Method and system for judging safety situation of pressure-bearing boundary of primary loop of reactor

Abstract

The invention belongs to the technical field of nuclear power devices, and discloses a reactor primary loop pressure-bearing boundary safety situation judgment method and system, and the method comprises the steps: carrying out the data collection according to a characteristic variable of a certain key link of a pressure-bearing boundary; preprocessing the characteristic variable data acquired in a certain key link; inputting the processed data into the safety state evaluation model corresponding to the link; operation is carried out through the model, and a safety state judgment result of the link is obtained; performing information association on the judgment result, the link and the identifier of the link; performing quantification processing on the judgment result; the quantification processing result is displayed in a plane coordinate axis form; the key links are associated with the basic information of the key links, and the basic information, such as production dates, manufacturers and rated parameters, of the links can be displayed and checked in a visual display page through a basic information menu; and data of all links are managed by a data management module and a database.

Description

Technical Field

[0001] The present invention belongs to but is not limited to the technical field of nuclear power plants, and in particular relates to a method and system for assessing the safety situation of a reactor primary circuit pressure boundary. Background Art

[0002] In a nuclear power plant, when the primary coolant system of a nuclear reactor (referred to as the reactor) is not sealed tightly or has a breach, the integrity of the reactor primary coolant pressure boundary (referred to as the pressure boundary) is damaged, and the coolant in the primary system will leak, thus affecting or even endangering the safe operation of the nuclear power plant. Maintaining a good safety state of the pressure boundary is the basic guarantee for the safe operation of the nuclear power plant. During the service of the nuclear power plant, in order to ensure the safe operation of the nuclear power plant, the operation management personnel need to keep abreast of the safety status of the pressure boundary at any time so as to take appropriate disposal decisions in a timely manner.

[0003] At present, nuclear power plant operation managers understand the safety status of the pressure boundary in the following ways:

[0004] (1) Nuclear power plant maintenance inspection. During the reactor shutdown and maintenance period, maintenance personnel conduct a comprehensive inspection of the pressure boundary and determine whether the pressure boundary meets the safety operation requirements of the nuclear power plant and is in a safe state based on the inspection results.

[0005] (2) Regular safety inspections. In accordance with nuclear safety management requirements, technicians regularly conduct comprehensive inspections of the reactor primary coolant system. Then, based on the inspection results, they determine whether the pressure boundary meets the safety operation requirements of the nuclear power plant and is in a safe state.

[0006] (3) Operation parameter monitoring. This method is applicable to real-time monitoring of the pressure boundary during the operation of a nuclear power plant. The method is that the operation manager observes the changes in the operating parameters of the reactor's primary coolant system and its equipment. When the relevant parameters of the primary coolant system and its equipment, such as the pressurizer pressure and liquid level, suddenly drop rapidly, it can be judged that the reactor's primary coolant system may have leaked and there is a problem with the safety of the pressure boundary.

[0007] (4) Leakage monitoring: The pre-installed reactor primary coolant leakage monitoring system is used to monitor whether the primary coolant has leaked, so as to determine the integrity and safety of the primary coolant pressure boundary.

[0008] In view of the above analysis, the technical problems that need to be solved urgently in the prior art are:

[0009] (1) Both maintenance inspections and regular safety inspections of nuclear power plants need to be carried out after the reactor has been shut down for a period of time, which will greatly affect the economy and efficiency of the nuclear power plant. Moreover, there is a considerable time interval between each maintenance inspection or regular safety inspection of a nuclear power plant and the next inspection. During this time interval, the safety status of the pressure boundary may change, and it is difficult for operation managers to understand the current safety situation of the pressure boundary, and it is also difficult to grasp and estimate the safety status of each key link of the pressure boundary.

[0010] (2) The operating parameter monitoring method is used to monitor the safety status of the pressure boundary. When an abnormal operating parameter is found, a problem may have occurred in the reactor primary coolant pressure boundary, which cannot prevent the hidden dangers of the pressure boundary.

[0011] (3) The above method relies to a certain extent on the historical experience of the operation managers in the nuclear power plants they manage. However, when the operation managers are replaced, it is difficult for the new operation managers to grasp the safety status of the pressure boundary.

[0012] (4) Operation management personnel cannot grasp the safety status of weak links and the overall safety situation of the pressure boundary through the above method.

[0013] (5) There is a lack of visual display of the safety status and security situation of key links in the pressure boundary. Summary of the invention

[0014] In view of the problems existing in the prior art, the present invention provides a method and system for judging the safety situation of the pressure boundary of the primary circuit of a reactor.

[0015] The present invention is implemented as follows: a method for evaluating the safety situation of a reactor primary circuit pressure boundary, comprising:

[0016] S1, collect data based on the characteristic variables of a key link of the pressure boundary.

[0017] S2, preprocess the characteristic variable data collected in a key link and convert them into a unified data type.

[0018] S3, input the processed data into the safety status evaluation model corresponding to the link, and calculate through the model to obtain the safety status evaluation result of the link.

[0019] S4, associate the evaluation result with the link and its identifier, so that the color of the link and its identifier changes to be consistent with the color of the corresponding security situation level, so that the security situation of the link is displayed in a visual form.

[0020] S5, at the same time, the evaluation results of this link are quantified.

[0021] S6, the quantitative processing result is displayed in the form of a plane coordinate axis. In the coordinate axis, the horizontal axis represents time, and the vertical axis represents the security level. The broken line formed by connecting the security situation of different periods of this link shows the development trend of its security situation over time.

[0022] S7, associate the key link with its basic information. In the visual display page, the basic information of the link can be displayed through the basic information menu, such as production date, manufacturer, rated parameters, etc.

[0023] S8, data in all links are managed by data management module and database.

[0024] Furthermore, the method for constructing the pressure boundary safety situation map includes:

[0025] (1) Determine the key links that affect the safety of the pressure boundary:

[0026] The safety state of the pressure-bearing boundary is determined by the integrity of the pressure-bearing boundary. The weak links of the pressure-bearing boundary determine the integrity and safety state of the pressure-bearing boundary. These weak links are the key links that affect the safety state of the pressure-bearing boundary. Depending on the type of nuclear power plant reactor, the weak links of the pressure-bearing boundary will also be different, and its key links can be determined based on the actual composition of the pressure-bearing boundary. The weak links of the pressure-bearing boundary in the present invention include key equipment or parts such as the reactor sealing surface, the reactor control rod tube seat, the reactor outlet, the reactor inlet, the main gate valve outlet, the main gate valve sealing surface, the steam generator U-tube, the steam generator inlet, the steam generator outlet, the main coolant pump sealing surface, and the main check valve.

[0027] The security situation of the pressure-bearing boundary reflects the overall security status of all key links of the pressure-bearing boundary.

[0028] (2) Constructing a visualization of the pressure boundary of the primary coolant circuit of a nuclear reactor

[0029] 1) Use visualization graphics software to construct a visualization graphic of the pressure boundary (either a three-dimensional graphic or a two-dimensional graphic).

[0030] 2) The visualization graphics must include all key links of the pressure boundary.

[0031] 3) The visualization graphics include elements such as the main equipment of the pressure boundary and the connections between equipment, pipelines and other objects.

[0032] 4) Vertical iconic arrows with certain width and height are set at key links of the pressure boundary visualization graphic.

[0033] 5) The color of each key link and its symbolic arrow is dynamically changeable, and its color is associated with the safety status information of the key link. The color of the key link and its symbolic arrow shows the safety status of the key link for users to observe.

[0034] 6) The constructed visualization graphics should be vivid, intuitive and easy to observe.

[0035] 7) Visual graphics can be drawn using software such as Unity 3D.

[0036] (3) Establish a safety status evaluation model for key links:

[0037] The method of establishing an equipment safety status evaluation model is to use the relevant factors that affect the equipment reliability and technical performance as the input variables of the evaluation model. The output of the evaluation model is the equipment safety level, which represents the safety situation.

[0038] For specific methods and steps, please see the following “Method for Establishing a Safety Status Evaluation Model for Key Links”.

[0039] (4) Information association:

[0040] The evaluation results of the safety status evaluation model of each key link of the pressure boundary are associated with the colors of the corresponding key links and their iconic arrows in the pressure boundary visualization graphics.

[0041] The colors of the key links (equipment) and their symbolic arrows in the visualization are blue, green, yellow-green, yellow-red and red. These five colors represent reliable, safe, basically safe, risky and unsafe states respectively. The situations corresponding to these five states are:

[0042] "Reliable" corresponds to "favorable situation";

[0043] “Safety” corresponds to “normal situation”;

[0044] “Basic security” corresponds to “potential threat situation”;

[0045] “There is a risk” corresponds to “dangerous situation”;

[0046] “Unsafe” corresponds to “high-risk situation”.

[0047] (5) Safety status display

[0048] The safety status display adopts three visual display methods: iconic arrow color display; key link color display; coordinate chart display historical development trend.

[0049] (6) Security situation of pressured borders

[0050] The safety status of each key link of the pressure boundary together constitutes the nuclear safety situation map of the pressure boundary, showing the overall safety situation of the pressure boundary. According to the safety situation of the pressure boundary, users can grasp the safety situation of the entire pressure boundary and the current safety weaknesses.

[0051] Furthermore, the security status display specifically includes:

[0052] 1) Iconic arrow display

[0053] According to the information association, the current safety status of the key link is displayed by the symbolic arrow set on the link. The current color of the symbolic arrow shows the current safety status of the key link.

[0054] 2) The key link itself is displayed

[0055] In the pressure boundary visualization graph, the key links are associated with their current safety status evaluation results and displayed in corresponding colors.

[0056] The color of the key link is consistent with the color of its iconic arrow, and the two together show the safety status of the key link.

[0057] 3) Coordinate graphs show historical development trends

[0058] The coordinate graph shows the relationship between the safety status of each key link and time, and is the historical development trend of the safety status of the key links.

[0059] Furthermore, the method for establishing the safety status evaluation model of the key links of the pressure boundary specifically includes:

[0060] (1) Analysis of factors affecting the safety status of key links in the pressure boundary

[0061] The safety of the key links of the pressure boundary is closely related to the reliability and technical performance of its equipment. Factors that affect the reliability and technical performance of equipment are also factors that affect the safety of key links. Factors that affect equipment reliability and technical performance are as follows:

[0062] 1) Intrinsic factors

[0063] The inherent reliability level or inherent defects of equipment formed by factors such as design, material selection and processing technology.

[0064] 2) Environmental factors

[0065] Environmental conditions such as high temperature, high pressure, humidity, radioactivity, harmful gases, vibration, wear, corrosion, and electromagnetics affect the reliability and technical performance of equipment. Harsh environmental conditions can easily accelerate the aging and failure of equipment.

[0066] 3) Usage factors

[0067] The impact of equipment operation and use on equipment reliability and technical performance is related to factors such as equipment usage intensity, load and usage mode.

[0068] 4) Installation or replacement factors

[0069] The impact of equipment installation or replacement on equipment reliability and technical performance.

[0070] 5) Aging factors

[0071] Refers to the impact of aging and deterioration of equipment on equipment reliability and technical performance.

[0072] 6) Maintenance Factors

[0073] Correct maintenance can greatly improve the reliability and technical performance of equipment, while poor maintenance or lack of maintenance will accelerate the aging of equipment.

[0074] 7) Maintenance factors

[0075] Through maintenance, equipment failures can be discovered and eliminated, equipment conditions can be understood, and equipment functions can be maintained. Improper maintenance can cause equipment hazards and may also lead to operational failures or accidents.

[0076] 8) Inspection factors

[0077] Through detection and inspection, equipment failures can be discovered, equipment conditions can be understood, and the safety of equipment use can be improved.

[0078] 9) Service life

[0079] The life of equipment is usually related to the length of time it has been in service, but other factors can extend or shorten the life of equipment.

[0080] 10) Other factors

[0081] The impact of factors other than the above on equipment reliability and technical performance.

[0082] (2) Determine the input variables of the key link safety status evaluation model

[0083] 1) Evaluation variables

[0084] The factors that affect the reliability and technical performance of the equipment are used as the evaluation variables of the safety status of the key links of the pressure boundary, that is, these variables are used as the input variables of the equipment safety status evaluation model. The evaluation variables specifically include 11 types, such as inherent factor variables, environmental factors, usage factor variables, fault variables, and other factor variables. It should be noted here that the types and quantities of evaluation variables for different links can be determined according to actual conditions.

[0085] 2) Evaluation variable indicators

[0086] When judging the safety status of the key links of the pressure-bearing boundary, it is necessary to obtain the variable values ​​that characterize each factor. Since it is difficult to obtain the exact values ​​of the above variables, the variable values ​​are divided into different level intervals to determine the values ​​of each variable. The specific method is to divide the value range of each variable into several different areas, each area represents a technical state of a key link of the pressure-bearing boundary. At the same time, this technical state also reflects the reliability and safety level of the key links of the pressure-bearing boundary. The variable value range division should be divided according to the specific characteristics of each variable.

[0087] (3) Determine the output variables of the key link safety status evaluation model

[0088] The output variable of the safety status evaluation model is defined as the safety level, which is represented by SSD. The safety level of a link represents the safety risk level or safety status of the link. The higher the safety level, the lower the risk of the link.

[0089] (4) Establishing a safety status evaluation model for key links

[0090] 1) Evaluation Model

[0091] When judging the safety of the critical loop of the pressure boundary, the above-mentioned influencing factors are used to construct characteristic variables for equipment safety judgment, which serve as the input of the safety judgment model of the critical loop of the pressure boundary.

[0092] Here, SSD is used to represent the safety of the device, and the safety of the device can be expressed as

[0093] SSD=f(VS,VE,VU,VI,VA,VM,VR,VC,VL,VO,VF)(1)

[0094] Where:

[0095] VS represents inherent factor variable;

[0096] VE represents environmental factor variable;

[0097] VU stands for usage factor variable;

[0098] VI represents the installation factor variable;

[0099] VA represents aging factor variable;

[0100] VM represents maintenance factor variable;

[0101] VR represents the maintenance factor variable;

[0102] VC represents the check factor variable;

[0103] VL represents the service life factor variable;

[0104] VF represents the variable of failure (leakage or rupture).

[0105] VO represents the variable of other factors except the above factors.

[0106] 2) Subset division of input variables (status)

[0107] 3) Subset (status) division of output variables

[0108] The subset (status) division of the output variable SSD is as follows:

[0109] SSD = FS, NS, TS, AS, DS

[0110] FS is a favorable situation, NS is a normal situation, TS is a potential threat situation, AS is an unfavorable situation, DS is a dangerous situation, and LS is an unsafe situation (leakage situation);

[0111] 4) Inference rules of the evaluation algorithm

[0112] According to the subset division of each input variable of the inference system and the relationship between each variable and the status of a certain link, the inference rules of the evaluation algorithm can be designed. In the evaluation of the safety status of a certain link, conditional inference is used to establish the inference rules. Considering the importance of nuclear safety and the nuclear safety margin that a certain link should have, the basic principles followed in designing the rules are: the principle of doubt, that is, having a skeptical attitude towards the status of a certain link; the principle of the most unfavorable, that is, considering the most unfavorable situation of this link, that is, always taking the most unfavorable factors of a certain link as the first consideration factors to determine the status of this link. The inference principles of the evaluation algorithm are as follows:

[0113] ① If VS = Val, then SSD is LS; (The output result is an unsafe situation or a leakage situation)

[0114] ② If VS = VSf, VE = VEne or VEse, VU = VUne, VI = VUne, VA = VAne, VM = VMf, VR = VRfr, VC = VCf, VL = VLm or VLe, VO = VOn, then SSD is FS; (The output result is a favorable situation)

[0115] ③ If VS = VSf, VE = VEne or VEse, VU = VUne, VI = VUne, VA = VAse, VM = VMforVMsm, VR = VRfr, VC = VCf, VL = VLm or VLe, VO = VOn, then SSD is NS; (The output result is a normal situation)

[0116] ④If VS=VSd or VE=VEse or VI=VIse or VA=VAme or VR=VRsr or VL=VLml or VO=VOs,then SSD is TS;(output result is potential threat)

[0117] ⑤If VE=VEbe or VU=VUbe or VI=VIbe or VA=VAbe or VR=VRpr or VL=VLl or VO=VOb,then SSD is DS;(output result is dangerous situation)

[0118] ⑥else,other isAS. (the rest of the output results are unfavorable)

[0119] 5) Output quantization

[0120] The situation is represented by segmentation in the interval [0,1]. According to the 6 situations, the interval [-1,1] is divided into 6 levels, each level represents a situation, as follows:

[0121]

[0122] Using the above quantification, the evaluation result of a certain link is used as the vertical axis, and the evaluation date is used as the horizontal axis. The development trend of the safety status of this link over time can be displayed on the axis. Note: The output quantification value is determined based on the expert's cognitive experience.

[0123] Furthermore, the method for dividing the values ​​of the safety status evaluation variables of the key links of the pressure boundary specifically includes:

[0124] ① Intrinsic factor variable (VS)

[0125] It reflects the inherent technical characteristics and reliability level of the key links of the pressure boundary.

[0126] If a link in the pressure-bearing boundary has no inherent defects or shortcomings in design and manufacturing, the value of the inherent factor variable of this link can be considered to be fixed and can be taken as "normal"; if this link has inherent defects or shortcomings in design and manufacturing, the value can be taken as "defective" according to the degree of the inherent defects or shortcomings of this link.

[0127] ② Environmental factor variables (VE)

[0128] The impact of environmental factors on each link of the pressure boundary is relatively complex, and the impact on each link is often a long-term and repeated process. The severity of the impact of various factors is also different. The impact on the technical performance of each link may be slight or serious, and even cause the failure of the link. Therefore, the value range of environmental factor variables is relatively wide. According to the degree of influence of environmental factors on the technical performance of equipment, the impact of environmental factor variables can be divided into several levels such as "no impact", "influence", and "great impact".

[0129] ③Using factor variables (VU)

[0130] The influence of usage factors includes the correctness of use, the intensity of use, the way of use, etc. According to the actual situation of the use influence of a certain link, the influence of the usage factor variable can be divided into three levels: "no influence", "influence" and "significant influence".

[0131] ④Installation or replacement factor variables (VI)

[0132] If a link is installed correctly, it will not affect the technical performance of the link, and this factor can be ignored. If there is a problem with the installation of the link, as the equipment is used for a longer time, it will have an adverse effect on the technical performance of the link, and the role of this factor needs to be considered.

[0133] According to the actual situation of the impact of installation factors, the impact of installation factor variables can be divided into two levels: "no impact" and "influence". Because when the installation brings a greater impact, reinstallation may be considered.

[0134] If a link is replaced recently, since the replacement process has been inspected and tested, the link can be considered a new link and will not be affected by installation factors.

[0135] ⑤ Aging factor variable (VA)

[0136] Aging is a common phenomenon in nuclear power systems. According to the degree of aging in a certain link, the aging impact can be divided into four levels: "no aging", "aging", "moderate aging" and "serious aging".

[0137] ⑥Maintenance factor variable (VM)

[0138] During the service period, the quality of maintenance work directly affects the performance of each link. The actual situation is that some links may make maintenance work difficult to achieve, which makes the link have potential problems or safety risks. According to the maintenance status of the link, the maintenance factor can be divided into three levels: "well maintained", "averagely maintained" and "no maintenance".

[0139] ⑦Maintenance factor variable (VR)

[0140] Maintenance work is also an important factor that directly affects the technical performance of each link. The technical performance of a faulty link can be restored through good maintenance. If the maintenance work of a link is not thorough, it will cause hidden dangers, thereby reducing the safety index of the link. The actual situation is that some links may make maintenance work difficult to achieve, which makes the link have potential problems or safety risks. According to the actual maintenance situation of a link, the maintenance factors can be divided into three levels: "thorough maintenance (or replacement of new products)", "incomplete maintenance", and "poor maintenance".

[0141] ⑧ Detection and inspection factor variable (VC)

[0142] Regular inspections can detect faults or problems in each link, and timely take corresponding disposal measures to keep it in good technical condition. If there is a lack of inspection and inspection in a certain link, it may cause hidden dangers in that link and increase the safety risk of that link. According to the actual situation of the inspection and inspection of each link, the impact of the inspection and inspection factors can be divided into three levels: "careful inspection", "general inspection" and "no inspection". Among them, no impact refers to the situation where the inspection and inspection and problem handling are relatively good, impact refers to the situation where the inspection and inspection and problem handling are general, and greater impact refers to the situation where the inspection and inspection are missing.

[0143] ⑨Service life variable (VL)

[0144] The service life has a direct impact on the safety of each link. The impact of service life is related to the service life of a link. According to the analysis of the impact of service life on the safety of a link, the service life variable can be divided into four stages: "early stage", "middle stage", "mid-late stage" and "final stage".

[0145] ⑩Fault variable

[0146] Problems such as cracks and leakage in the key ring of the pressure-bearing boundary directly affect the safety of the key link, making the link unsafe.

[0147] Other factor variables (VO)

[0148] The impact of other factors on equipment safety is generally determined based on actual conditions and can generally be divided into three levels: "no impact", "influence" and "significant impact".

[0149] Another object of the present invention is to provide a reactor primary circuit pressure boundary safety situation assessment system for implementing the reactor primary circuit pressure boundary safety situation assessment method, comprising:

[0150] 1. Visual display module:

[0151] The visualization display module intuitively displays the safety status of each key link of the nuclear reactor primary coolant system in the form of visual graphics, and the visualization graphics are drawn through Unity 3D.

[0152] 2. Key link safety status evaluation model management module:

[0153] This module contains a safety status evaluation model for each key link of the pressure boundary. Using this evaluation model, according to the relevant information of each key link input by the system, the current safety status analysis of each key link is completed, and the analysis results are associated with the corresponding links of the pressure boundary, and displayed in a visual form in the pressure boundary visualization structure diagram.

[0154] 3. Data management module:

[0155] This module manages the data of each key link of the pressure boundary, including historical data. The historical data of each key link within a specified time range can be queried in this module to intuitively understand the historical safety situation of each key link and its development and change trends.

[0156] 4. User management module:

[0157] This module manages system users. System users are divided into two categories: administrators and ordinary users. Administrators have system maintenance management authority, and ordinary users have nuclear power plant operation management authority, that is, system use management authority.

[0158] Furthermore, a visualization structure diagram of the pressure boundary of the reactor primary coolant system is displayed through a visualization display module. In the visualization structure diagram, each key link that may affect the integrity of the pressure boundary is marked with color and color markers (vertical arrows), and the color of each link and its marker represents the corresponding safety status of the link. All key links and their markers in the visualization structure diagram of the reactor primary coolant system are combined to form an overall safety situation diagram of the reactor primary coolant pressure boundary. Through the safety situation diagram, the current overall safety situation of the pressure boundary and the safety status of the key links can be directly observed and understood. In this way, nuclear power operation managers can view the current overall safety situation of the pressure boundary and the safety situation of each key link at any time through the management system.

[0159] Based on the safety situation map of the pressure boundary, nuclear power operation managers can observe and grasp the weak links of the pressure boundary, estimate the safety status of each key link of the pressure boundary, and take appropriate disposal decisions and measures in time before problems occur in the pressure boundary, so as to prevent and eliminate hidden dangers in the pressure boundary.

[0160] By using the data management module, nuclear power operation managers can observe the current overall safety situation of the pressure boundary and the safety status of each key link at any time through the system display terminal equipment, and grasp the weak links of the pressure boundary. Newly appointed operation managers can also use the data management module to understand the development and changes of the safety situation of each key link of the pressure boundary over time, and grasp the safety situation of the pressure boundary and the safety status of each key link.

[0161] Another object of the present invention is to provide a computer device, which includes a memory and a processor, wherein the memory stores a computer program, and when the computer program is executed by the processor, the processor executes the steps of the method for assessing the safety situation of the pressure boundary of the first circuit of a reactor.

[0162] Another object of the present invention is to provide a computer-readable storage medium storing a computer program. When the computer program is executed by a processor, the processor executes the steps of the method for assessing the safety situation of the pressure boundary of the first loop of a reactor.

[0163] Another object of the present invention is to provide an information data processing terminal, which includes the reactor primary loop pressure boundary safety situation assessment system.

[0164] In combination with the above technical solutions and the technical problems solved, the advantages and positive effects of the technical solutions to be protected by the present invention are as follows:

[0165] First, the present invention enables nuclear power operation management personnel to observe and understand the current overall safety situation of the pressure boundary and the safety status of each key link at any time through the system display terminal. The system provides real-time data presentation, which helps to fully understand the operating status and ensure the safe and reliable operation of nuclear power plants under various working conditions.

[0166] The present invention can timely remind nuclear power operation management personnel and device support personnel to take preventive measures by monitoring adverse changes in the safety situation. Compared with the traditional method that relies on operation parameter monitoring and leakage monitoring, it significantly reduces the passive situation of taking remedial measures only after problems such as leakage occur in the reactor primary loop coolant system, and improves the foresight and initiative of safety management.

[0167] The present invention introduces the method of safety situation diagram to intuitively display the safety situation of the pressure boundary of the primary coolant circuit in a visual form. The method can present complex data in a visual and easy-to-understand way, helping operation managers to quickly identify safety hazards and enhance the efficiency and accuracy of risk assessment.

[0168] The present invention proposes a key link safety status evaluation model and its construction method, and combines multi-dimensional data analysis technology to scientifically evaluate the safety status of key links in the pressure boundary. The model provides a theoretical basis for the safety monitoring of nuclear power plants and further improves the intelligent and refined management level of the system.

[0169] Second, as auxiliary evidence of the inventiveness of the claims of the present invention, it is also reflected in the following important aspects:

[0170] (1) The expected benefits and commercial value of the technical solution of the present invention after transformation are:

[0171] (2) The technical solution of the present invention fills the technical gap in the industry at home and abroad:

[0172] (3) The technical solution of the present invention solves the technical problems that people have been eager to solve but have never been able to solve successfully:

[0173] (4) The technical solution of the present invention overcomes technical prejudice:. BRIEF DESCRIPTION OF THE DRAWINGS

[0174] Figure 1 It is a schematic diagram of the principle of a method for assessing the safety situation of a reactor primary circuit pressure boundary provided by an embodiment of the present invention;

[0175] Figure 2 It is a schematic diagram of the structure of a reactor primary circuit pressure boundary safety situation assessment system provided by an embodiment of the present invention;

[0176] Figure 3 It is a schematic diagram of a software architecture diagram provided by an embodiment of the present invention;

[0177] Figure 4 It is a schematic diagram of a visualized two-dimensional display of the safety situation of the pressure boundary of the reactor primary loop provided by an embodiment of the present invention. DETAILED DESCRIPTION

[0178] In order to make the purpose, technical solution and advantages of the present invention more clearly understood, the present invention is further described in detail below in conjunction with the embodiments. It should be understood that the specific embodiments described herein are only used to explain the present invention and are not used to limit the present invention.

[0179] The present invention provides a method and a display system for evaluating the safety situation of a reactor primary circuit pressure boundary. The system displays the safety situation of a nuclear reactor primary circuit coolant pressure boundary in a visual manner, and manages key link safety situation evaluation models, data and users associated with the safety situation.

[0180] First, data collection is performed through characteristic variables for the key links of the pressure-bearing boundary. The collected data is preprocessed in a unified format and converted into standardized data types to ensure the accuracy and consistency of subsequent analysis.

[0181] The preprocessed data is input into the pre-built safety status evaluation model, and the safety status evaluation result of the link is obtained through model operation. The model is based on the evaluation algorithm of key characteristic variables and can accurately judge the safety status of the link.

[0182] The safety status assessment results are associated with the corresponding links and their identifiers. The color of the identifier changes with the level of the safety situation, so that the safety situation of the link is displayed intuitively in a visual form, making it easier for operators to quickly grasp the safety status of key links.

[0183] The evaluation results are quantified and the development trend of the security situation of each link is displayed through the plane coordinate axis. The horizontal axis represents time, the vertical axis represents the security level, and the security situation of each time period is connected into a broken line, which intuitively presents the dynamic trend of the security status changing over time.

[0184] By associating with the basic information menu in the visualization page, you can view the basic information of the link in real time, such as production date, manufacturer, rated parameters, etc. This information integration method improves the comprehensiveness and convenience of information management.

[0185] Data from all links are centrally managed by the data management module and database to ensure the integrity, reliability and traceability of the data, providing solid data support for dynamic monitoring and analysis of security situations.

[0186] The system includes a pressure boundary safety situation visualization display module, a key link model management module, a data management module and a user management module. The technical methods include: a method for constructing a safety situation diagram of the pressure boundary of the reactor primary loop coolant; a safety situation visualization display method; and a key link safety situation evaluation model.

[0187] 1. Visual display module

[0188] The visualization display module intuitively displays the safety status of each key link of the nuclear reactor primary coolant system in the form of visual graphics, and the visualization graphics are drawn through Unity 3D.

[0189] 2. Key link safety status evaluation model management module

[0190] This module contains a safety status evaluation model for each key link of the pressure boundary. Using this evaluation model, according to the relevant information of each key link input by the system, the current safety status analysis of each key link is completed, and the analysis results are associated with the corresponding links of the pressure boundary, and displayed in a visual form in the pressure boundary visualization structure diagram.

[0191] 3. Data management module

[0192] This module manages the data of each key link of the pressure boundary, including historical data. The historical data of each key link within a specified time range can be queried in this module to intuitively understand the historical safety situation of each key link and its development and change trends.

[0193] 4. User management module

[0194] This module manages system users. System users are divided into two categories: administrators and ordinary users. Administrators have system maintenance management authority, and ordinary users have nuclear power plant operation management authority, that is, system use management authority.

[0195] In order to display the safety situation of the pressure boundary of the primary coolant loop of a nuclear reactor in a visual manner, the present invention provides a method for constructing a visualization graphic of the safety situation of the pressure boundary, a method for evaluating the safety status of key links, and a method for visualizing the safety situation.

[0196] 1. Construction method of pressure boundary safety situation map

[0197] The method of constructing the pressure boundary security situation map is as follows:

[0198] (1) Determine the key links that affect the safety of the pressure boundary

[0199] The safety state of the pressure-bearing boundary is determined by the integrity of the pressure-bearing boundary. The weak links of the pressure-bearing boundary determine the integrity and safety state of the pressure-bearing boundary. These weak links are the key links that affect the safety state of the pressure-bearing boundary. Depending on the type of nuclear power plant reactor, the weak links of the pressure-bearing boundary will also be different, and its key links can be determined based on the actual composition of the pressure-bearing boundary. The weak links of the pressure-bearing boundary in the present invention include key equipment or parts such as the reactor sealing surface, the reactor control rod tube seat, the reactor outlet, the reactor inlet, the main gate valve outlet, the main gate valve sealing surface, the steam generator U-tube, the steam generator inlet, the steam generator outlet, the main coolant pump sealing surface, and the main check valve.

[0200] The security situation of the pressure-bearing boundary reflects the overall security status of all key links of the pressure-bearing boundary.

[0201] (2) Constructing a visualization of the pressure boundary of the primary coolant circuit of a nuclear reactor

[0202] 1) Use visualization graphics software to construct a visualization graphic of the pressure boundary (either a three-dimensional graphic or a two-dimensional graphic).

[0203] 2) The visualization graphics must include all key links of the pressure boundary.

[0204] 3) The visualization graphics include elements such as the main equipment of the pressure boundary and the connections between equipment, pipelines and other objects.

[0205] 4) Vertical iconic arrows with certain width and height are set at key links of the pressure boundary visualization graphic.

[0206] 5) The color of each key link and its symbolic arrow is dynamically changeable, and its color is associated with the safety status information of the key link. The color of the key link and its symbolic arrow shows the safety status of the key link for users to observe.

[0207] 6) The constructed visualization graphics should be vivid, intuitive and easy to observe.

[0208] 7) Visual graphics can be drawn using software such as Unity 3D.

[0209] (3) Establishing a safety status evaluation model for key links

[0210] The method of establishing an equipment safety status evaluation model is to use the relevant factors that affect the equipment reliability and technical performance as the input variables of the evaluation model. The output of the evaluation model is the equipment safety level, which represents the safety situation.

[0211] For specific methods and steps, please see the following “Method for Establishing a Safety Status Evaluation Model for Key Links”.

[0212] (4) Information association

[0213] The evaluation results of the safety status evaluation model of each key link of the pressure boundary are associated with the colors of the corresponding key links and their iconic arrows in the pressure boundary visualization graphics.

[0214] The colors of the key links (equipment) and their symbolic arrows in the visualization are blue, green, yellow-green, yellow-red and red. These five colors represent reliable, safe, basically safe, risky and unsafe states respectively. The situations corresponding to these five states are:

[0215] "Reliable" corresponds to "favorable situation";

[0216] “Safety” corresponds to “normal situation”;

[0217] “Basic security” corresponds to “potential threat situation”;

[0218] “There is a risk” corresponds to “dangerous situation”;

[0219] “Unsafe” corresponds to “high-risk situation”.

[0220] (5) Safety status display

[0221] The safety status display adopts three visual display methods: iconic arrow color display; key link color display; coordinate chart display historical development trend.

[0222] 1) Iconic arrow display

[0223] According to the information association, the current safety status of the key link is displayed by the symbolic arrow set on the link. The current color of the symbolic arrow shows the current safety status of the key link.

[0224] 2) The key link itself is displayed

[0225] In the pressure boundary visualization graph, the key links are associated with their current safety status evaluation results and displayed in corresponding colors.

[0226] The color of the key link is consistent with the color of its iconic arrow, and the two together show the safety status of the key link.

[0227] 3) Coordinate graphs show historical development trends

[0228] The coordinate graph shows the relationship between the safety status of each key link and time, and is the historical development trend of the safety status of the key links.

[0229] (6) Security situation of pressured borders

[0230] The safety status of each key link of the pressure boundary together constitutes the nuclear safety situation map of the pressure boundary, showing the overall safety situation of the pressure boundary. According to the safety situation of the pressure boundary, users can grasp the safety situation of the entire pressure boundary and the current safety weaknesses.

[0231] 2. Method for establishing a safety status evaluation model for key links of the pressure boundary

[0232] (1) Analysis of factors affecting the safety status of key links in the pressure boundary

[0233] The safety of the key links of the pressure boundary is closely related to the reliability and technical performance of its equipment. Factors that affect the reliability and technical performance of equipment are also factors that affect the safety of key links. Factors that affect equipment reliability and technical performance are as follows:

[0234] 1) Intrinsic factors

[0235] The inherent reliability level or inherent defects of equipment formed by factors such as design, material selection and processing technology.

[0236] 2) Environmental factors

[0237] Environmental conditions such as high temperature, high pressure, humidity, radioactivity, harmful gases, vibration, wear, corrosion, and electromagnetics affect the reliability and technical performance of equipment. Harsh environmental conditions can easily accelerate the aging and failure of equipment.

[0238] 3) Usage factors

[0239] The impact of equipment operation and use on equipment reliability and technical performance is related to factors such as equipment usage intensity, load and usage mode.

[0240] 4) Installation or replacement factors

[0241] The impact of equipment installation or replacement on equipment reliability and technical performance.

[0242] 5) Aging factors

[0243] Refers to the impact of aging and deterioration of equipment on equipment reliability and technical performance.

[0244] 6) Maintenance Factors

[0245] Correct maintenance can greatly improve the reliability and technical performance of equipment, while poor maintenance or lack of maintenance will accelerate the aging of equipment.

[0246] 7) Maintenance factors

[0247] Through maintenance, equipment failures can be discovered and eliminated, equipment conditions can be understood, and equipment functions can be maintained. Improper maintenance can cause equipment hazards and may also lead to operational failures or accidents.

[0248] 8) Inspection factors

[0249] Through detection and inspection, equipment failures can be discovered, equipment conditions can be understood, and the safety of equipment use can be improved.

[0250] 9) Service life

[0251] The life of equipment is usually related to the length of time it has been in service, but other factors can extend or shorten the life of equipment.

[0252] 10) Other factors

[0253] The impact of factors other than the above on equipment reliability and technical performance.

[0254] (2) Determine the input variables of the key link safety status evaluation model

[0255] 1) Evaluation variables

[0256] The factors that affect the reliability and technical performance of the equipment are used as the evaluation variables of the safety status of the key links of the pressure boundary, that is, these variables are used as the input variables of the equipment safety status evaluation model. The evaluation variables specifically include 11 types, such as inherent factor variables, environmental factors, usage factor variables, fault variables, and other factor variables. It should be noted here that the types and quantities of evaluation variables for different links can be determined according to actual conditions.

[0257] 2) Evaluation variable indicators

[0258] When judging the safety status of the key links of the pressure-bearing boundary, it is necessary to obtain the variable values ​​that characterize each factor. Since it is difficult to obtain the exact values ​​of the above variables, the variable values ​​are divided into different level intervals to determine the values ​​of each variable. The specific method is to divide the value range of each variable into several different areas, each area represents a technical state of a key link of the pressure-bearing boundary. At the same time, this technical state also reflects the reliability and safety level of the key links of the pressure-bearing boundary. The variable value range division should be divided according to the specific characteristics of each variable. The following introduces the variable value division method for judging the safety status of the key links of the pressure-bearing boundary.

[0259] ① Intrinsic factor variable (VS)

[0260] It reflects the inherent technical characteristics and reliability level of the key links of the pressure boundary.

[0261] If a link in the pressure-bearing boundary has no inherent defects or shortcomings in design and manufacturing, the value of the inherent factor variable of this link can be considered to be fixed and can be taken as "normal"; if this link has inherent defects or shortcomings in design and manufacturing, the value can be taken as "defective" according to the degree of the inherent defects or shortcomings of this link.

[0262] ② Environmental factor variables (VE)

[0263] The impact of environmental factors on each link of the pressure boundary is relatively complex, and the impact on each link is often a long-term and repeated process. The severity of the impact of various factors is also different. The impact on the technical performance of each link may be slight or serious, and even cause the failure of the link. Therefore, the value range of environmental factor variables is relatively wide. According to the degree of influence of environmental factors on the technical performance of equipment, the impact of environmental factor variables can be divided into several levels such as "no impact", "influence", and "great impact".

[0264] ③Using factor variables (VU)

[0265] The influence of usage factors includes the correctness of use, the intensity of use, the way of use, etc. According to the actual situation of the use influence of a certain link, the influence of the usage factor variable can be divided into three levels: "no influence", "influence" and "significant influence".

[0266] ④Installation or replacement factor variables (VI)

[0267] If a link is installed correctly, it will not affect the technical performance of the link, and this factor can be ignored. If there is a problem with the installation of the link, as the equipment is used for a longer time, it will have an adverse effect on the technical performance of the link, and the role of this factor needs to be considered.

[0268] According to the actual situation of the impact of installation factors, the impact of installation factor variables can be divided into two levels: "no impact" and "influence". Because when the installation brings a greater impact, reinstallation may be considered.

[0269] If a link is replaced recently, since the replacement process has been inspected and tested, the link can be considered a new link and will not be affected by installation factors.

[0270] ⑤ Aging factor variable (VA)

[0271] Aging is a common phenomenon in nuclear power systems. According to the degree of aging in a certain link, the aging impact can be divided into four levels: "no aging", "aging", "moderate aging" and "serious aging".

[0272] ⑥Maintenance factor variable (VM)

[0273] During the service period, the quality of maintenance work directly affects the performance of each link. The actual situation is that some links may make maintenance work difficult to achieve, which makes the link have potential problems or safety risks. According to the maintenance status of the link, the maintenance factor can be divided into three levels: "well maintained", "averagely maintained" and "no maintenance".

[0274] ⑦Maintenance factor variable (VR)

[0275] Maintenance work is also an important factor that directly affects the technical performance of each link. The technical performance of a faulty link can be restored through good maintenance. If the maintenance work of a link is not thorough, it will cause hidden dangers, thereby reducing the safety index of the link. The actual situation is that some links may make maintenance work difficult to achieve, which makes the link have potential problems or safety risks. According to the actual maintenance situation of a link, the maintenance factors can be divided into three levels: "thorough maintenance (or replacement of new products)", "incomplete maintenance", and "poor maintenance".

[0276] ⑧ Detection and examination factor variable (VC)

[0277] Regular inspections can detect faults or problems in each link, and timely take corresponding disposal measures to keep it in good technical condition. If there is a lack of inspection and inspection in a certain link, it may cause hidden dangers in that link and increase the safety risk of that link. According to the actual situation of the inspection and inspection of each link, the impact of the inspection and inspection factors can be divided into three levels: "careful inspection", "general inspection" and "no inspection". Among them, no impact refers to the situation where the inspection and inspection and problem handling are relatively good, impact refers to the situation where the inspection and inspection and problem handling are general, and greater impact refers to the situation where the inspection and inspection are missing.

[0278] ⑨Service life variable (VL)

[0279] The service life has a direct impact on the safety of each link. The impact of service life is related to the service life of a link. According to the analysis of the impact of service life on the safety of a link, the service life variable can be divided into four stages: "early stage", "middle stage", "mid-late stage" and "final stage".

[0280] ⑩Fault variable

[0281] Problems such as cracks and leakage in the key ring of the pressure-bearing boundary directly affect the safety of the key link, making the link unsafe.

[0282] Other factor variables (VO)

[0283] The impact of other factors on equipment safety is generally determined based on actual conditions and can generally be divided into three levels: "no impact", "influence" and "significant impact".

[0284] (3) Determine the output variables of the key link safety status evaluation model

[0285] The output variable of the safety status evaluation model is defined as the safety level, which is represented by SSD. The safety level of a link represents the safety risk level or safety status of the link. The higher the safety level, the lower the risk of the link.

[0286] (4) Establishing a safety status evaluation model for key links

[0287] 1) Evaluation Model

[0288] When judging the safety of the critical loop of the pressure boundary, the above-mentioned influencing factors are used to construct characteristic variables for equipment safety judgment, which serve as the input of the safety judgment model of the critical loop of the pressure boundary.

[0289] Here, SSD is used to represent the safety of the device, and the safety of the device can be expressed as

[0290] SSD=f(VS,VE,VU,VI,VA,VM,VR,VC,VL,VO,VF)(1)

[0291] Where:

[0292] VS represents inherent factor variable;

[0293] VE represents environmental factor variable;

[0294] VU stands for usage factor variable;

[0295] VI represents the installation factor variable;

[0296] VA represents aging factor variable;

[0297] VM represents maintenance factor variable;

[0298] VR represents the maintenance factor variable;

[0299] VC represents the check factor variable;

[0300] VL represents the service life factor variable;

[0301] VF represents the failure (leakage or rupture) variable.

[0302] VO represents other factor variables besides the above factors.

[0303] 2) Input variable subset partitioning (state)

[0304] The input variables of the evaluation model are shown in Table 1.

[0305] Table 1 Input variables of the evaluation model

[0306]

[0307]

[0308] For each input variable of the inference system shown in Table 1, its subset (state) division is shown in Table 2.

[0309] Table 2 Input variable subset (state) division of the evaluation model

[0310]

[0311]

[0312] 3) Output variable subset (state) division

[0313] The output variable SSD subset (state) is divided as follows:

[0314] SSD=FS,NS,TS,AS,DS

[0315] In the above subset (state) divisions, the meanings of the symbols FS, NS, TS, AS, DS, etc. are shown in Table 3.

[0316] Table 3 Meaning of symbols in output variable subset (state) division

[0317] Serial number symbol meaning 1 FS Favorable situation 2 NS Normal situation 3 TS Potential threat situation 4 AS Unfavorable situation 5 DS Dangerous situation 6 LS Unsafe situation (leakage situation)

[0318] 4) Judging algorithm reasoning rules

[0319] According to the subset division of each input variable of the reasoning system and the relationship between each variable and the state of a certain link, the reasoning rules of the judgment algorithm can be designed. In the judgment of the safety state of a certain link, the conditional reasoning method is used to establish the reasoning rules. Taking into account the importance of nuclear safety and the nuclear safety margin that a certain link should have, the basic principles followed when designing rules are: the questioning principle, that is, to question the state of a certain link; the most unfavorable principle, that is, to take into account the most unfavorable conditions of the link, that is, always take the most unfavorable factors of a link as the first consideration to determine the state of the link. Based on this idea, the reasoning principles of the design judgment algorithm are as follows:

[0320] ①If VS=Val,then SSD is LS;(output result is unsafe situation or leakage situation)

[0321] ②If VS=VSf,VE=VEne or VEse,VU=VUne,VI=VUne,VA=VAne,VM=VMf,VR=VRfr,VC=VCf,VL=VLm or VLe,VO=VOn,then SSD is FS;(output result is favorable situation)

[0322] ③If VS=VSf,VE=VEne or VEse,VU=VUne,VI=VUne,VA=VAse,VM=VMforVMsm,VR=VRfr,VC=VCf,VL=VLm or VLe,VO=VOn,then SSD is NS;(output result is normal)

[0323] ④If VS=VSd or VE=VEse or VI=VIse or VA=VAme or VR=VRsr or VL=VLml or VO=VOs,then SSD is TS;(output result is potential threat)

[0324] ⑤If VE=VEbe or VU=VUbe or VI=VIbe or VA=VAbe or VR=VRpr or VL=VLl or VO=VOb,then SSD is DS;(output result is dangerous situation)

[0325] ⑥else,other isAS. (the rest of the output results are unfavorable)

[0326] 5) Output quantization

[0327] The situation is represented by segmentation in the interval [0,1]. According to the 6 situations, the interval [-1,1] is divided into 6 levels, each level represents a situation, as follows:

[0328]

[0329] Using the above quantification, the evaluation result of a certain link is used as the vertical axis, and the evaluation date is used as the horizontal axis. The development trend of the safety status of this link over time can be displayed on the axis. Note: The output quantification value is determined based on the expert's cognitive experience.

[0330] The principle of the present invention is as follows Figure 1 shown.

[0331] The principle of the present invention is explained by taking the safety situation evaluation and display of a key link of a pressure-bearing boundary as an example.

[0332] (1) Collect data based on the characteristic variables of a key link of the pressure boundary.

[0333] (2) Preprocess the characteristic variable data collected at a key link and convert them into a unified data type.

[0334] (3) Input the processed data into the safety status evaluation model corresponding to the link. The model is used to perform calculations to obtain the safety status evaluation result of the link.

[0335] (4) The evaluation result is associated with the link and its identifier, so that the color of the link and its identifier changes to be consistent with the color of the corresponding security situation level, so that the security situation of the link is displayed in a visual form.

[0336] (5) At the same time, the evaluation results of this link are quantified.

[0337] (6) The quantitative processing results are displayed in the form of a plane coordinate axis. In the coordinate axis, the horizontal axis represents time and the vertical axis represents the security level. The broken line formed by connecting the security situation of different periods of this link shows the development trend of its security situation over time.

[0338] (7) The key link is associated with its basic information. The basic information of the link, such as production date, manufacturer, rated parameters, etc., can be viewed through the basic information menu on the visual display page.

[0339] (8) Data in all links are managed by the data management module and database.

[0340] Figure 2 The composition of the reactor primary circuit pressure boundary safety situation display system is described. Figure 3 Describes the system's software architecture diagram; Figure 4 The two-dimensional visualization of the safety situation of the reactor's primary circuit pressure boundary is described (in the figure, the color of the main gate valve sealing surface in link A is yellow-red, indicating a dangerous situation; the color of the main coolant pipeline in link B is blue, indicating a normal situation).

[0341] An application embodiment of the present invention provides a computer device, which includes a memory and a processor. The memory stores a computer program. When the computer program is executed by the processor, the processor executes the steps of the method.

[0342] An application embodiment of the present invention provides a computer-readable storage medium storing a computer program. When the computer program is executed by a processor, the processor executes the steps of the method.

[0343] An application embodiment of the present invention provides an information data processing terminal, which includes a system.

[0344] 1. Specific application fields or related products of the present invention.

[0345] 2. Relevant evidence of the technical effects obtained by the embodiments of the present invention.

[0346] It should be noted that the embodiments of the present invention can be implemented by hardware, software, or a combination of software and hardware. The hardware part can be implemented using dedicated logic; the software part can be stored in a memory and executed by an appropriate instruction execution system, such as a microprocessor or dedicated design hardware. It can be understood by a person of ordinary skill in the art that the above-mentioned devices and methods can be implemented using computer executable instructions and / or contained in a processor control code, such as a carrier medium such as a disk, CD or DVD-ROM, a programmable memory such as a read-only memory (firmware), or a data carrier such as an optical or electronic signal carrier. Such code is provided on the carrier medium. The device and its modules of the present invention can be implemented by hardware circuits such as very large-scale integrated circuits or gate arrays, semiconductors such as logic chips, transistors, etc., or programmable hardware devices such as field programmable gate arrays, programmable logic devices, etc., can also be implemented by software executed by various types of processors, and can also be implemented by a combination of the above-mentioned hardware circuits and software, such as firmware.

[0347] The above description is only a specific implementation mode of the present invention, but the protection scope of the present invention is not limited thereto. Any modifications, equivalent substitutions and improvements made by any technician familiar with the technical field within the technical scope disclosed by the present invention and within the spirit and principle of the present invention should be covered by the protection scope of the present invention.

Claims

1. A method for assessing the safety situation of a reactor primary circuit pressure boundary, characterized in that: include: S1, data collection based on characteristic variables of a key link of the pressure-bearing boundary; S2, preprocessing the characteristic variable data collected in a key link and converting them into a unified data type; S3, inputting the processed data into the safety status evaluation model corresponding to the link; performing calculations through the model to obtain the safety status evaluation result of the link; S4, associating the evaluation result with the link and its identifier, so that the color of the link and its identifier changes to be consistent with the color of the corresponding security situation level, so that the security situation of the link is displayed in a visual form; S5, at the same time, the evaluation results of this link are quantified; S6, the quantitative processing results are displayed in the form of a plane coordinate axis; in the coordinate axis, the horizontal axis represents time, and the vertical axis represents the security level; the broken line formed by connecting the security situation of different periods of this link shows the development trend of its security situation over time; S7, associate the key link with its basic information. In the visual display page, the basic information of the link can be displayed through the basic information menu, such as production date, manufacturer, rated parameters, etc.; S8, data in all links are managed by data management module and database.

2. The method for assessing the safety situation of the pressure boundary of the reactor primary circuit according to claim 1, characterized in that: The method for constructing the pressure boundary safety situation map includes: (1) Determine the key links that affect the safety of the pressure boundary: The safety state of the pressure-bearing boundary is determined by the integrity of the pressure-bearing boundary; the weak links of the pressure-bearing boundary determine the integrity and safety state of the pressure-bearing boundary; these weak links are key links that affect the safety state of the pressure-bearing boundary; the weak links of the pressure-bearing boundary will also be different according to the different reactor types of the nuclear power plant, and the key links can be determined according to the actual composition of the pressure-bearing boundary; the weak links of the pressure-bearing boundary in the present invention include key equipment or parts such as the reactor sealing surface, the reactor control rod tube seat, the reactor outlet, the reactor inlet, the main gate valve outlet, the main gate valve sealing surface, the steam generator U-tube, the steam generator inlet, the steam generator outlet, the main coolant pump sealing surface, and the main check valve; The security situation of the pressure-bearing border reflects the overall security status of each key link of the pressure-bearing border; (2) Constructing a visualization of the pressure boundary of the primary coolant circuit of a nuclear reactor 1) Use visualization graphics software to construct visualization graphics of the pressure boundary; 2) The visualization graphics must include all key links of the pressure-bearing boundary; 3) Visual graphics include elements such as the main equipment of the pressure boundary and the connections between equipment, pipelines and other objects; 4) Set vertical arrows with certain width and height at the key links of the pressure boundary visualization graphics; 5) The colors of each key link and its symbolic arrow are dynamically changeable, and their colors are associated with the safety status information of the key link; the colors of the key link and its symbolic arrow show the safety status of the key link for users to observe; 6) The constructed visualization graphics should be vivid, intuitive and easy to observe; 7) Visual graphics can be drawn using software such as Unity 3D; (3) Establish a safety status evaluation model for key links: The method of establishing the equipment safety status evaluation model is to use the relevant factors affecting the equipment reliability and technical performance as the input variables of the evaluation model, and the output of the evaluation model is the equipment safety level, which represents the safety situation; For specific methods and steps, please refer to the "Establishment Method of Key Link Safety Status Evaluation Model" later; (4) Information association: The evaluation results of the safety status evaluation model of each key link of the pressure boundary are associated with the colors of the corresponding key links and their iconic arrows in the pressure boundary visualization graphics; The colors of the key links and their iconic arrows in the visualization are blue, green, yellow-green, yellow-red and red. These five colors represent reliable, safe, basically safe, at risk and unsafe states respectively; the situations corresponding to these five states are: "Reliable" corresponds to "favorable situation"; "Safety" corresponds to "normal situation"; "Basic security" corresponds to "potential threat situation"; "There is a risk" corresponds to "dangerous situation"; "Unsafe" corresponds to "high-risk situation"; (5) Safety status display The safety status display adopts three visual display modes: the iconic arrow color display; the key link color display; the coordinate chart displays the historical development trend; (6) Security situation of pressured borders The safety status of each key link of the pressure boundary together constitutes the nuclear safety situation map of the pressure boundary, showing the overall safety situation of the pressure boundary; according to the safety situation of the pressure boundary, users can grasp the safety situation of the entire pressure boundary and the current weak safety links.

3. The method for assessing the safety situation of the pressure boundary of the reactor primary circuit according to claim 2, characterized in that: The security status display includes: 1) Iconic arrow display According to the information association, the current safety status of the key link is displayed by a symbolic arrow set on the link; the current color of the symbolic arrow shows the current safety status of the key link; 2) The key link itself is displayed In the pressure boundary visualization graph, the key links are associated with their current safety status evaluation results and displayed in corresponding colors; The color of the key link is consistent with the color of its iconic arrow, and the two together show the safety status of the key link; 3) Coordinate graphs show historical development trends The coordinate graph shows the relationship between the safety status of each key link and time, and is the historical development trend of the safety status of the key links.

4. The method for assessing the safety situation of the pressure boundary of the reactor primary circuit according to claim 1, characterized in that: The method for establishing the safety status evaluation model of the key link of the pressure-bearing boundary comprises the following steps: 1) Analyze the factors affecting the safety status of key links in the pressure boundary Including inherent factors, environmental factors, usage factors, installation or replacement factors, aging factors, maintenance factors, repair factors, testing and inspection factors, service life and other factors; Comprehensively analyze the impact of various influencing factors on equipment reliability and technical performance from multiple aspects such as equipment design, processing technology, operating environment, usage, maintenance, etc. 2) Determine the input variables of the key link safety status evaluation model The above-mentioned influencing factors are defined as input variables for safety status assessment, including inherent factor variables, environmental factor variables, usage factor variables, installation factor variables, aging factor variables, maintenance factor variables, repair factor variables, detection and inspection factor variables, service life variables, and failure variables; The values ​​of each input variable are divided into different levels, such as "no impact", "impact" and "significant impact". The specific level division is determined according to the actual impact degree and characteristics; 3) Determine the output variables of the key link safety status evaluation model The output variables are defined as the safety degree level (SSD), including favorable situation (FS), normal situation (NS), potential threat situation (TS), unfavorable situation (AS), dangerous situation (DS), and unsafe situation (LS); The output variable SSD is quantified in the interval [-1,1] and divided into six levels to represent the changing trend of the link safety status over time.

5. The method for assessing the safety situation of the pressure boundary of the reactor primary circuit according to claim 1, characterized in that: The method for dividing the values ​​of the safety status evaluation variables of the key links of the pressure-bearing boundary includes: 1) Intrinsic factor variable (VS) If there are no defects in design and manufacturing, the value is "normal"; if there are defects or shortcomings, it is classified as "defective" according to the degree of the defect; 2) Environmental variables (VE) According to the degree of impact of the environment on the equipment, it is divided into "no impact", "impact" and "significant impact" levels; 3) Using factor variables (VU) According to factors such as usage mode and intensity, they are divided into "no impact", "impact" and "significant impact"; 4) Installation or replacement factor variables (VI) If the installation is correct, the value is "No impact", if the installation is defective, the value is "Impact"; 5) Aging factor variable (VA) According to the degree of aging, it is divided into "no aging", "some aging", "moderate aging" and "severe aging"; 6) Maintenance factor variable (VM) According to the maintenance status, it is divided into "well maintained", "averagely maintained" and "no maintenance"; 7) Maintenance factor variable (VR) According to the maintenance status, it is divided into "thorough maintenance", "incomplete maintenance" and "poor maintenance"; 8) Detection and verification factor variables (VC) According to the inspection results, the system can be divided into "careful inspection", "general inspection" and "no inspection"; 9) Variable life (VL) According to the life cycle stage, it is divided into "early stage", "middle stage", "late stage" and "final stage"; 10) Fault variable (VF) If cracks or leaks occur, the value is "unsafe"; 11) Other factor variables (VO) According to the actual impact, it is divided into "no impact", "impact" and "significant impact".

6. A reactor primary circuit pressure boundary safety situation assessment system implementing the reactor primary circuit pressure boundary safety situation assessment method as claimed in any one of claims 1 to 5, characterized in that: include: Visualization display module: The visualization display module intuitively displays the safety status of each key link of the nuclear reactor primary coolant system in the form of visual graphics. The visualization graphics are drawn through Unity 3D. Key link safety status evaluation model management module: This module contains the safety status evaluation model of each key link of the pressure boundary; using this evaluation model, according to the relevant information of each key link input by the system, complete the current safety status analysis of each key link, and associate the analysis results with the corresponding link of the pressure boundary, and display them in a visual form in the pressure boundary visualization structure diagram; Data management module: This module manages the data of each key link of the pressure boundary, including historical data. In this module, you can query the historical data of each key link within a specified time range to intuitively understand the historical safety situation of each key link and its development and change trend; User management module: This module manages system users; system users are divided into two categories: administrators and ordinary users; administrators have system maintenance management authority, and ordinary users have nuclear power plant operation management authority, that is, system usage management authority.

7. The reactor primary circuit pressure boundary safety situation assessment system according to claim 6, characterized in that: The visualization display module is used to display the visualization structure diagram of the pressure boundary of the reactor primary coolant system; in the visualization structure diagram, each key link that may affect the integrity of the pressure boundary is marked with color and color identifiers, and the color of each link and its identifier represents the corresponding safety status of the link; all key links and their identifiers in the visualization structure diagram of the reactor primary coolant system are combined to form the overall safety situation diagram of the reactor primary coolant pressure boundary; through the safety situation diagram, the current overall safety situation of the pressure boundary and the safety status of the key links can be directly observed and understood; in this way, the nuclear power operation management personnel can view the current overall safety situation of the pressure boundary and the safety situation of each key link at any time through the management system; Based on the safety situation diagram of the pressure boundary, nuclear power operation managers can observe and grasp the weak links of the pressure boundary, estimate the safety status of each key link of the pressure boundary, and take appropriate disposal decisions and measures in time before problems occur in the pressure boundary, so as to prevent and eliminate the hidden dangers existing in the pressure boundary; By using the data management module, nuclear power operation managers can observe the current overall safety situation of the pressure boundary and the safety status of each key link at any time through the system display terminal equipment, and grasp the weak links of the pressure boundary; newly appointed operation managers can also use the data management module to understand the development and changes of the safety situation of each key link of the pressure boundary over time, and grasp the safety situation of the pressure boundary and the safety status of each key link.

8. A computer-readable storage medium storing a computer program, which, when executed by a processor, causes the processor to execute the steps of the method for assessing the safety situation of the pressure boundary of the primary circuit of a reactor as claimed in any one of claims 1 to 5.

9. An information data processing terminal, comprising the reactor primary circuit pressure boundary safety situation assessment system according to any one of claims 6 to 7.

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