Nuclear safety grading and quality assurance grading method and system for nuclear power plant valve parts

Abstract

The invention relates to a nuclear power plant valve part nuclear safety grading and quality assurance grading method and system. The method comprises the following steps that a safety function list of a valve is generated; generating a safety function and safety level list of the valve; obtaining a part detail list of the valve, and generating a part list of the valve based on the part detail list; performing applicability analysis according to the safety function, the safety level list and the part list to obtain a corresponding relation between the safety function and the part of the valve; according to the corresponding relation between the safety functions and the parts, the target safety level of each part of the valve is determined; and determining the quality assurance level corresponding to each part based on the target safety level of each part of the valve. According to the method, safety grading is conducted on the parts of the valve, it is guaranteed that the safety grade and the quality guarantee grade of the parts of the valve adapt to the safety function borne by the parts of the valve, and the method has great significance in improving the reliability and economical efficiency of the valve and the safety and the availability rate of a nuclear power unit.

Description

Technical Field

[0001] This invention relates to the technical field of nuclear power plant equipment management, and more specifically, to a method and system for nuclear safety classification and quality assurance classification of valve components in nuclear power plants. Background Technology

[0002] According to nuclear power plant design principles, the safety level of valves is determined by the system design unit based on their function within the system. However, there are no requirements or relevant information regarding the safety classification of sub-components or parts within the valves. In practice, valve manufacturers classify the quality assurance of equipment components based on the valve safety level specified in the procurement technical requirements. However, the quality assurance classification of components only provides general principles without clear procedures and methods. This can lead to some components having quality assurance levels that are either too low or too high. When the quality assurance classification is too low, it will be incompatible with the nuclear safety functions they perform, thus affecting the equipment's ability to fully perform its safety functions and impacting the safety and reliability of the system and even the unit. Conversely, when the quality assurance classification is too high, it will cause unnecessary waste of resources and increase unnecessary resource input in process control. Summary of the Invention

[0003] The technical problem to be solved by the present invention is to provide a method and system for nuclear safety classification and quality assurance classification of valve components in nuclear power plants, addressing the problems existing in the prior art.

[0004] The technical solution adopted by this invention to solve its technical problem is: to construct a method for nuclear safety classification and quality assurance classification of valve components in nuclear power plants, including the following steps:

[0005] Obtain the system safety function information and corresponding status information of the valve, and generate a safety function list of the valve based on the system safety function information and corresponding status information;

[0006] Obtain the safety level information of the valve, and generate a safety function and safety level list of the valve by combining the safety function list and the safety level information;

[0007] Obtain the parts list of the valve, and generate the parts list of the valve based on the parts list;

[0008] Based on the list of safety functions and safety levels and the list of components, an applicability analysis is performed to obtain the correspondence between the safety functions and components of the valve.

[0009] Based on the correspondence between the safety functions and the components, the target safety level of each component of the valve is determined;

[0010] The quality assurance level of each component is determined based on the target safety level of each component and the correspondence between the safety level and the quality assurance level.

[0011] In the nuclear safety classification and quality assurance classification method for nuclear power plant valve components described in this invention, the step of acquiring the system safety function information and corresponding status information of the valve, and generating the safety function list of the valve based on the system safety function information and corresponding status information includes:

[0012] Obtain the valve procurement technical requirements document;

[0013] The valve procurement technical requirements document is identified and read to obtain the system safety function information and corresponding status information;

[0014] Based on the system safety function information and the corresponding status, determine all safety functions of the valve, and the valve status or status change corresponding to each safety function;

[0015] The safety function list is generated based on all the safety functions and the valve status or status change corresponding to each safety function.

[0016] In the nuclear safety classification and quality assurance classification method for nuclear power plant valve components described in this invention, the step of obtaining the safety level information of the valve and generating the safety function and safety level list of the valve by combining the safety function list and the safety level information includes:

[0017] By identifying and reading the safety level information from the valve procurement technical requirements, the safety level information corresponding to each safety function of the valve can be obtained.

[0018] Based on the security level information and the security function list, the security function and security level list are generated.

[0019] In the nuclear safety classification and quality assurance classification method for nuclear power plant valve components described in this invention, the step of obtaining a detailed list of valve parts and generating a component list for the valve based on the detailed list of parts includes:

[0020] Obtain the drawings of the valve;

[0021] Extract component information from the valve drawings to obtain information on all valve components;

[0022] Generate the parts list based on all the parts information;

[0023] The parts list is processed again to generate the component list.

[0024] In the nuclear safety classification and quality assurance classification method for nuclear power plant valve components described in this invention, the secondary processing of the parts list to generate the parts list includes:

[0025] Identify parts in the parts list that maintain the same state or perform the same function;

[0026] By combining the parts that maintain the same state or perform the same action, a combined component is obtained;

[0027] The assembly and other parts in the parts list are organized together to obtain the parts list.

[0028] In the nuclear safety classification and quality assurance classification method for nuclear power plant valve components described in this invention, the step of performing an applicability analysis based on the safety function and safety level list and the component list to obtain the correspondence between the valve's safety functions and components includes:

[0029] Based on the list of safety functions and safety levels and the list of components, and in conjunction with the valve operation and action mechanism, determine the applicability of each component to the corresponding safety function;

[0030] Based on the applicability described, the correspondence between each component and its corresponding safety function is determined.

[0031] In the nuclear safety classification and quality assurance classification method for nuclear power plant valve components described in this invention, determining the target safety level of each valve component based on the correspondence between the safety function and the component includes:

[0032] Based on the correspondence between the safety functions and the components, a safety classification list of the valve components is generated;

[0033] The highest safety level for each component is determined based on the aforementioned safety classification list;

[0034] The target safety level of each component of the valve is determined based on the highest safety level of each component and its component type.

[0035] In the nuclear safety classification and quality assurance classification method for nuclear power plant valve components described in this invention, the component types include: mechanical components and electrical instrumentation components;

[0036] Determining the target safety level of each component of the valve based on its highest safety level and component type includes:

[0037] If the component type is a mechanical part, then the highest safety level of the component is selected as the target safety level.

[0038] If the component type is an electrical instrumentation component, then identify the highest safety level type of the component; if the highest safety level type of the component is any one of nuclear safety level 1, nuclear safety level 2, nuclear safety level 3, or nuclear safety level, then the target level of the component is nuclear safety level; if the highest safety level type of the component is non-nuclear safety level, then the target level of the component is non-nuclear safety level.

[0039] In the nuclear safety classification and quality assurance classification method for nuclear power plant valve components described in this invention, determining the corresponding quality assurance level for each component based on its target safety level includes:

[0040] Obtain the correspondence table between safety classification and quality assurance classification;

[0041] Based on the correspondence table between the safety classification and the quality assurance classification and the target safety level of each component, the corresponding quality assurance level of each component is determined.

[0042] This invention also provides a nuclear safety classification and quality assurance classification system for valve components in nuclear power plants, comprising:

[0043] The information acquisition unit is used to acquire the system safety function information and corresponding status information of the valve, and generate a safety function list of the valve based on the system safety function information and corresponding status information.

[0044] A valve level identification unit is used to obtain the safety level information of the valve and generate a safety function and safety level list of the valve by combining the safety function list and the safety level information.

[0045] A component acquisition unit is used to acquire a detailed list of parts for the valve and generate a component list for the valve based on the detailed list of parts.

[0046] The relationship analysis unit is used to perform applicability analysis based on the list of safety functions and safety levels and the list of components to obtain the correspondence between the safety functions and components of the valve.

[0047] A safety level identification unit is used to determine the target safety level of each component of the valve based on the correspondence between the safety functions and the components.

[0048] The quality assurance level determination unit is used to determine the quality assurance level of each component based on the target safety level of each component of the valve and the correspondence between the safety level and the quality assurance level.

[0049] The nuclear safety classification and quality assurance classification method and system for nuclear power plant valve components of the present invention have the following beneficial effects: It includes the following steps: generating a safety function list for valves; generating a safety function and safety level list for valves; obtaining a detailed parts list for valves, and generating a component list for valves based on the detailed parts list; performing an applicability analysis based on the safety function and safety level list and the component list to obtain the correspondence between the valve's safety functions and components; determining the target safety level for each component of the valve based on the correspondence between safety functions and components; and determining the corresponding quality assurance level for each component based on the target safety level of each component. This invention, by classifying the safety of valve components, ensures that the safety level and quality assurance level of the valve components are commensurate with their safety functions, which is of great significance for improving valve reliability and economy, and the safety and availability of nuclear power units. Attached Figure Description

[0050] The present invention will be further described below with reference to the accompanying drawings and embodiments. In the accompanying drawings:

[0051] Figure 1 This is a flowchart illustrating the nuclear safety classification and quality assurance classification method for nuclear power plant valve components provided in this embodiment of the invention.

[0052] Figure 2 This is a logic block diagram of nuclear safety classification and quality assurance classification of nuclear power plant valve components provided in the embodiments of the present invention. Detailed Implementation

[0053] 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.

[0054] Since valves serve system functions, and valve functions rely on components or combinations of components to achieve them, this invention takes the valve's role in system safety functions as its starting point, and uses the determination of the correspondence between valve functions and components as an important approach. Ultimately, it determines the safety and quality assurance classifications of components, and clarifies the relationship between nuclear safety functions and valves and components in principle, realizing the basic logic that the control level of an item should be adapted to the function it undertakes.

[0055] refer to Figure 1 In a preferred embodiment, the nuclear safety classification and quality assurance classification method for valve components in a nuclear power plant includes the following steps:

[0056] Step S101: Obtain the system safety function information and corresponding status information of the valve, and generate a safety function list of the valve based on the system safety function information and corresponding status information.

[0057] Optionally, in this embodiment of the invention, obtaining the system safety function information and corresponding status information of the valve, and generating a safety function list of the valve based on the system safety function information and corresponding status information includes: obtaining the valve procurement technical requirements document; identifying and reading the information in the valve procurement technical requirements document to obtain the system safety function information and corresponding status information; determining all safety functions of the valve based on the system safety function information and corresponding status, and the valve status or status change corresponding to each safety function; and generating a safety function list based on all safety functions and the valve status or status change corresponding to each safety function.

[0058] Specifically, the valve procurement technical requirements document clearly lists all the safety functions (i.e., system safety functions) performed by the valve and their corresponding valve states or state changes. Therefore, this invention obtains the valve procurement technical requirements document and uses text recognition technology (including but not limited to OCR technology) to read the system safety function information and corresponding state information from it. This information can then be organized to form a safety function list. It should be noted that if the valve procurement technical requirements document does not list the system safety functions performed by the valve in detail, all safety functions performed by the valve and their corresponding valve states or state changes provided by the corresponding system design unit can be obtained through the system interface.

[0059] For example, the safety function list of a certain valve is shown in Table 1.

[0060] Table 1. List of Safety Functions of Valves

[0061]

[0062] It should be noted that the three safety functions listed in Table 1—containment isolation, flow regulation, and safety injection—are for illustrative purposes only and do not represent all the safety functions of the valve. The possible state of the valve before executing a safety function is the initial valve state, and the valve state during the execution of the safety function is the final valve state. The difference between the final state and the initial state is the valve state change, and the action requirement is whether the valve needs to participate when executing the containment isolation function.

[0063] Step S102: Obtain the safety level information of the valve, and generate a list of safety functions and safety levels of the valve by combining the safety function list and the safety level information.

[0064] Optionally, in this embodiment of the invention, obtaining the safety level information of the valve and generating the safety function and safety level list of the valve in combination with the safety function list and the safety level information includes: identifying and reading the safety level information through the valve procurement technical requirements to obtain the safety level information corresponding to each safety function of the valve; and generating the safety function and safety level list based on the safety level information and the safety function list.

[0065] Specifically, the valve procurement technical requirements document clearly lists the safety level information corresponding to various system safety functions. Therefore, in this embodiment of the invention, the safety level corresponding to each safety function of the valve can be obtained by reading the safety level information corresponding to each system safety function in the valve procurement technical requirements document, and then a list of safety functions and safety levels can be formed based on the read safety level information and the list of safety functions. Similarly, taking the valve in Table 1 above as an example, its list of safety functions and safety levels is shown in Table 2.

[0066] Table 2. List of Valve Safety Functions and Safety Levels

[0067]

[0068] It should be noted that the three safety functions listed in Table 2—containment isolation, flow regulation, and safety injection—are for illustrative purposes only and do not represent all the safety functions of the valve. The possible state of the valve before executing a safety function is the initial valve state, and the valve state during the execution of the safety function is the final valve state. The difference between the final state and the initial state constitutes the valve state change, and the action requirement indicates whether the valve needs to participate when executing the containment isolation function. The containment isolation safety function corresponds to a nuclear safety level of 2, the flow regulation safety function corresponds to a non-safety level, and the safety injection safety function corresponds to a nuclear safety level of 2.

[0069] Step S103: Obtain the valve parts list and generate the valve component list based on the parts list.

[0070] Optionally, in this embodiment of the invention, obtaining a detailed list of valve parts and generating a list of valve components based on the detailed list of parts includes: obtaining valve drawings; extracting component information from the valve drawings to obtain information on all valve components; generating a detailed list of parts based on all component information; and performing secondary processing on the detailed list of parts to generate a list of components. Optionally, in this embodiment of the invention, performing secondary processing on the detailed list of parts to generate a list of components includes: identifying components in the detailed list that maintain the same state or perform the same function; combining components that maintain the same state or perform the same function to obtain combined components; and organizing the combined components and other components in the detailed list to obtain a list of components.

[0071] Specifically, valve design units can decompose the valve structure on their drawings according to the valve type. In principle, the valve structure should be decomposed into individual small parts, but this is not always necessary. Therefore, after obtaining all component information of the valve by reading the equipment drawings, a detailed parts list is compiled. Then, based on the equipment status and operating mechanism, parts that maintain the same state or perform the same function are combined into a component (i.e., a combined component), ultimately resulting in the valve's parts list. It should be noted that all parts within a component maintain a consistent hierarchical structure. It should also be noted that the parts referred to in this invention also refer to valve components. The valve's parts list indicates the type of each component (mechanical or electrical). Again, using the aforementioned valve as an example, its parts list is shown in Table 3.

[0072] Table 3. Valve Component List

[0073]

[0074] As shown in Table 3, the valve body, valve core, and electric actuator assembly are the components of this valve, with the electric actuator assembly being a combined component. It should be noted that the valve body, valve core, and electric actuator assembly in Table 3 are for illustrative purposes only and do not represent all the components of this valve. The valve and valve core are mechanical components, while the electric actuator assembly is an electrical component. Specifically, the electric actuator assembly is a combination of the electric actuator and gearbox.

[0075] Step S104: Conduct an applicability analysis based on the list of safety functions and safety levels and the list of components to obtain the correspondence between the safety functions of the valve and the components.

[0076] Optionally, in this embodiment of the invention, the applicability analysis based on the list of safety functions and safety levels and the list of components to obtain the correspondence between the safety functions and components of the valve includes: determining the applicability of each component to the corresponding safety function based on the list of safety functions and safety levels and the list of components, combined with the valve's operation and action mechanism; and determining the correspondence between each component and the corresponding safety function based on the applicability.

[0077] Specifically, based on the safety function and safety level list generated in step S102 and the component list generated in step S103, an applicability analysis is performed on each component of the valve and each safety function of the valve to determine the correspondence between safety functions and components. That is, the participation of a component in a function is determined based on the equipment's operation and operating mechanism. For example, taking the electric actuator assembly as an example, its corresponding safety functions include: containment isolation, flow regulation, and safety injection. For containment isolation, the electric actuator assembly changes from an open to a closed state, requiring the electric actuator assembly to provide the power to close the valve; therefore, the electric actuator participates in this function. For flow regulation, the electric actuator needs to provide the power to adjust the valve, increasing or decreasing the valve opening; therefore, the electric actuator assembly also participates in the flow regulation safety function. For safety injection, the valve state does not need to change, and the electric actuator assembly does not need to function; therefore, the electric actuator assembly participates in the safety injection safety function. Through these analyses, the correspondence between each valve component and its corresponding safety function can be determined, forming a correspondence list. Similarly, taking the aforementioned valve as an example, its correspondence list is shown in Table 4.

[0078] Table 4. List of Corresponding Safety Functions and Components

[0079]

[0080]

[0081] As shown in Table 4, the correspondence between the valve body and the containment isolation safety function is yes; the correspondence between the valve body and the flow regulation safety function is yes; and the correspondence between the valve body and the safety injection safety function is yes. The correspondence between the electric actuator assembly and the containment isolation safety function is yes; the correspondence between the electric actuator assembly and the flow regulation safety function is yes; and the correspondence between the electric actuator assembly and the safety injection safety function is no. It should be noted that the valve body and electric actuator assembly in Table 4 are only illustrative examples and do not represent all components of the valve.

[0082] Step S105: Determine the target safety level of each component of the valve based on the correspondence between safety functions and components.

[0083] Optionally, in this embodiment of the invention, determining the target safety level of each component of the valve based on the correspondence between safety functions and components includes: generating a safety classification list of valve components based on the correspondence between safety functions and components; determining the highest safety level of each component based on the safety classification list; and determining the target safety level of each component of the valve based on the highest safety level of each component and its component type.

[0084] The determination of the target safety level for each valve component based on its highest safety level and component type includes: if the component type is a mechanical part, then the highest safety level of the component is selected as the target safety level; if the component type is an electrical component, then the highest safety level type of the component is identified; if the highest safety level type of the component is any one of nuclear safety level 1, nuclear safety level 2, nuclear safety level 3, or nuclear safety level, then the target level of the component is nuclear safety level; if the highest safety level type of the component is non-nuclear safety level, then the target level of the component is non-nuclear safety level.

[0085] Specifically, based on the correspondence between the valve's safety functions and its components, and the list of the valve's safety functions and safety levels, the safety level corresponding to each component can be determined, forming a component safety classification list. Then, based on the safety classification list, the highest safety level for each component is determined. Finally, the target safety level for each component is determined based on the highest safety level and its component type. Taking the aforementioned valve as an example, for the case where one component in the valve corresponds to several safety functions, the safety levels corresponding to each safety function are listed, and the highest safety level is selected. See Table 5 for details.

[0086] Table 5. Safety Classification List of Components

[0087]

[0088] As shown in Table 5, the valve body is a mechanical component, and the safety functions it performs are: containment isolation (i.e., number 1), flow regulation (i.e., number 2), and safety injection (i.e., number 3). The safety levels corresponding to each safety function are: nuclear safety level 2 (containment isolation), non-safety level (flow regulation), and nuclear safety level 2 (safety injection). Among these safety levels, nuclear safety level 2 has the highest safety level. Therefore, its highest safety level is nuclear safety level 2.

[0089] The valve core is a mechanical component, and the safety functions it performs are: containment isolation (i.e., number 1) and flow regulation (i.e., number 2). The safety levels corresponding to each safety function are: nuclear safety level 2 (containment isolation) and non-safety level (flow regulation). Among these safety levels, nuclear safety level 2 is the highest. Therefore, its highest safety level is nuclear safety level 2.

[0090] The electric head assembly is an electrical instrument component, and the safety functions it performs are: containment isolation (i.e., number 1) and flow regulation (i.e., number 2). The safety levels corresponding to each safety function are: nuclear safety level 2 (containment isolation) and non-safety level (flow regulation). Among these safety levels, nuclear safety level 2 is the highest. Therefore, its highest safety level is nuclear safety level 2.

[0091] Furthermore, after determining the highest safety level for each component, the target safety level for each component is determined according to the principles for classifying target safety levels. The principles for classifying target safety levels for components are as follows:

[0092] Mechanical components: The highest safety level of each component is selected as its target safety level;

[0093] Electrical and instrumentation components: For components with the highest safety level of nuclear safety level 1, nuclear safety level 2, nuclear safety level 3 and nuclear safety level, the target safety level of the electrical and instrumentation components is: nuclear safety level; for components with the highest safety level of non-safety level, the target safety level of the electrical and instrumentation components is: non-safety level.

[0094] Step S106: Determine the quality assurance level of each component based on the target safety level of each component of the valve and the correspondence between the safety level and the quality assurance level.

[0095] Optionally, in this embodiment of the invention, determining the quality assurance level of each component based on its target safety level and the correspondence between safety level and quality assurance level includes: obtaining a table showing the correspondence between safety classification and quality assurance classification; and determining the quality assurance level of each component based on the table and its target safety level. Specifically, taking the aforementioned valve as an example, its quality assurance level is shown in Table 6 below.

[0096] Table 6. List of Quality Assurance Levels for Components

[0097]

[0098]

[0099] In this embodiment of the invention, a nuclear safety grade is defined as: equipment and components that perform nuclear safety functions during or after a nuclear power plant design basis event, belonging to nuclear safety grade equipment and components. The design basis event refers to a series of hypothetical events selected during the design of the nuclear power plant. Nuclear safety functions include: reactivity control, core residual heat removal, and radioactive containment. The nuclear safety grades include the aforementioned: Nuclear Safety Level 1, Nuclear Safety Level 2, Nuclear Safety Level 3, Nuclear Safety Grade 4, and Non-Nuclear Safety Grade.

[0100] In this embodiment of the invention, quality assurance grading is defined as: a grading of quality assurance based on the importance of the equipment or component, i.e., the nuclear safety grading result, to provide sufficient credibility. The quality assurance grading related to the nuclear safety level includes the aforementioned: Nuclear Quality Assurance Level 1 (QA1), Nuclear Quality Assurance Level 2 (QA2), Nuclear Quality Assurance Level 3 (QA3), and / or No Nuclear Quality Assurance Level (NQA).

[0101] This invention is based on the concept that valves serve system functions, and that valve functions are realized by components or combinations of components. It forms a list of valve safety functions and a list of components by sorting out the two dimensions of valve safety functions and valve structure. Based on the list, the correspondence between the two is sorted out to determine the various safety functions undertaken by the components and their corresponding safety levels, and finally to determine the safety level of each component.

[0102] This invention develops a safety classification method for valve components, enabling the classification of valve components based on their safety, and ultimately determining the quality assurance level of these components. This ensures that the safety level and quality assurance level of valve components are commensurate with their safety functions, which is of great significance for improving valve reliability, economy, unit safety, and availability. It also has significant potential for widespread application in the nuclear power industry.

[0103] It should be noted that the term "safety" as used in this invention refers to "nuclear safety." Furthermore, the safety referred to in this invention does not include other types of safety such as industrial safety or traffic safety.

[0104] refer to Figure 2 , Figure 2 This is a preferred embodiment of the nuclear safety classification and quality assurance classification system for nuclear power plant valve components provided by the present invention.

[0105] Specifically, such as Figure 2 As shown, the nuclear safety classification and quality assurance classification system for valve components in this nuclear power plant includes:

[0106] The information acquisition unit 201 is used to acquire the system safety function information and corresponding status information of the valve, and generate a safety function list of the valve based on the system safety function information and corresponding status information.

[0107] The valve level identification unit 202 is used to obtain the safety level information of the valve and generate a list of safety functions and safety levels of the valve by combining the safety function list and the safety level information.

[0108] The component acquisition unit 203 is used to acquire a detailed list of valve parts and generate a component list of the valve based on the detailed list of parts.

[0109] The relationship analysis unit 204 is used to perform applicability analysis based on the list of safety functions and safety levels and the list of parts, and to obtain the correspondence between the safety functions of the valve and the parts.

[0110] The safety level identification unit 205 is used to determine the target safety level of each component of the valve based on the correspondence between safety functions and components.

[0111] The quality assurance level determination unit 206 is used to determine the quality assurance level of each component based on the target safety level of each component of the valve and the correspondence between the safety level and the quality assurance level.

[0112] Specifically, the specific coordination and operation process between the various units in the nuclear safety classification and quality assurance classification system for nuclear power plant valve components can be referred to the aforementioned nuclear safety classification and quality assurance classification method for nuclear power plant valve components, and will not be repeated here.

[0113] Furthermore, an electronic device of the present invention includes a memory and a processor; the memory is used to store a computer program; the processor is used to execute the computer program to implement the nuclear safety classification and quality assurance classification method for nuclear power plant valve components as described above. Specifically, according to embodiments of the present invention, the processes described above with reference to the flowchart can be implemented as computer software programs. For example, embodiments of the present invention include a computer program product comprising a computer program carried on a computer-readable medium, the computer program containing program code for performing the methods shown in the flowchart. In such embodiments, when the computer program is downloaded, installed, and executed by an electronic device, it performs the functions defined in the methods of the embodiments of the present invention. The electronic device in the present invention can be a terminal such as a laptop, desktop computer, tablet computer, or smartphone, or it can be a server.

[0114] Furthermore, one type of storage medium of the present invention stores a computer program thereon, which, when executed by a processor, implements the nuclear safety classification and quality assurance classification method for nuclear power plant valve components as described above. Specifically, it should be noted that the storage medium described above in the present invention can be a computer-readable signal medium or a computer-readable storage medium, or any combination of the two. A computer-readable storage medium can be, for example, but not limited to, an electrical, magnetic, optical, electromagnetic, infrared, or semiconductor system, device, or any combination thereof. More specific examples of a computer-readable storage medium may include, but are not limited to: an electrical connection having one or more wires, a portable computer disk, a hard disk, random access memory (RAM), read-only memory (ROM), erasable programmable read-only memory (EPROM or flash memory), optical fiber, portable compact disk read-only memory (CD-ROM), optical storage device, magnetic storage device, or any suitable combination thereof. In the present invention, a computer-readable storage medium can be any tangible medium containing or storing a program that can be used by or in conjunction with an instruction execution system, device, or apparatus. In this invention, a computer-readable signal medium may include a data signal propagated in baseband or as part of a carrier wave, carrying computer-readable program code. This propagated data signal may take various forms, including but not limited to electromagnetic signals, optical signals, or any suitable combination thereof. The computer-readable signal medium may also be any computer-readable medium other than a computer-readable storage medium, capable of sending, propagating, or transmitting a program for use by or in conjunction with an instruction execution system, apparatus, or device. The program code contained on the computer-readable medium may be transmitted using any suitable medium, including but not limited to: wires, optical fibers, RF (radio frequency), etc., or any suitable combination thereof.

[0115] The aforementioned computer-readable medium may be included in the aforementioned electronic device; or it may exist independently and not assembled into the electronic device.

[0116] The various embodiments in this specification are described in a progressive manner, with each embodiment focusing on its differences from other embodiments. Similar or identical parts between embodiments can be referred to interchangeably. For the apparatus disclosed in the embodiments, since they correspond to the methods disclosed in the embodiments, the description is relatively simple; relevant parts can be referred to the method section.

[0117] Those skilled in the art will further recognize that the units and algorithm steps of the various examples described in conjunction with the embodiments disclosed herein can be implemented in electronic hardware, computer software, or a combination of both. To clearly illustrate the interchangeability of hardware and software, the components and steps of the various examples have been generally described in terms of functionality in the foregoing description. Whether these functions are implemented in hardware or software depends on the specific application and design constraints of the technical solution. Those skilled in the art can use different methods to implement the described functions for each specific application, but such implementations should not be considered beyond the scope of this invention.

[0118] The steps of the methods or algorithms described in conjunction with the embodiments disclosed herein can be implemented directly by hardware, a software module executed by a processor, or a combination of both. The software module can be located in random access memory (RAM), main memory, read-only memory (ROM), electrically programmable ROM, electrically erasable programmable ROM, registers, hard disk, removable disk, CD-ROM, or any other form of storage medium known in the art.

[0119] The above embodiments are only for illustrating the technical concept and features of the present invention, and are intended to enable those skilled in the art to understand the content of the present invention and implement it accordingly. They do not limit the scope of protection of the present invention. All equivalent changes and modifications made within the scope of the claims of the present invention should fall within the scope of the claims of the present invention.

Claims

1. A method for nuclear safety classification and quality assurance classification of valve components in nuclear power plants, characterized in that, Includes the following steps: Obtain the system safety function information and corresponding status information of the valve, and generate a safety function list of the valve based on the system safety function information and corresponding status information; Obtain the safety level information of the valve, and generate a safety function and safety level list of the valve by combining the safety function list and the safety level information; Obtain the parts list of the valve, and generate the parts list of the valve based on the parts list; Based on the list of safety functions and safety levels and the list of components, an applicability analysis is performed to obtain the correspondence between the safety functions and components of the valve. Based on the correspondence between the safety functions and the components, the target safety level of each component of the valve is determined; The quality assurance level of each component is determined based on the target safety level of each component and the correspondence between the safety level and the quality assurance level.

2. The method for nuclear safety classification and quality assurance classification of nuclear power plant valve components according to claim 1, characterized in that, The process of acquiring the system safety function information and corresponding status information of the valve, and generating the safety function list of the valve based on the system safety function information and corresponding status information, includes: Obtain the valve procurement technical requirements document; The valve procurement technical requirements document is identified and read to obtain the system safety function information and corresponding status information; Based on the system safety function information and the corresponding status, determine all safety functions of the valve, and the valve status or status change corresponding to each safety function; The safety function list is generated based on all the safety functions and the valve status or status change corresponding to each safety function.

3. The method for nuclear safety classification and quality assurance classification of nuclear power plant valve components according to claim 1, characterized in that, The step of obtaining the safety level information of the valve and generating the safety function and safety level list of the valve by combining the safety function list and the safety level information includes: By identifying and reading the safety level information from the valve procurement technical requirements, the safety level information corresponding to each safety function of the valve can be obtained. Based on the security level information and the security function list, the security function and security level list are generated.

4. The method for nuclear safety classification and quality assurance classification of nuclear power plant valve components according to claim 1, characterized in that, The step of obtaining a detailed parts list for the valve and generating a component list for the valve based on the detailed parts list includes: Obtain the drawings of the valve; Extract component information from the valve drawings to obtain information on all valve components; Generate the parts list based on all the parts information; The parts list is processed again to generate the component list.

5. The method for nuclear safety classification and quality assurance classification of nuclear power plant valve components according to claim 4, characterized in that, The secondary processing of the parts list to generate the component list includes: Identify parts in the parts list that maintain the same state or perform the same function; By combining the parts that maintain the same state or perform the same action, a combined component is obtained; The assembly and other parts in the parts list are organized together to obtain the parts list.

6. The method for nuclear safety classification and quality assurance classification of nuclear power plant valve components according to claim 1, characterized in that, The step of performing an applicability analysis based on the list of safety functions and safety levels and the list of components to obtain the correspondence between the safety functions and components of the valve includes: Based on the list of safety functions and safety levels and the list of components, and in conjunction with the valve operation and action mechanism, determine the applicability of each component to the corresponding safety function; Based on the applicability described, the correspondence between each component and its corresponding safety function is determined.

7. The method for nuclear safety classification and quality assurance classification of nuclear power plant valve components according to claim 1, characterized in that, The step of determining the target safety level of each component of the valve based on the correspondence between the safety functions and the components includes: Based on the correspondence between the safety functions and the components, a safety classification list of the valve components is generated; The highest safety level for each component is determined based on the aforementioned safety classification list; The target safety level of each component of the valve is determined based on the highest safety level of each component and its component type.

8. The method for nuclear safety classification and quality assurance classification of nuclear power plant valve components according to claim 7, characterized in that, The types of components include: mechanical parts and electrical components; Determining the target safety level of each component of the valve based on its highest safety level and component type includes: If the component type is a mechanical part, then the highest safety level of the component is selected as the target safety level. If the component type is an electrical instrumentation component, then identify the highest safety level type of the component; if the highest safety level type of the component is any one of nuclear safety level 1, nuclear safety level 2, nuclear safety level 3, or nuclear safety level, then the target level of the component is nuclear safety level; if the highest safety level type of the component is non-nuclear safety level, then the target level of the component is non-nuclear safety level.

9. The method for nuclear safety classification and quality assurance classification of nuclear power plant valve components according to claim 1, characterized in that, The process of determining the quality assurance level of each component based on its target safety level includes: Obtain the correspondence table between safety classification and quality assurance classification; Based on the correspondence table between the safety classification and the quality assurance classification and the target safety level of each component, the corresponding quality assurance level of each component is determined.

10. A nuclear safety classification and quality assurance classification system for valve components in nuclear power plants, characterized in that, include: The information acquisition unit is used to acquire the system safety function information and corresponding status information of the valve, and generate a safety function list of the valve based on the system safety function information and corresponding status information. A valve level identification unit is used to obtain the safety level information of the valve and generate a safety function and safety level list of the valve by combining the safety function list and the safety level information. A component acquisition unit is used to acquire a detailed list of parts for the valve and generate a component list for the valve based on the detailed list of parts. The relationship analysis unit is used to perform applicability analysis based on the list of safety functions and safety levels and the list of components to obtain the correspondence between the safety functions and components of the valve. A safety level identification unit is used to determine the target safety level of each component of the valve based on the correspondence between the safety functions and the components. The quality assurance level determination unit is used to determine the quality assurance level of each component based on the target safety level of each component of the valve and the correspondence between the safety level and the quality assurance level.

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