A test verification system and verification method for a nuclear energy system

Abstract

The application provides a test verification system and method of a nuclear energy system, and belongs to the technical field of nuclear energy tests. First, hierarchical decomposition is performed; items in the same level of the nuclear energy system are arranged according to structural feature complexity; then, physical phenomenon identification is performed; based on the state of the nuclear energy system, the physical phenomenon or operation failure mechanism of each item is identified according to the function and operation mode of the item, and a key item dataset is constructed; then, maturity analysis is performed; maturity analysis is performed from three angles of a carrier form of the item, an environment condition of verification and a fidelity of a verification test; finally, verification requirement analysis is performed; items with a maturity lower than a specific level are formed into a set of items to be verified, target and boundary conditions of a verification test of each item are determined, a plurality of principles of verification test merging and optimization are defined based on the structural characteristics of the item level and the root item level, and finally, a verification test matrix is formed.

Description

Technical Field

[0001] This invention belongs to the field of nuclear energy testing technology, specifically relating to a testing and verification system and method for a nuclear energy system. Background Technology

[0002] The design and development of nuclear energy systems can generally be divided into the design phase and the design verification phase. During the design process, in order to improve economy and safety, designers often optimize or innovate the design at the levels of materials, parts, components, equipment, and systems, either through partial improvements or overall changes. In the design verification phase, one or more of the following methods are usually used: operational experience feedback, experimental verification, and computational analysis, to confirm that these new designs can operate normally as expected or fulfill their design functions.

[0003] In the practice of nuclear energy applications around the world, in order to ensure nuclear safety and protect workers, the public, and the environment from the harm of excessive radiation, nuclear energy regulatory authorities have set clear review requirements for design changes, optimizations, and innovations of nuclear energy systems. For example, my country's "Safety Regulations for Nuclear Power Plant Design (HAF102-2016)" clearly stipulates that "when an unverified design or facility is introduced, or when there is a deviation from existing engineering practice, its safety must be demonstrated through appropriate supporting research programs, performance tests based on specific acceptance criteria, or verification through operational experience gained in other relevant applications. New designs, facilities, or practices must undergo sufficient testing before being put into use and be monitored during use to verify that the expected effects have been achieved."

[0004] In summary, as an important verification method for nuclear energy system design innovation, experimental verification is directly related to the final safety performance of the nuclear energy system and is an indispensable key link in the safety review and engineering application of nuclear energy system design. Due to the complexity of nuclear energy systems, the design verification process often requires conducting various types of tests with multiple objectives. The combination of these verification tests is generally called a verification test matrix. Rationally determining the test requirements, forming a verification test matrix, clarifying the type, objectives, and research content of each verification test, designing an experimental verification system consisting of one or more test devices, and completing the tests are among the key issues that must be addressed in the design verification phase.

[0005] Currently, in the research and development of innovative nuclear power technologies, new research reactors, and innovative nuclear energy systems, the design of verification test matrices and test verification systems is mainly determined on a case-by-case basis through expert judgment. The complexity of nuclear energy system design and the engineering experience of experts will have a significant impact on the test matrix, thereby affecting the sufficiency and rationality of the design verification process.

[0006] To address this issue, this invention proposes a design verification method and a corresponding experimental verification system for nuclear energy systems, providing technical support for designers to develop high-quality design verification test matrices and systematically complete design verification work. Summary of the Invention

[0007] To address the aforementioned issues, this invention proposes a test verification system and method for nuclear energy systems based on the hierarchical analysis and technology maturity theory. This system is used to determine the test verification requirements and design verification test matrix during the design verification of nuclear energy systems, providing technical support for designers to systematically and efficiently complete design verification work.

[0008] This invention is achieved through the following technical solution: A nuclear energy system: The nuclear energy system includes the reactor body, reactor coolant system, dedicated safety system, energy conversion system, and process auxiliary system; The reactor body includes a pressure vessel and its interfaces; the pressure vessel is used to withstand the high temperature, high pressure and high radiation conditions generated during the nuclear reaction process, and to ensure the correct and safe operation of the nuclear fuel; The reactor coolant system includes a reactor pressure vessel, a primary side of a steam generator, a main pump, and a pressurizer. It is used to control and regulate the heat generated by the nuclear reaction process in the reactor and to transfer it. The primary side of the steam generator converts the heat from the reactor coolant system into steam, which is connected to the reactor pressure vessel via pipes. The main pump is used to regulate and maintain the flow rate of the reactor coolant system. The pressurizer is used to regulate and maintain the pressure of the reactor coolant system. The dedicated safety system includes an emergency core cooling system and containment-related systems. The emergency core cooling system includes a makeup water tank, a safety injection tank, a safety injection pump, and a residual heat removal heat exchanger, etc., used to inject coolant or other specific media in the event of an accident or emergency to cool the nuclear reactor core and ensure the safety of the nuclear reactor. The containment-related systems include the containment shell, water tanks, pumps, and heat exchangers, used to provide radiation shielding and physical isolation for the nuclear reactor, and to maintain pressure balance and gas circulation inside the containment. The energy conversion system includes a secondary side of a steam generator and a steam turbine unit, used to transfer steam from the primary side of the steam generator to other systems for energy conversion and power generation; The process support system includes an equipment cooling system, a heater, and a lubricating oil system, which provide auxiliary support functions for the start-up, operation, and shutdown of the nuclear energy system. The pressure vessel of the reactor body includes fuel assemblies, in-core components, and corresponding piping interfaces, used to withstand the high temperature, high pressure, and high radiation conditions generated during the nuclear reaction, and to ensure the correct and safe operation of the nuclear fuel; the fuel assemblies consist of nuclear fuel rods, grids, etc., used to generate nuclear reactions and release heat; the in-core components are all other components within the pressure vessel except for the fuel assemblies and their related components, including the upper core support components, the lower core support components, and the core measurement support structure; the primary side of the steam generator includes heat exchange tube bundles; The steam generator is a heat exchange device in a nuclear energy system. It converts the heat from the primary side of the steam generator in the reactor coolant system into high-temperature, high-pressure steam on the secondary side of the steam generator, which is then transferred to the turbine unit to generate power or transferred to the demand side to realize the utilization of thermal energy. The secondary side of the steam generator includes a feedwater pump, which draws liquid condensate from the turbine unit and increases its pressure, then sends it to the inlet of the steam generator. The turbine unit includes blades for realizing the energy conversion of the nuclear energy system, converting steam energy into mechanical energy; when high-temperature, high-pressure steam acts on the blades, the blades will rotate and drive the turbine shaft, thereby driving the generator to produce electrical energy; By transferring high-temperature, high-pressure steam from the secondary side of the steam generator to the turbine unit, the nuclear energy system achieves the conversion of thermal energy into mechanical energy and then into electrical energy, ultimately generating usable electricity. The cooling system includes a cooling pump, the heater includes a heating rod, and the lubricating oil system includes a lubricating oil pump.

[0009] A test and verification system for nuclear energy systems: The experimental verification system consists of one or more experimental devices with specific simulation functions, which can be used to reproduce the main thermal-hydraulic phenomena in the nuclear energy system and verify the operating performance and safety characteristics of the nuclear energy system.

[0010] The test apparatus includes a test body, a test loop system, a measurement and control system, and a test auxiliary system. It is used to simulate one or more subsystems and one or more devices in a nuclear energy system, such as the reactor body, main coolant system, dedicated safety system, and energy conversion system, and can verify its design operating performance under specific boundary conditions.

[0011] The test subject is a system or device with specific simulation functions and specific geometric structures. The specific object and simulation requirements are determined by the verification method. The design parameters are obtained based on the similarity principle. The simulation scope includes the entire nuclear energy system, one or more subsystems of the nuclear energy system, and one or more devices in the nuclear energy system.

[0012] The test loop system includes a circulating pump, pipelines, and valves, forming multiple circulating flow loops with a specific spatial arrangement. It is used to provide the test body with a flowing working medium and external environment, and to regulate parameters such as flow rate, temperature, and pressure.

[0013] The measurement and control system includes a test parameter measurement system and a test device control system. The test parameter measurement system includes test parameter measuring instruments, test loop status indicators and protection instruments, and a corresponding data conversion and storage system, used to measure and store test target parameters, while monitoring and ensuring the normal operation of the test device. The test device control system is used to realize the power supply, start and stop of the test device, and to provide control functions for parameters such as flow rate, pressure and temperature of the device loop.

[0014] A method for verifying a nuclear energy system: The verification method specifically includes the following steps: Step 1, Hierarchical decomposition; The various subsystems, components, and equipment that constitute the nuclear energy system and their combinations are called items. The nuclear energy system is decomposed at different levels to form items at different levels; Items within the same level of the nuclear energy system are arranged in order of structural feature complexity, and items that have functional coupling relationships are arranged close together. Step 2, Physical Phenomenon Identification; Based on the state of the nuclear energy system, and according to the functions and operating modes of the items, identify the physical phenomena or operational failure mechanisms of each item, and construct a set of key items; Step 3, Maturity Analysis: The maturity of the key itemset is analyzed from three perspectives: carrier form, verification environment conditions, and the fidelity of the verification test, to determine the maturity level of each item. Step 4, verify the requirements analysis; items with maturity levels lower than a certain level in Step 3 constitute the set of items to be verified, determine the objectives and boundary conditions of the verification tests for each item, and define several principles for merging and optimizing verification tests based on the structural characteristics of the level to which the items to be verified belong and the root item level, forming a verification test matrix.

[0015] Further, in step 1, Nuclear energy systems are broken down into multiple levels, including overall system design, subsystem design, equipment design, component design, and part design. These levels of study are denoted as follows: i , i =1, 2, 3, 4, 5, ..., n, where n is a positive integer; for any selected level, the main items contained therein are numbered and denoted as . j , j =1, 2, 3, 4, 5, ..., n, where n is a positive integer; therefore, any subsystem, component, and device in a nuclear energy system can be represented as Q i，j ,sequence[i, j This indicates the position of the item within the hierarchical structure of the nuclear energy system; it decomposes the nuclear energy system into components with... i Hierarchical structure, each level containing j A tree structure diagram of the individual items.

[0016] Furthermore, in step 2, Based on the state and tree structure diagram of the nuclear energy system, identify the physical phenomena or operational failure mechanisms occurring within each item, denoted as... k Item; combined with the importance index, the degree of importance of each physical phenomenon relative to the importance index is obtained. I i，j，k This allows us to identify key items and their hierarchical structure that exhibit physical phenomena or operational failure mechanisms, thus forming a set of key items. The importance index is related to the operating mode or system status of the nuclear energy system. Under operating mode, the operating specifications serve as the importance index; while under accident status, the acceptance criteria for different accidents serve as the importance index.

[0017] Furthermore, in step 3, The degree to which an item can operate safely and reliably is called design maturity. R The design maturity of the items is marked by a score of 1-9. Conduct design maturity analysis on the key itemset, starting from the first i Starting from level 1, traverse the entire hierarchy tree from bottom to top, identifying each key item and its root item. Q i，j Design maturity R i，j ; Maturity analysis is conducted from three perspectives: the carrier form of the item, the environmental conditions for verification, and the fidelity of the verification test. Maturity analysis based on carrier form: Considering the impact of the carrier form of the item on the verification work, the higher the maturity, the closer it is to the carrier form in actual application. Maturity analysis is performed on the validation environment conditions: This involves the environmental conditions created when validating items, which simulate actual working conditions, including temperature, pressure, flow rate, and radiation environment. Maturity analysis based on the fidelity of the validation test: The fidelity of the validation test refers to the degree of similarity between the validation test and the actual working situation.

[0018] Furthermore, in step 4, First, construct a set of items to be verified, placing items in the nuclear energy system tree structure diagram with a maturity level below a specific level N, i.e. R i，j Items less than N constitute the set of items to be verified. Then, based on the simulation capabilities and accuracy of the analysis tools, the set of items to be verified is divided into a simulation analysis subset and an experimental verification subset; the simulation analysis subset is verified using simulation analysis tools; the experimental verification subset requires experimental verification, which is the verification content that the experimental matrix needs to cover; based on the results of maturity analysis and technical factor assessment for each item, the objectives and boundary conditions of the verification experiments for each item in the experimental verification subset are determined. Then, define the principles for merging and optimizing verification experiments: Based on the structural characteristics of the item level to which the innovative design belongs and its root item level, define several principles for merging and optimizing verification experiments; Then, a verification test matrix is ​​formed, which defines the objectives, test content, boundary conditions, required resources and equipment, and corresponding specific requirements for each verification test.

[0019] Finally, based on the principle of similarity, one or more test devices that meet the requirements of the verification test matrix are designed to form a test verification system for the nuclear energy system. An electronic device includes a memory and a processor, the memory storing a computer program, the processor executing the computer program to implement the steps of the above method.

[0020] A computer-readable storage medium for storing computer instructions that, when executed by a processor, implement the steps of the above-described method.

[0021] Beneficial effects of the invention Based on the Analytic Hierarchy Process (AHP) and Technology Maturity Theory (TMT), this invention provides a verification method and experimental verification system for the design verification phase of nuclear energy system R&D. It establishes a standardized method and analysis process for determining verification test matrices that is traceable, quantifiable, and highly versatile. This not only improves the determination of verification test matrices in nuclear energy system R&D but also optimizes the design of nuclear energy system experimental verification systems. It can further enhance the completeness, sufficiency, and rationality of the nuclear energy system design verification process, and features high versatility, high standardization, quantifiability, and traceability.

[0022] 1) The verification method described in this invention has a highly standardized process, is applicable to various nuclear energy systems, and has excellent versatility.

[0023] 2) In this invention, importance is determined by the specific design and acceptance criteria of the nuclear energy system, supplemented by expert judgment; the design maturity of an item is determined by quantifiable indicators with practical engineering significance, based on the identification of the importance of physical phenomena within the item, and can also be supplemented by expert judgment; the test matrix is ​​determined based on the quantified design maturity. Throughout the entire process, key decision-making is based on quantifiable indicators, possessing good traceability and technical logic, effectively avoiding the cognitive limitations and arbitrariness of expert experience-based judgment methods.

[0024] 3) The experimental verification system proposed in this invention is standardized and traceable. Once formed and solidified, it can be easily referenced and used for the design verification of similar nuclear energy systems. In the long run, it can simplify the design demonstration process and improve efficiency. In addition, the experimental verification system and its design method can also incorporate the research results and engineering experience of experts, record and solidify them in the demonstration documents, which can improve the utilization efficiency of these research results and engineering experience.

[0025] This invention is the first to systematically apply the Analytic Hierarchy Process (AHP) theory and the Technology Maturity Scale (TMS) theory to the field of nuclear energy system design verification, and develops a set of verification methods and experimental verification systems that are highly applicable to engineering research and development, forming a complete and standardized software and hardware system, analysis methods and processes. Attached Figure Description

[0026] Figure 1 This is a flowchart illustrating the verification test system and verification method for the nuclear energy system of the present invention. Figure 2 This is an example diagram of a hierarchical tree of a nuclear energy system structure. Figure 3 An example diagram to verify the experimental matrix analysis process. Detailed Implementation

[0027] The technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.

[0028] Combination Figures 1 to 3 .

[0029] A nuclear energy system: The nuclear energy system includes multiple subsystems such as the reactor body, reactor coolant system, dedicated safety system, energy conversion system, and process auxiliary system. According to the design functions such as production operation, safety protection, measurement and control, and process auxiliary, the nuclear energy system can be divided into four subsystems. Further, according to the hierarchical structure of system, subsystem, component, and equipment, the hierarchical structure (hierarchical tree) of the nuclear energy system can be obtained. The subsystems, components, and equipment that constitute the system and their combinations are all called items.

[0030] The reactor body includes a pressure vessel and its interfaces; the pressure vessel is used to withstand the high temperature, high pressure and high radiation conditions generated during the nuclear reaction process, and to ensure the correct and safe operation of the nuclear fuel; The reactor coolant system includes a reactor pressure vessel, a primary steam generator (the side that is in direct contact with the main coolant circulation of the nuclear reactor), a main pump, and a pressurizer, which are used to control and regulate the heat generated by the nuclear reaction process in the reactor and transfer it. The reactor pressure vessel includes fuel assemblies, in-core components, and corresponding piping interfaces. It withstands the high temperature, high pressure, and high radiation conditions generated during the nuclear reaction and ensures the correct and safe operation of the nuclear fuel. The fuel assemblies consist of fuel rods, positioning components, and support components. The fuel rods contain fuel pellets made of materials such as uranium or plutonium, used to generate nuclear fission reactions and release heat. The in-core components are all other components within the pressure vessel besides the fuel assemblies and their related components. These include upper core support components, lower core support components, and core measurement support structures. The design and arrangement of the in-core components must consider neutron economy, flow-induced vibration, and cooling conditions. The steam generator is used to convert the heat of the reactor coolant system into steam, and is connected to the reactor pressure vessel through pipelines. It mainly consists of a steam generator shell and a heat exchange tube bundle. The main pump is used to regulate and maintain the flow rate of the reactor coolant system. The pressurizer is used to regulate and maintain the pressure of the reactor coolant system. The dedicated safety system includes an emergency core cooling system and containment-related systems. The emergency core cooling system includes a makeup water tank, a safety injection tank, a safety injection pump, and a residual heat removal heat exchanger, etc., used to inject coolant or other specific media into the core in the event of an accident or emergency to cool the nuclear reactor core and ensure the safety of the nuclear reactor. The containment-related systems include the containment shell, water tanks, pumps, and heat exchangers, used to provide radiation shielding and physical isolation for the reactor, and to maintain pressure balance and gas circulation inside the containment. The energy conversion system includes a secondary side of a steam generator and a steam turbine unit, used to transfer steam from the primary side of the steam generator to other systems for energy conversion and power generation; The steam generator is a heat exchange device in a nuclear energy system. It converts heat from the reactor coolant system into high-temperature, high-pressure steam on the secondary side of the steam generator, which is then transferred to the turbine unit to generate power or to the demand side to realize the utilization of thermal energy. The secondary side of the steam generator includes a feedwater pump, which draws liquid condensate from the turbine unit and increases its pressure, then sends it to the inlet of the steam generator. The turbine unit includes a turbine casing, a main shaft, and blades, which are used to realize the energy conversion of the nuclear energy system, converting steam energy into mechanical energy; when high-temperature, high-pressure steam acts on the blades, the blades will rotate and drive the turbine shaft, thereby driving the generator to produce electrical energy; By transferring high-temperature, high-pressure steam from the secondary side of the steam generator to the turbine unit, the nuclear energy system achieves the conversion of thermal energy into mechanical energy and then into electrical energy, ultimately generating usable electricity. The process support system includes an equipment cooling system, a heater, and a lubricating oil system, which provide auxiliary support functions for the start-up, operation, and shutdown of the nuclear energy system. The cooling system includes cooling pumps, a circulating medium, and equipment requiring cooling. It is primarily used to provide cooling for critical equipment in the nuclear energy system to ensure its normal operation. The circulating medium can be different media such as water, helium, or carbon dioxide, depending on the type of nuclear energy system.

[0031] The heater includes heating rods for providing auxiliary heating to the nuclear energy system, such as preheating of the coolant.

[0032] The lubrication system includes an oil pump, primarily used to lubricate lubrication points to reduce friction and wear on components, ensuring their normal operation and lifespan. In nuclear power systems, the lubrication system can be applied to bearings and seals of components such as main pumps and turbine units.

[0033] A test and verification system for nuclear energy systems: The experimental verification system consists of one or more experimental devices with specific simulation functions, which can be used to reproduce the main thermal-hydraulic phenomena in the nuclear energy system and verify the operating performance and safety characteristics of the nuclear energy system.

[0034] The test apparatus includes a test body, a test loop system, a measurement and control system, and a test auxiliary system. It is used to simulate one or more subsystems and one or more devices in a nuclear energy system, such as the reactor body, main coolant system, dedicated safety system, and energy conversion system, and can verify its design operating performance under specific boundary conditions.

[0035] The test subject is a system or device with specific simulation functions and specific geometric structures. The specific object and simulation requirements are determined by the verification method. The design parameters are obtained based on the similarity principle. The simulation scope includes the entire nuclear energy system, one or more subsystems of the nuclear energy system, and one or more devices in the nuclear energy system.

[0036] The test loop system includes a circulating pump, pipelines, and valves, forming multiple circulating flow loops with a specific spatial arrangement. It is used to provide an external environment for the test body and to regulate parameters such as flow rate, temperature, and pressure.

[0037] The measurement and control system includes a test parameter measurement system and a test device control system. The test parameter measurement system includes test parameter measuring instruments, test loop status indicators and protection instruments, and a corresponding data conversion and storage system, used to measure and store test target parameters, while monitoring and ensuring the normal operation of the test device. The test device control system is used to realize the power supply, start and stop of the test device, and to provide control functions for parameters such as flow rate, pressure and temperature of the device loop.

[0038] A test verification method for a nuclear energy system: The verification method includes steps such as hierarchical decomposition, phenomenon identification, maturity analysis, and verification requirements analysis. It can serve as a general process for obtaining nuclear energy system design verification requirements, determining the test types, research content, and parameter requirements for experimental verification, and forming a verification test matrix and an experimental verification system for designing nuclear energy systems.

[0039] Furthermore, each step includes the following specific details: Step 1, Hierarchical Decomposition: Based on the structural design characteristics and functional requirements of the nuclear energy system, according to structural categories such as structures, subsystems, components, equipment, parts, and materials, the nuclear energy system is decomposed into a tree-like structure diagram (hierarchical tree) with different levels, each level containing multiple items; based on the carrier form and item characteristics corresponding to the innovative design, its level in the hierarchical tree, its parent level, and its specific number are determined.

[0040] Step 2, Physical Phenomenon Identification: Based on the state and hierarchical tree of the nuclear energy system, and according to the functions and operating modes performed by the items, identify the physical phenomena or operational failure mechanisms that may occur within each item. Based on the importance index, determine the important items and their levels, and form a set of key items. Step 3, Maturity Analysis; Define design maturity levels and formulate detailed rules for evaluating the maturity of items at each level; Conduct design maturity analysis on the key item set, traverse the key items and root items in the entire hierarchical tree from bottom to top, determine the design maturity of each item in the key item set, and obtain the main items and technical factors that restrict the improvement of innovative design maturity.

[0041] Step 4: Verify the requirements analysis; items in the nuclear energy system hierarchy tree with a design maturity level lower than a specific level constitute the set of items to be verified; based on the simulation capabilities of existing analysis tools, the set of items to be verified is divided into a simulation analysis subset and an experimental verification subset; based on the experimental verification subset, the objectives and boundary conditions of each item's verification test are determined; based on the structural characteristics of the hierarchy to which the item to be verified belongs and its root item hierarchy, the principle of merging and optimizing verification tests is determined, a verification test matrix is ​​formed, and the experimental verification system of the nuclear energy system is designed.

[0042] In the verification method for the nuclear energy system, there is an iterative relationship between the steps of hierarchical decomposition, phenomenon identification, maturity analysis, and verification requirements analysis.

[0043] In step 1, the items represent the various subsystems, components, equipment, and combinations thereof that constitute the nuclear energy system.

[0044] The tree-like structure diagram (hierarchical tree) contains items at different levels of the nuclear energy system, representing the nuclear energy system as a set of items. The nuclear energy system is decomposed into levels of overall system design, subsystem design, equipment design, component design, and part design. The level under study is denoted as... i , i =1,2,3,4,5,...,n, where n is a positive integer; for any selected level, the main components it contains are numbered and denoted as... j , j =1,2,3,4,5,...,n, where n is a positive integer; Q i,j To represent any subsystem, component, or device in a nuclear energy system, in sequence [ i,j The location of an item within the hierarchical structure of the nuclear energy system allows for the decomposition of the nuclear energy system into components with... i Hierarchical structure, each level containing j A tree structure diagram of the individual items.

[0045] In the tree structure diagram, items within the same level of the nuclear energy system are arranged in order of structural feature complexity, and items that have functional coupling relationships are arranged close together.

[0046] The design innovations include partial or overall changes at the levels of materials, parts, components, equipment, and systems, as well as changes to the combination of each level, and changes to the operating mode, safety control logic, and setting values ​​of existing designs.

[0047] Furthermore, in step 2, Clearly define the design function and operating mode of each item. When a nuclear energy system has different operating modes, each physical phenomenon should be identified, and its importance should be judged and quantified. Based on the design function and operating mode, the structure of the item hierarchy tree can be iteratively adjusted.

[0048] The physical phenomena or operational failure mechanisms described depend on the design function and operating mode of the item, and their categories can include multiple disciplines such as thermal hydraulics, neutron physics, radiation protection, chemistry, and mechanics; multiple possible physical phenomena or operational failure mechanisms identified within the same item are denoted as... k , k =1,2,3,4,5,...,n, where n is a positive integer.

[0049] The important phenomena are indicated by their relative importance to the importance index. I i,j,k Representing items Q i,j Inner k The degree of importance of a physical phenomenon relative to an importance index.

[0050] The importance indicators are related to the operating mode or system state of the nuclear energy system. Under operating mode, operating specification parameters are used as importance indicators; while under accident conditions, acceptance criteria for different accidents are used as importance indicators. For example, fuel cladding temperature under a break-out loss-of-hydrate accident, and deviation from nucleation boiling ratio under a non-break-out transient accident.

[0051] The important items are those that contain any important phenomenon in the nuclear energy system, and important items with innovative designs are called key items.

[0052] The key item set is a collection or subset thereof consisting of important items with innovative designs and items with intergenerational relationships to them.

[0053] The importance of the physical phenomena or operational failure mechanisms can be determined through computational analysis, expert (group) judgment, or a combination of both. Several score levels (such as 9 or 5 points) can be used to measure the importance of different physical phenomena. For example, using a 5-point scale, 1 point represents the lowest value indicating low importance, 2 points represent low importance, 3 points represent medium importance, 4 points represent high importance, and 5 points represent the highest value indicating high importance.

[0054] Table 1 exemplarily presents the results of physical phenomenon identification and importance ranking for a nuclear power system plant-wide power outage accident, using high, medium, low, and non-existent as importance levels and deviation from the bubble-nucleation boiling ratio as the importance index.

[0055] Table 1 shows the identification and importance ranking of physical phenomena in a nuclear power plant blackout accident. In step 3, The design maturity level includes technology maturity, integration maturity, and system maturity, and is the degree to which an item can operate safely and reliably, denoted as design maturity. R .

[0056] The design maturity level can be categorized into several levels, such as levels 1-7 or 1-9. Specific descriptions of each level's design maturity can be provided from three perspectives: carrier form, verification environment conditions, and the fidelity of the verification experiment. Table 2 exemplarily illustrates the definitions of design maturity levels 1-9 and the specific descriptions of each level.

[0057] Table 2 shows the Level 9 technology maturity level of a certain passive waste heat removal technology. Design maturity analysis can begin from the first... i Starting from the first level, traverse the key items and root item in the entire hierarchy tree from bottom to top, and then determine each item in the key item set. Q i,j Design maturity R i,j Based on the intergenerational relationships of each item in the hierarchical tree, technology maturity analysis, integration maturity analysis, and system maturity analysis are performed respectively to determine the maturity of the innovative design and its subsystems.

[0058] Design maturity analysis can be conducted from three perspectives: the carrier form of the item, the environmental conditions for verification, and the fidelity of the verification test. Maturity analysis based on carrier form: Different items may have different carrier forms, such as prototypes, mockups, experimental models, etc. Maturity analysis needs to consider the impact of the carrier form on the validation process; the higher the maturity level, the closer it is to the carrier form used in actual applications. Maturity analysis is performed on the validation environment conditions: This involves the environmental conditions created when validating the item. The validation environment conditions simulate actual working conditions, including temperature, pressure, and radiation. Maturity analysis needs to consider the authenticity and realism of the validation environment conditions to ensure the accuracy and reliability of the validation results. Maturity analysis is based on the fidelity of validation tests: the fidelity of validation tests refers to the degree of similarity between the validation test and actual working conditions. In maturity analysis, the accuracy of validation tests in reflecting the performance and reliability of the item needs to be considered. Validation tests with higher fidelity can more accurately reflect the item's performance in practical applications, thereby improving the item's maturity.

[0059] The key technology maturity assessment criteria consist of different judgment conditions, and different assessment criteria can be formulated for items at different levels. The specific content of the assessment criteria can be adjusted for different nuclear energy systems.

[0060] In step 4, the first step is to construct a set of items to be verified, placing items in the nuclear energy system tree structure diagram whose maturity level is below a specific level N, i.e. R i，j Items less than N constitute the set of items to be verified. For example, when using a design maturity level classification of 1 to 9, N =7.

[0061] Then, based on the simulation capabilities and accuracy of the analysis tools, the set of items to be verified is divided into a simulation analysis subset and an experimental verification subset; the simulation analysis subset is verified using simulation analysis tools; the experimental verification subset requires experimental verification, which is the verification content that the experimental matrix needs to cover; based on the results of maturity analysis and technical factor assessment for each item, the objectives and boundary conditions of the verification experiments for each item in the experimental verification subset are determined. The principles for merging and optimizing verification tests include requirements and criteria regarding item hierarchy, verification methods, and verification cycles. Separation effect tests are conducted on items belonging to a specific innovative design and its sub-level items; overall effect tests are conducted on items at the same level and root level of the innovative design. The design verification cycle for nuclear energy systems can be coupled with the item hierarchy being verified. Furthermore, the design verification cycle includes the commissioning test process before the nuclear energy system's operation; therefore, commissioning tests should be considered a special type of verification test.

[0062] Then, the principles for merging and optimizing verification tests are defined: based on the structural characteristics of the item level to which the innovative design belongs and its root item level, several principles for merging and optimizing verification tests are defined; the principles for merging and optimizing verification tests can reduce the number of tests, merge tests with similar verification objectives, and make the most of existing verification equipment and resources, etc.

[0063] Then, a verification test matrix is ​​formed. This matrix defines the objectives, test content, boundary conditions, required resources and equipment, and corresponding specific requirements for each verification test. The verification test matrix includes a series of tests conducted to verify the nuclear energy system design, and includes the objectives, content, boundary conditions, and required resources and equipment for each test. It can serve as a guiding basis for the verification and implementation of nuclear energy system design. The test content in the verification test matrix needs to encompass the technical factors that restrict the maturity improvement of each key item in terms of parameter range.

[0064] Finally, based on the principle of similarity, one or more test devices that meet the requirements of the verification test matrix are designed to form a test verification system for the nuclear energy system. An exemplary verification test matrix analysis process is as follows: Figure 3 As shown.

[0065] In the process of obtaining the verification test matrix, the requirements for verification tests can be further obtained from the perspectives of functional verification, performance verification, safety verification, reliability verification, and compatibility verification. Functional verification requirements: Analyze and determine the functional requirements that need to be verified for each item in the nuclear energy system, based on its functional characteristics. This includes verifying whether the item can perform its intended function as designed and ensuring that its interfaces and interoperability with other items are normal.

[0066] Performance verification requirements: Analyze and determine the performance requirements that need to be verified for each item in the nuclear energy system, based on its performance characteristics. This includes verifying the performance indicators of the items under specific operating conditions, such as power output, efficiency, and response speed.

[0067] Safety Validation Requirements: Analyze and determine the safety requirements that need to be validated for each item in the nuclear energy system. This includes ensuring that items remain safe under normal operation and abnormal conditions, and effectively responding to potential failures, accidents, or disasters.

[0068] Reliability verification requirements: Analyze and determine the reliability requirements that need to be verified for each item in the nuclear energy system, based on its reliability characteristics. This includes verifying that the items can maintain their performance and reliability throughout their specified lifespan and meet the system's reliability requirements.

[0069] Compatibility verification requirements: Analyze and determine the compatibility requirements that need to be verified for the interfaces and collaborative operation between various items in the nuclear energy system. This includes verifying the correctness and stability of data exchange, information transmission, and collaborative operations between items.

[0070] The experimental verification system includes one or more experimental devices for conducting a series of tests to meet the requirements of the verification test matrix. The experimental devices and tests included are designed based on the principle of similarity.

[0071] The definition of the nuclear energy system described in this invention is related to the specific objects and stages of design and development. A nuclear energy system can be a complex system composed of structures and different functional subsystems, such as a nuclear power plant, a research reactor, or a nuclear fuel reprocessing plant; it can also be a subsystem composed of components, equipment, and piping systems that can perform specific functions, such as a reactor coolant system or a passive core cooling system; or it can be a component or equipment with a complex structure composed of parts and materials, such as fuel assemblies, turbine pumps, and valves.

[0072] Meanwhile, in this invention, nuclear energy system can be a virtual concept, and its specific meaning can be related to the goal of the research and development activities. It can refer to a complex energy conversion system composed of structures and equipment; it can also refer to a subsystem that performs a specific function, composed of equipment, components and piping systems; or it can refer to equipment or components that perform a specific function, composed of parts and equipment.

[0073] If the research and development is focused on nuclear power plants, then the nuclear energy system refers to the nuclear power plant; if the research and development is focused on cooling systems, then the nuclear energy system refers to the cooling system; if the research and development is focused on main pumps, then the nuclear energy system refers to the main pumps.

[0074] Therefore, this invention not only relates to the testing and verification system for nuclear energy systems, but also provides a method for the research and development of nuclear power plants, cooling systems or equipment to obtain a set of tests (verification test matrix) that should be carried out to confirm that the product design meets the final safety requirements.

[0075] Furthermore, regarding the verification method for the nuclear energy system: An electronic device includes a memory and a processor, the memory storing a computer program, the processor executing the computer program to implement the steps of the above method.

[0076] A computer-readable storage medium for storing computer instructions that, when executed by a processor, implement the steps of the above-described method.

[0077] The memory in the embodiments of this application can be volatile memory or non-volatile memory, or may include both volatile and non-volatile memory. Non-volatile memory can be read-only memory (ROM), programmable read-only memory (PROM), erasable programmable read-only memory (EPROM), electrically erasable programmable read-only memory (EEPROM), or flash memory. Volatile memory can be random access memory (RAM), which is used as an external cache. By way of example, but not limitation, many forms of RAM are available, such as static RAM (SRAM), dynamic RAM (DRAM), synchronous DRAM (SDRAM), double data rate synchronous DRAM (DDR SDRAM), enhanced synchronous DRAM (ESDRAM), synchronous linked DRAM (SLDRAM), and direct rambus RAM (DR RAM). It should be noted that the memory of the methods described in this invention is intended to include, but is not limited to, these and any other suitable types of memory.

[0078] In the above embodiments, implementation can be achieved entirely or partially through software, hardware, firmware, or any combination thereof. When implemented using software, it can be implemented entirely or partially in the form of a computer program product. The computer program product includes one or more computer instructions. When the computer instructions are loaded and executed on a computer, all or part of the processes or functions described in the embodiments of this application are generated. The computer can be a general-purpose computer, a special-purpose computer, a computer network, or other programmable device. The computer instructions can be stored in a computer-readable storage medium or transmitted from one computer-readable storage medium to another. For example, the computer instructions can be transmitted from one website, computer, server, or data center to another website, computer, server, or data center via wired means such as coaxial cable, optical fiber, digital subscriber line, DSL, or wireless means such as infrared, wireless, microwave, etc. The computer-readable storage medium can be any available medium that a computer can access or a data storage device such as a server or data center that integrates one or more available media. The available medium can be a magnetic medium such as a floppy disk, hard disk, magnetic tape; an optical medium such as a high-density digital video disc, DVD; or a semiconductor medium such as a solid-state disk, SSD, etc.

[0079] In implementation, each step of the above method can be completed by integrated logic circuits in the processor's hardware or by instructions in software. The steps of the method disclosed in the embodiments of this application can be directly implemented by a hardware processor, or by a combination of hardware and software modules in the processor. The software modules can reside in random access memory, flash memory, read-only memory, programmable read-only memory, electrically erasable programmable memory, registers, or other mature storage media in the art. This storage medium is located in memory, and the processor reads information from the memory and, in conjunction with its hardware, completes the steps of the above method. To avoid repetition, detailed descriptions are omitted here.

[0080] It should be noted that the processor in the embodiments of this application can be an integrated circuit chip with signal processing capabilities. During implementation, each step of the above method embodiments can be completed by the integrated logic circuits in the processor's hardware or by instructions in software form. The processor can be a general-purpose processor, a digital signal processor (DSP), an application-specific integrated circuit (ASIC), a field-programmable gate array (FPGA), or other programmable logic devices, discrete gate or transistor logic devices, or discrete hardware components. It can implement or execute the methods, steps, and logic block diagrams disclosed in the embodiments of this application. The general-purpose processor can be a microprocessor or any conventional processor. The steps of the methods disclosed in the embodiments of this application can be directly embodied as execution by a hardware decoding processor, or as execution by a combination of hardware and software modules in the decoding processor. The software modules can be located in random access memory, flash memory, read-only memory, programmable read-only memory, electrically erasable programmable memory, registers, or other mature storage media in the art. This storage medium is located in memory; the processor reads information from the memory and, in conjunction with its hardware, completes the steps of the above methods.

[0081] The above provides a detailed description of the experimental verification system and verification method for a nuclear energy system proposed in this invention, and elucidates the principles and implementation methods of this invention. The description of the above embodiments is only for the purpose of helping to understand the method and core ideas of this invention. At the same time, for those skilled in the art, there will be changes in the specific implementation methods and application scope based on the ideas of this invention. Therefore, the content of this specification should not be construed as a limitation of this invention.

Claims

1. A verification method for a nuclear energy system, characterized in that: The nuclear energy system includes the reactor body, reactor coolant system, dedicated safety system, energy conversion system, and process auxiliary system; The reactor body includes a pressure vessel and its interfaces; the pressure vessel is used to withstand the high temperature, high pressure and high radiation conditions generated during the nuclear reaction process, and to ensure the correct and safe operation of the nuclear fuel; The reactor coolant system includes a reactor pressure vessel, a primary side of a steam generator, a main pump, and a pressurizer. It is used to control and regulate the heat generated by the nuclear reaction process in the reactor and to transfer it. The primary side of the steam generator converts the heat from the reactor coolant system into steam, which is connected to the reactor pressure vessel via pipes. The main pump is used to regulate and maintain the flow rate of the reactor coolant system. The pressurizer is used to regulate and maintain the pressure of the reactor coolant system. The dedicated safety system includes an emergency core cooling system and containment-related systems. The emergency core cooling system includes a makeup water tank, a safety injection tank, a safety injection pump, and a residual heat removal heat exchanger, used to inject coolant or other specific media in the event of an accident or emergency to cool the nuclear reactor core and ensure the safety of the nuclear reactor. The containment-related systems include the containment shell, a water storage tank, pumps, and heat exchangers, used to provide radiation shielding and physical isolation for the nuclear reactor and to maintain pressure balance and gas circulation inside the containment. The energy conversion system includes a secondary side of a steam generator and a steam turbine unit, used to transfer steam from the primary side of the steam generator to other systems for energy conversion and power generation; The process support system includes an equipment cooling system, a heater, and a lubricating oil system, which provide auxiliary support functions for the start-up, operation, and shutdown of the nuclear energy system. The test verification of a nuclear energy system consists of one or more test devices with specific simulation functions, which can be used to verify the operating characteristics, thermal-hydraulic phenomena and safety performance of the nuclear energy system. The test apparatus includes a test body, a test loop system, a measurement and control system, and a process auxiliary system. It can be used for one or more subsystems and one or more devices in the simulated reactor body, main coolant system, dedicated safety system and energy conversion system of a nuclear energy system, and can verify its design performance under specific boundary conditions. The test body is a system or device with specific simulation functions and specific geometric structure. The specific object of the simulation is determined by the verification method, the design parameters are obtained based on the similarity principle, and the simulation scope includes the entire nuclear energy system, one or more subsystems of the nuclear energy system, and one or more devices in the nuclear energy system. The test loop system includes a circulating pump, pipe sections, and valves, forming multiple circulating flow loops with a specific spatial arrangement, used to provide an external environment for the test body to regulate flow rate, temperature, and pressure; The measurement and control system includes a test parameter measurement system and a test device control system. The test parameter measurement system includes test parameter measuring instruments, test loop status indicators and protection instruments, and a corresponding data conversion and storage system, used to measure and store test target parameters, while monitoring and ensuring the normal operation of the test device. The test device control system is used to realize the power supply, start and stop of the test device, and to provide control functions for the flow, pressure and temperature parameters of the device loop. The verification method specifically includes the following steps: Step 1, Hierarchical decomposition; The various subsystems, components, and equipment that constitute the nuclear energy system and their combinations are called items. The nuclear energy system is decomposed at different levels to form items at different levels; Items within the same level of the nuclear energy system are arranged in order of structural feature complexity, and items that have functional coupling relationships are arranged close together. Step 2, Physical Phenomenon Identification; Based on the state of the nuclear energy system, and according to the functions and operating modes of the items, identify the physical phenomena or operational failure mechanisms of each item, and construct a set of key items; Step 3, Maturity Analysis: The maturity of the key itemset is analyzed from three perspectives: carrier form, verification environment conditions, and the fidelity of the verification test, to determine the maturity level of each item. Step 4, verify the requirements analysis; items with maturity levels lower than a certain level in Step 3 constitute the set of items to be verified, determine the objectives and boundary conditions of the verification tests for each item, and define several principles for merging and optimizing verification tests based on the structural characteristics of the level to which the items to be verified belong and the root item level, forming a verification test matrix.

2. The verification method for a nuclear energy system according to claim 1, characterized in that: The pressure vessel of the reactor body includes fuel assemblies, in-core components, and corresponding piping interfaces, used to withstand the high temperature, high pressure, and high radiation conditions generated during the nuclear reaction, and to ensure the correct and safe operation of the nuclear fuel; the fuel assembly consists of nuclear fuel rods and grids, used to generate nuclear reactions and release heat; the in-core components are all other components within the pressure vessel except for the fuel assemblies and their related components, including the upper core support components, the lower core support components, and the core measurement support structure; the primary side of the steam generator includes heat exchange tube bundles; A steam generator is a heat exchange device in a nuclear energy system. It converts the heat from the primary side of the steam generator in the reactor coolant system into high-temperature, high-pressure steam on the secondary side of the steam generator, which is then transferred to the turbine unit to generate power or to the demand side to realize the utilization of thermal energy. The secondary side of the steam generator includes a feedwater pump, which draws liquid condensate from the turbine unit and increases its pressure, then sends it to the inlet of the steam generator. The turbine unit includes blades for realizing the energy conversion of the nuclear energy system, converting steam energy into mechanical energy; when high-temperature, high-pressure steam acts on the blades, the blades will rotate and drive the turbine shaft, thereby driving the generator to produce electrical energy; By transferring high-temperature, high-pressure steam from the secondary side of the steam generator to the turbine unit, the nuclear energy system achieves the conversion of thermal energy into mechanical energy and then into electrical energy, ultimately generating usable electricity. The equipment cooling system includes a cooling pump, the heater includes a heating rod, and the lubricating oil system includes a lubricating oil pump.

3. The verification method for the nuclear energy system according to claim 2, characterized in that: In step 1, Nuclear energy systems are decomposed into multiple levels, including overall system design, subsystem design, equipment design, component design, and part design. These levels of study are denoted as follows: i , i =1, 2, 3, 4, 5, ..., n, where n is a positive integer; for any selected level, the main items contained therein are numbered and denoted as . j , j =1, 2, 3, 4, 5, ..., n, where n is a positive integer; Therefore, any subsystem, component, and device in a nuclear energy system can be represented as Q i，j ,sequence[ i, j This indicates the position of the item within the hierarchical structure of the nuclear energy system; it decomposes the nuclear energy system into components with... i Hierarchical structure, each level containing j A tree structure diagram of the individual items.

4. The verification method for the nuclear energy system according to claim 3, characterized in that: In step 2, Based on the state and tree structure diagram of the nuclear energy system, identify the physical phenomena or operational failure mechanisms occurring within each item, denoted as... k Item; combined with the importance index, the degree of importance of each physical phenomenon relative to the importance index is obtained. I i，j，k This allows us to identify key items and their hierarchical structure that exhibit physical phenomena or operational failure mechanisms, thus forming a set of key items. The importance index is related to the operating mode or system status of the nuclear energy system. Under operating mode, the operating specifications serve as the importance index; while under accident status, the acceptance criteria for different accidents serve as the importance index.

5. The verification method for a nuclear energy system according to claim 4, characterized in that: In step 3, The degree to which an item can operate safely and reliably is called design maturity. R The design maturity of the items is marked by a score of 1-9. Conduct design maturity analysis on the key itemset, starting from the first i Starting from level 1, traverse the entire hierarchy tree from bottom to top, identifying each key item and its root item. Q i，j Design maturity R i，j ; Maturity analysis is conducted from three perspectives: the carrier form of the item, the environmental conditions for verification, and the fidelity of the verification test. Maturity analysis based on carrier form: Considering the impact of the carrier form of the item on the verification work, the higher the maturity, the closer it is to the carrier form in actual application. Maturity analysis is performed on the validation environment conditions: This involves the environmental conditions created when validating items, which simulate actual working conditions, including temperature, pressure, flow rate, and radiation. Maturity analysis based on the fidelity of the validation test: The fidelity of the validation test refers to the degree of similarity between the validation test and the actual working situation.

6. The verification method for a nuclear energy system according to claim 5, characterized in that: In step 4, First, construct a set of items to be verified, placing items in the nuclear energy system tree structure diagram with a maturity level below a specific level N, i.e. R i，j Items < N constitute the set of items to be verified. Then, based on the simulation capabilities and accuracy of the analysis tools, the set of items to be verified is divided into a simulation analysis subset and an experimental verification subset; the simulation analysis subset is verified using simulation analysis tools; the experimental verification subset requires experimental verification, which is the verification content that the experimental matrix needs to cover; based on the results of maturity analysis and technical factor assessment for each item, the objectives and boundary conditions of the verification experiments for each item in the experimental verification subset are determined. Then, define the principles for merging and optimizing verification experiments: Based on the structural characteristics of the item level to which the innovative design belongs and its root item level, define several principles for merging and optimizing verification experiments; Then, a verification test matrix is ​​formed, which defines the objectives, test content, boundary conditions, required resources and equipment, and corresponding specific requirements for each verification test; Finally, based on the principle of similarity, one or more test devices that meet the requirements of the verification test matrix are designed to form a test verification system for the nuclear energy system.

7. An electronic device comprising a memory and a processor, wherein the memory stores a computer program, characterized in that, When the processor executes the computer program, it implements the steps of the method according to any one of claims 1-5.

8. A computer-readable storage medium for storing computer instructions, characterized in that, When the computer instructions are executed by the processor, they implement the steps of the method according to any one of claims 1-5.

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