embodiments, step S203 may also include: taking the function flow model as input, and conducting sub-function analysis based on the sub-functions obtained by the function flow analysis to determine the missing sub-functions. When determining the missing sub-functions, each sub-function may be analyzed from the four dimensions of "who, where, what, and to what extent", and the sub-functions are continuously optimized through this iterative process. The sub-function analysis model is constructed using the SysML module definition diagram as output.

[0132] Specifically, in step S204, the nuclear reactor function flow represented by the SysML activity diagram and the sub-function analysis model represented by the SysML module definition diagram can be used as inputs to determine the sub-function failure mode for the sub-function that has a safety impact on the nuclear reactor in combination with the nuclear reactor engineering design experience. In some embodiments, examples of the determined sub-function failure modes are shown in Table 3.

[0133] Table 3 Examples of sub-function failure modes

[0134]

[0135]

[0136] In step S205, for the failure modes of nuclear reactor sub-functions, the safety impact of each sub-function failure on the nuclear reactor is considered. For example, when the sub-function of providing power to the coolant fails, the coolant cannot flow and cannot take away the heat of the nuclear reactor, causing the temperature of the nuclear reactor to continue to rise, causing a relatively serious safety impact on the nuclear reactor.

[0137] In step S206, consider how to deal with different sub-function failure procedures, whether it is necessary to add new sub-functions to reduce the safety impact of functional failures on nuclear reactors, and determine the new sub-functions by analyzing the sub-function failure response scenarios. In step S207, use SysML activity diagrams to build sub-function failure response scenario models. The nuclear reactor sub-function failure response scenario model represented by the SysML activity diagram is used as the output.

[0138] Figure 8A schematic diagram of a scenario for coping with failure of the coolant power sub-function provided in accordance with an embodiment of the present application is shown. In view of the failure of the coolant power sub-function, the failure impact of the coolant power sub-function is determined. If the coolant power completely fails, resulting in loss of coolant flow, two new sub-functions, emergency shutdown and residual heat extraction, can be added; on the one hand, a new emergency shutdown sub-function needs to be added to prevent the nuclear reactor from continuing to generate heat; on the other hand, a new residual heat extraction sub-function needs to be added to extract the heat generated by the nuclear reactor and discharge it to the external environment to ensure the safety of the reactor. If the coolant power fails within a controllable range, a coolant power control sub-function can be added to ensure the safety of the reactor.

[0139] Specifically, in step S208, the functional flow model, sub-function analysis model and sub-function failure response scenario model are used as input to sort out all sub-function components of the nuclear reactor, establish a functional architecture, and use the SysML module definition diagram to construct a model of all sub-function components of the nuclear reactor as output.

[0140] In some embodiments, step S2 may further include: using a SysML general matrix to construct a traceability matrix model between sub-functions and top-level functions, where the traceability matrix model may reflect the associated traceability relationship between the sub-functions and the top-level functions.

[0141] Specifically, in step S209, the task scenario models corresponding to all life cycle stages represented by the SysML module definition diagram or use case diagram and the nuclear reactor all sub-function composition models represented by the SysML module definition diagram are used as inputs to carry out sub-function interaction analysis, determine the interaction between each sub-function, and use the SysML activity diagram / internal block diagram to construct a sub-function interaction scenario model as output. The correctness of the nuclear reactor function logic is ensured by simulating the sub-function interaction scenario model to verify that each task scenario that meets all life cycle stages of the nuclear reactor is met.

[0142] Take the sub-function interaction scenario in the power operation scenario as an example. Fig. 9As shown. The sub-function interaction scenario model may include heat generation nodes, heat transfer nodes, thermoelectric conversion nodes, and waste heat emission nodes. For example, under the heat generation node, nuclear fuel is used as input to generate nuclear reaction heat, and nuclear reaction heat and nuclear reactor radiation are output; under the heat transfer node, nuclear reaction heat is used as input, and sub-functions of nuclear reaction heat generation and nuclear reaction heat generation reception are interacted, and sub-functions of nuclear reaction heat generation reception, heat transfer, and heat output are interacted, and heat transfer energy is output; under the thermoelectric conversion node, heat transfer energy is used as input, and sub-functions of heat transfer and heat transfer reception are interacted, and sub-functions of heat transfer reception, heat energy conversion into mechanical energy, and mechanical energy conversion into electrical energy are interacted, and heat energy and electrical energy are output; under the waste heat emission node, the output heat energy of thermoelectric conversion is used as input, and sub-functions of heat transfer reception and heat reception are interacted, and sub-functions of heat reception and waste heat emission are interacted, and waste heat is output.

[0143] In step S210, according to the sub-function interaction scenario model, the interface information between each sub-function is identified, and the interfaces between all sub-functions of the nuclear reactor are determined. The interface model of all sub-functions is constructed using the SysML internal block diagram / state machine diagram.

[0144] Specifically, the sub-function interaction scenario model is constructed with SysML activity diagram / internal block diagram as input, and the interface information between each sub-function is identified. In some embodiments, the interface information between sub-functions may include: information flow between sub-functions such as control and monitoring, material flow between sub-functions such as nuclear fuel, coolant, working fluid, etc.; energy flow between sub-functions such as electrical energy and thermal energy, and all sub-function interfaces of the nuclear reactor are defined, such as nuclear fuel interface, nuclear reaction radiation interface, nuclear reaction heat interface, thermal energy interface, mechanical energy interface, electrical energy interface, waste heat interface, etc. The SysML internal block diagram / state machine diagram is used to construct the interface model of all sub-functions as output.

[0145] In some embodiments, step S3 may also include: step S301 - step S301.

[0146] S301. Determine the function-logic allocation of the nuclear reactor according to all sub-functions of the nuclear reactor, and construct a function-logic allocation matrix model using the SysML general matrix.

[0147] S302. According to the function-logic allocation matrix model, all sub-functions of the nuclear reactor are allocated functional combinations to determine the system equipment composition of the nuclear reactor, and a system equipment composition model of the nuclear reactor is constructed using a SysML module definition diagram.

[0148] S303. Perform logic scenario interaction analysis based on all sub-function interface models and system equipment composition models, analyze the interaction between sub-functions under the nuclear reactor system equipment, and use SysML activity diagrams / internal block diagrams to build a logic interaction scenario model.

[0149] S304: Execute a logic interaction scenario model simulation so that the system equipment composition of the nuclear reactor can meet the mission scenarios of all life cycle stages of the nuclear reactor.

[0150] S305. Perform interface analysis according to the logical interaction scenario model, determine the internal and external interfaces of the nuclear reactor system equipment, and use the SysML internal block diagram / general matrix to construct the internal and external interface models of the nuclear reactor system equipment.

[0151] S306. According to the logical interaction scenario model, perform key indicator correlation analysis, determine the key indicator correlation of the nuclear reactor as a whole, system, and equipment, and use the SysML parameter diagram to build a key indicator correlation model.

[0152] S307. Decompose the indicators according to the key indicator correlation model to determine the indicator parameters of the nuclear reactor system equipment.

[0153] Specifically, in step S301, all sub-functions of the nuclear reactor can be used as input, and all sub-functions can be combined and allocated to the logical structure implementation, corresponding to the nuclear reactor, and the function combination can be allocated to the equipment implementation. The equipment composition is determined by constructing a function-logical structure allocation matrix, and the function-logic allocation matrix model is constructed using the SysML general matrix.

[0154] In some embodiments, in the function-logic allocation matrix, the columns represent the logical structure and the rows represent the functions. An example of the function-logic allocation matrix is ​​shown in Table 4. When performing the function-logic allocation, the nuclear reactor sub-function can be allocated to the fuel assembly, the coolant power supply sub-function can be allocated to the pump, the low-temperature coolant flow and the high-temperature coolant flow can be allocated to the coolant pipeline, the coolant and the working fluid side heat exchange sub-function can be allocated to the heat exchanger, the low-temperature working fluid flow and the high-temperature working fluid flow sub-function can be allocated to the working fluid pipeline, and the working fluid working sub-function can be allocated to the steam turbine, etc., to determine the equipment composition of the nuclear reactor.

[0155] Table 4 Example of function-logic allocation matrix

[0156]

[0157]

[0158] In some embodiments, step S302 may also include combining all the equipment components of the nuclear reactor into a nuclear reactor system in combination with the characteristics of the nuclear reactor system composition, and using a SysML module definition diagram to construct a nuclear reactor system equipment composition model. The nuclear reactor system equipment composition represented by the SysML module definition diagram is output.

[0159] Fig.11 It is a schematic diagram of the nuclear reactor system equipment composition model provided according to the embodiment of the present application. According to the composition of the nuclear reactor equipment and in combination with the composition characteristics of the nuclear reactor system, the equipment is combined into a plurality of nuclear reactor systems. For example, the main pump 210, the heat exchanger 220 and the impurity removal device 230 are combined into a primary loop system 200. Other equipment is similarly combined, and the nuclear reactor 1000 is divided into a nuclear reactor core system 100, a primary loop system 200, a power conversion system 300 and a waste heat discharge system 400.

[0160] Specifically, in step S303, the SysML internal block diagram / state machine diagram is used to construct the interface model of all sub-functions and the nuclear reactor system equipment composition model represented by the SysML module definition diagram as input, and a logical interaction scenario analysis is performed to analyze the interaction between the sub-functions of the nuclear reactor system equipment, and a logical interaction scenario model is established using the SysML activity diagram / internal block diagram. In step S305, by executing the logical interaction scenario model simulation, it is verified that the composition of the nuclear reactor system equipment meets the task scenarios of all life cycle stages of the nuclear reactor. The logical interaction scenario model is constructed using the SysML activity diagram / internal block diagram as output.

[0161] Fig.12 is a schematic diagram of a nuclear reactor logic interaction scenario model provided according to an embodiment of the present application. Fig.12 In some embodiments, the nuclear reactor is composed of a nuclear reactor core system, a primary loop system, a power conversion system, and a waste heat discharge system. The reactor core system has a nuclear reaction heat generation sub-function, which interacts with the nuclear reactor heat generation receiving sub-function of the primary loop system; the nuclear reactor heat generation receiving sub-function, heat transfer sub-function and other sub-functions of the primary loop system interact internally, and the heat transfer sub-function of the primary loop system interacts with the heat transfer receiving sub-function under the power conversion system; the heat transfer receiving sub-function, heat energy conversion to mechanical energy sub-function, and mechanical energy conversion to electrical energy sub-function of the power conversion system interact internally, and the heat transfer receiving sub-function of the power conversion system interacts with the heat receiving sub-function of the waste heat discharge system; the heat receiving sub-function, waste heat discharge sub-function and other sub-functions of the waste heat discharge system interact internally. Through logical interaction scenario analysis, the functional interaction between nuclear reactor system equipment can be determined.

[0162] Specifically, in step S305, the logical interaction scenario model represented by the SysML activity diagram / internal block diagram is used as input, and based on the nuclear reactor logical interaction scenario model, the information flow, material flow, energy flow, etc. between various system devices are identified, the internal and external interfaces of the nuclear reactor system equipment are determined, and the internal and external interface models of the nuclear reactor system equipment are constructed using the SysML internal block diagram / general matrix. The internal and external interface models of the nuclear reactor system equipment represented by the SysML internal block diagram / general matrix are used as output.

[0163] See also Fig.13 Through interface analysis, it can be known that the reactor core system 100 has a nuclear fuel interface and a nuclear reaction radiation interface with the outside, there are internal interfaces such as a thermal energy interface and a coolant interface between the reactor core system 100 and the primary loop system 200, there are internal interfaces such as a thermal energy interface between the primary loop system 200 and the power conversion system 300, there are internal interfaces such as a thermal energy interface and a mechanical force interface between the power conversion system 300 and the waste heat discharge system 400, there are internal interfaces such as a thermal energy interface and a mechanical force interface between the power conversion system 300 and the outside, there is an electric energy interface between the power conversion system 300 and the outside, and there is a waste heat interface between the waste heat discharge system 400 and the outside.

[0164] In some embodiments, in step S306, key indicators may include indicators proposed by stakeholders, indicators obtained from functional analysis, indicators obtained from sub-function failure analysis, etc., such as electric power indicators, temperature indicators, pressure indicators, flow indicators, etc. In some embodiments, key indicators may be allocated to nuclear reactor system equipment.

[0165] In some embodiments, in step S307, when the indicator decomposition is performed according to the key indicator association relationship model, the indicator decomposition can be performed through a coupling calculation formula or professional calculation and analysis software to determine the indicator parameters of the nuclear reactor system equipment.

[0166] In some embodiments, step S41 may also include: selecting equipment according to the functions, interfaces, and system index parameters to be realized by the system equipment of the nuclear reactor, and determining a variety of alternative design solutions in combination with physical and thermal engineering analysis.

[0167] In some embodiments, in step S42, for a variety of alternative design schemes, a simulation analysis involving multidisciplinary collaboration may be performed to weigh the various alternative design schemes to determine the optimal design scheme for the nuclear reactor.

[0168] The MBSE-based nuclear reactor architecture design method of this application can provide ideas for conducting model-based requirements, functions, logic and physical analysis, and can support the overall design process such as nuclear reactor design requirement definition, system equipment interface division, requirement indicator correlation tracing, and scheme trade-off demonstration.

[0169] Regarding the embodiments of the present application, it should also be noted that, in the absence of conflict, the embodiments of the present application and the features therein can be combined with each other to obtain new embodiments.

[0170] The above are only specific implementation methods of the present application, but the protection scope of the present application is not limited thereto. The protection scope of the present application shall be based on the protection scope of the claims.

Claims

1. A nuclear reactor architecture design method based on MBSE, characterized in that: include: S1. According to the power supply and heating capacity requirements of the nuclear reactor, a demand analysis is performed on the nuclear reactor to determine the model requirements of the nuclear reactor; S2. According to the model requirements of the nuclear reactor, perform a functional analysis on the nuclear reactor to determine all sub-function components of the nuclear reactor and interfaces between the sub-functions; S3, performing a logical analysis on the nuclear reactor according to all sub-functions of the nuclear reactor and interfaces between the sub-functions, and determining the system equipment composition of the nuclear reactor, the internal and external interfaces of the system equipment, and the index parameters of the system equipment; S4. Determine the design scheme of the nuclear reactor according to the system equipment composition of the nuclear reactor, the internal and external interfaces of the system equipment, and the index parameters of the system equipment.

2. The method according to claim 1, characterized in that: The S1 step includes: S11. Determine the mission scenarios of all life cycle stages of the nuclear reactor according to the power supply and heating capacity requirements of the nuclear reactor; S12, determining the stakeholders of each task scenario corresponding to each life cycle stage of the nuclear reactor according to the task scenarios of all life cycle stages of the nuclear reactor; S13, determining stakeholder needs of the nuclear reactor according to stakeholders of each task scenario corresponding to each life cycle stage of the nuclear reactor; S14. Perform dynamic interactive scenario analysis based on the mission scenarios of all life cycle stages of the nuclear reactor and the needs of stakeholders of the nuclear reactor to determine the model requirements of the nuclear reactor.

3. The method according to claim 2, characterized in that The step S11 includes: S111, determining the entire life cycle stages of the nuclear reactor according to the power supply and heat supply capacity requirements of the nuclear reactor; S112. Determine the mission scenarios of all life cycle stages of the nuclear reactor according to all life cycle stages of the nuclear reactor.

4. The method according to claim 1, characterized in that: The S2 step includes: S21. Determine the top-level function of the nuclear reactor according to the requirements of the nuclear reactor model; S22. Perform function flow analysis on each top-level function and decompose the top-level function into multiple sub-functions; S23, for the multiple sub-functions decomposed from the top-level functions, perform sub-function failure analysis and identify newly added sub-functions; S24, determining all sub-function components of the nuclear reactor according to the functional flow analysis and the sub-function failure analysis; S25. According to the task scenarios and all sub-functions of all life cycle stages of the nuclear reactor, sub-function interaction scenario analysis is performed to determine the interfaces between all sub-functions of the nuclear reactor.

5. The method according to claim 4, characterized in that The step S23 includes: Determine the failure modes of the sub-functions decomposed from the top-level functions; Determining the safety impact of each sub-function failure on the nuclear reactor according to the sub-function failure mode; According to the safety impact of the sub-function failure on the nuclear reactor, determining whether it is necessary to add a new sub-function to mitigate the safety impact of the sub-function failure on the nuclear reactor; When it is determined that a new sub-function needs to be added, construct a sub-function failure response scenario; Determine the newly added sub-function based on the sub-function failure response scenario.

6. The method according to claim 1, characterized in that The S3 step includes: S31, combining and allocating all sub-functions of the nuclear reactor to determine the system equipment composition of the nuclear reactor; S32, performing a logic interaction scenario analysis according to the interfaces between all sub-functions of the nuclear reactor and the system equipment composition of the nuclear reactor, so that the system equipment composition of the nuclear reactor can meet the task scenarios of all life cycle stages of the nuclear reactor; S33, performing interface analysis on the system equipment of the nuclear reactor according to the logic interaction scenario analysis, and determining the internal and external interfaces of the system equipment of the nuclear reactor; S34, analyzing the key indicator correlation relationship of the nuclear reactor according to the logic interaction scenario analysis, and sorting out the key indicator correlation relationship of the nuclear reactor as a whole, system, and equipment; S35. Decompose the indicators according to the key indicator association relationship to determine the indicator parameters of the nuclear reactor system equipment.

7. The method according to claim 1, characterized in that The S4 step includes: S41, selecting equipment according to the functions to be realized by the system equipment of the nuclear reactor, the interfaces, and the index parameters, and determining a plurality of alternative design solutions; S42. Weighing the alternative design schemes according to the plurality of alternative design schemes to determine the optimal design scheme for the nuclear reactor.

8. The method according to claim 1, characterized in that The S1 step further includes: Constructing a nuclear reactor life cycle model using a SysML state machine diagram, wherein the nuclear reactor life cycle model uses a SysML state machine diagram to represent all life cycle stages of the nuclear reactor; According to the nuclear reactor life cycle model, determine the task scenarios of all life cycle stages of the nuclear reactor, and construct the task scenario model of the nuclear reactor using SysML module definition diagram / use case diagram; Determine the stakeholders of the task scenario model of the nuclear reactor corresponding to each of the life cycle stages according to the task scenario model of the nuclear reactor, and construct the stakeholder model of each task scenario of the nuclear reactor corresponding to each of the life cycle stages using a SysML module definition diagram; Determine stakeholder requirements based on the stakeholder model of the nuclear reactor corresponding to the task scenario of each life cycle stage, and construct the stakeholder requirement model using SysML requirement diagram; According to the task scenario model of the nuclear reactor, determining the dynamic interaction process between the stakeholder and the nuclear reactor, and constructing the dynamic interaction scenario model using a SysML sequence diagram; Performing dynamic interaction scenario analysis according to the dynamic interaction scenario model, determining the external interface of the nuclear reactor, and constructing the external interface model using a SysML internal block diagram; According to the stakeholder requirement model and the external interface model, the model requirements of the nuclear reactor are determined, and the model requirement model of the nuclear reactor is constructed using a SysML requirement diagram / requirement list.

9. The method according to claim 8, characterized in that The S2 step further includes: Determine the top-level functions of the nuclear reactor according to the model requirement model of the nuclear reactor, and construct the top-level function model of the nuclear reactor using SysML use case diagram / module definition diagram; According to the top-level functional model of the nuclear reactor, a functional flow analysis is performed, a functional flow model is constructed using a SysML activity diagram, and the top-level function is decomposed into a plurality of sub-functions; According to the sub-functions, sub-function analysis is performed, and a sub-function analysis model is constructed using a SysML module definition diagram to determine the missing sub-functions; Determine sub-function failure modes according to the multiple sub-functions decomposed from the top-level function and the omitted sub-functions in combination with nuclear reactor engineering design experience; Determining the safety impact of each sub-function failure on the nuclear reactor according to the sub-function failure mode; According to the safety impact of the sub-function failure on the nuclear reactor, determining whether it is necessary to add a new sub-function to mitigate the safety impact of the sub-function failure on the nuclear reactor; When it is determined that a new sub-function needs to be added, a SysML activity diagram is used to build a sub-function failure response scenario model; Determine a newly added sub-function based on the sub-function failure response scenario model; Determine all sub-function components of the nuclear reactor according to the functional flow model, the sub-function analysis model and the sub-function failure response scenario model, and construct a model of all sub-function components of the nuclear reactor using a SysML module definition diagram; According to the task scenario model of all life cycle stages of the nuclear reactor and the model of all sub-function composition of the nuclear reactor, sub-function interaction scenario analysis is performed, and a sub-function interaction scenario model is constructed using SysML activity diagram / internal block diagram; According to the sub-function interaction scenario model, the interface information between the sub-functions is identified, the interfaces between all the sub-functions of the nuclear reactor are determined, and the interface models of all the sub-functions are constructed using SysML internal block diagrams / state machine diagrams.

10. The method according to claim 9, characterized in that The S3 step further includes: Determine the function-logic allocation of the nuclear reactor according to all sub-functions of the nuclear reactor, and construct a function-logic allocation matrix model using SysML general matrix; According to the function-logic allocation matrix model, all sub-functions of the nuclear reactor are allocated functional combinations to determine the system equipment composition of the nuclear reactor, and a system equipment composition model of the nuclear reactor is constructed using a SysML module definition diagram; According to the interface models of all sub-functions and the system equipment composition model, a logical scenario interaction analysis is performed to analyze the interaction between the sub-functions under the nuclear reactor system equipment, and a logical interaction scenario model is constructed using SysML activity diagrams / internal block diagrams; By executing a logic interaction scenario model simulation, the system equipment composition of the nuclear reactor satisfies the mission scenarios of all life cycle stages of the nuclear reactor; According to the logical interaction scenario model, interface analysis is performed to determine the internal and external interfaces of the nuclear reactor system equipment, and the internal and external interface models of the nuclear reactor system equipment are constructed using SysML internal block diagrams / general matrices; According to the logical interaction scenario model, a key indicator correlation relationship analysis is performed to determine the key indicator correlation relationship of the nuclear reactor as a whole, the system, and the equipment, and a key indicator correlation relationship model is constructed using a SysML parameter diagram; According to the key indicator association relationship model, indicator decomposition is performed to determine the indicator parameters of the nuclear reactor system equipment.

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