Dynamic risk assessment method, device and computer equipment for nuclear power unit shutdown and reactor trip

Abstract

The present application relates to the field of nuclear power plant industrial safety technology, and discloses a dynamic risk assessment method, device and computer equipment for nuclear power unit shutdown and reactor trip. Among them, the dynamic risk assessment method for nuclear power unit shutdown and reactor trip includes: establishing a benchmark model of the unit shutdown and reactor trip fault tree; in the benchmark model, setting different states of the unit through room events, and qualitatively analyzing to obtain different cut set lists under different states; obtaining the real-time operation state and real-time reliability level state, and training the benchmark model to update the benchmark model to obtain a dynamic model of the unit shutdown and reactor trip fault tree; based on the dynamic model, obtaining the dynamic assessment of the shutdown and reactor trip risk under different unit states and the dynamic ranking of equipment importance. Through the present application, the problem that dynamic risk assessment cannot be carried out and the importance of equipment cannot be updated in a timely manner under different states of the unit is solved, and the dynamic assessment of the shutdown and reactor trip risk of the nuclear power unit and the dynamic ranking of equipment importance are realized.

Description

Technical Field

[0001] The present application relates to the technical field of nuclear power plant industrial safety, and particularly to a method, device and computer equipment for dynamically evaluating the shutdown and reactor trip risks of nuclear power units. Background Art

[0002] A nuclear power unit is a basic power generation unit composed of a reactor and its supporting steam turbine generator set, as well as systems and facilities required to maintain their normal operation and ensure safety. Since there are many devices in a nuclear power unit, the damage of key sensitive devices will cause the unit to shut down and trip the reactor. Therefore, key sensitive devices are usually identified and managed to further manage the problems of unit shutdown and reactor trip caused by the failure of failed devices.

[0003] At present, the equipment management solution, based on the key sensitive equipment management system, determines the elimination priority of a single failed device through qualitative analysis, and eliminates or mitigates the failed device according to the elimination priority. This management method can reduce the number of shutdowns and reactor trips to a certain extent. However, in different states of the unit, dynamic risk assessment cannot be carried out and the importance of equipment cannot be updated in a timely manner, resulting in prominent problems of unplanned shutdowns and reactor trips, and relatively high shutdown and reactor trip risks.

[0004] In view of the problem that in the related technology, dynamic assessment of the shutdown and reactor trip risks of nuclear power units and dynamic ranking of the importance of equipment cannot be carried out, no effective solution has been proposed yet. Summary of the Invention

[0005] In this embodiment, a method, device, computer equipment and storage medium for dynamically evaluating the shutdown and reactor trip risks of nuclear power units are provided to solve the problem that in the related technology, dynamic assessment of the shutdown and reactor trip risks of nuclear power units and dynamic ranking of the importance of equipment cannot be carried out.

[0006] In the first aspect, in this embodiment, a method for dynamically evaluating the shutdown and reactor trip risks of nuclear power units is provided, and the method includes:

[0007] Establish a benchmark model of the unit shutdown and reactor trip fault tree; in the benchmark model, set different states of the unit through house events, and perform qualitative analysis according to the logical values of the house events in different states to obtain different cut set lists;

[0008] Obtain the real-time operation state of the unit and the real-time reliability level state of the equipment, train the benchmark model through the real-time operation state and the real-time reliability level state, and update the benchmark model to obtain the dynamic model of the unit shutdown and reactor trip fault tree;

[0009] Based on the dynamic model, a dynamic assessment of the shutdown and reactor trip risks under different unit states and a dynamic ranking of equipment importance are obtained.

[0010] In some of these embodiments, different states of the unit are set through house events, including:

[0011] Preset different states of the unit under different power levels and different operating conditions;

[0012] Under different states of the unit, the unit is controlled through the house events.

[0013] In some of these embodiments, after performing qualitative analysis according to the logical values of the house events in different states to obtain different cut set lists, it further includes:

[0014] Exclude equipment tests, online isolation maintenance of standby equipment, or failure states of standby equipment through the set of second-order cut set basic events in the qualitative analysis results of the benchmark model, so as to dynamically identify and manage key sensitive equipment.

[0015] In some of these embodiments, the benchmark model is trained through the real-time operating state and the real-time reliability level state, and the dynamic model of the unit shutdown and reactor trip fault tree is obtained by updating the benchmark model, including:

[0016] Input the real-time operating state and the real-time reliability level state into the benchmark model for calculation to obtain a calculation result;

[0017] Formulate an optimization plan for the benchmark model according to the calculation result;

[0018] Update the benchmark model through the optimization plan to obtain the dynamic model of the unit shutdown and reactor trip fault tree.

[0019] In some of these embodiments, formulating the optimization plan for the benchmark model according to the calculation result includes:

[0020] Based on the application process of the benchmark model, compare the shutdown and reactor trip risks of the unit evaluated in real time quantitatively with the shutdown and reactor trip risks corresponding to the benchmark model to obtain the comparison result of the shutdown and reactor trip risks;

[0021] Formulate an optimization plan according to the comparison result and modify the benchmark model in the shutdown and reactor trip fault tree benchmark model library.

[0022] In some of these embodiments, after obtaining the dynamic assessment of the shutdown and reactor trip risks under different unit states and the dynamic ranking of equipment importance based on the dynamic model, it further includes:

[0023] Determine the processing priorities of equipment defects based on the dynamic assessment and the dynamic ranking, and process the equipment defects one by one.

[0024] In some of these embodiments, determining the processing priorities of equipment defects based on the dynamic assessment and the dynamic ranking, and processing the equipment defects one by one includes:

[0025] Evaluate the defect or technical problem, judge the degree of influence of the defect or technical problem on the equipment availability, so as to change the equipment reliability data;

[0026] Input the changed equipment reliability data into the model for calculation, and obtain the shutdown and reactor trip risks of the unit in the presence of the defect or technical problem;

[0027] Judge whether the shutdown and reactor trip risks exceed the allowed range. If they exceed the range, immediately process the defect or technical problem; if they do not exceed the range, perform a priority ranking based on the importance of the equipment involved in the defect or technical problem and the existing defects or technical problems of the unit, and process them one by one.

[0028] In a second aspect, in this embodiment, a device for dynamically evaluating the shutdown and reactor trip risks of a nuclear power unit is further provided. The device includes:

[0029] The establishment module is used to establish a benchmark model of the shutdown and reactor trip fault tree of the unit; in the benchmark model, set different states of the unit through house events, and perform qualitative analysis according to the logical values of the house events in different states to obtain different cut set lists;

[0030] The training module is used to obtain the real-time operation state of the unit and the real-time reliability level state of the equipment, and train the benchmark model through the real-time operation state and the real-time reliability level state to update the benchmark model to obtain the dynamic model of the shutdown and reactor trip fault tree of the unit;

[0031] The application module is used to obtain the dynamic assessment of the shutdown and reactor trip risks and the dynamic ranking of the equipment importance under different unit states based on the dynamic model.

[0032] In a third aspect, in this embodiment, a computer device is provided, including a memory, a processor, and a computer program stored on the memory and executable on the processor. When the processor executes the computer program, it implements the method for dynamically evaluating the shutdown and reactor trip risks of a nuclear power unit described in the first aspect above.

[0033] Fourthly, in this embodiment, a storage medium is provided, on which a computer program is stored, and when the program is executed by a processor, the method for dynamically evaluating the shutdown and reactor trip risks of a nuclear power unit described in the first aspect above is implemented.

[0034] Compared with the related technologies, the method, device and computer equipment for dynamically evaluating the shutdown and reactor trip risks of a nuclear power unit provided in this embodiment establish a benchmark model of the shutdown and reactor trip fault tree of the unit. The benchmark model sets different states of the unit through house events, and performs qualitative analysis according to the logical values of the house events in different states to obtain different cut set lists; obtains the real-time operating state of the unit and the real-time reliability level state of the equipment, calculates the benchmark model through the real-time operating state and the real-time reliability level state, and obtains the dynamic evaluation of the shutdown and reactor trip risks and the dynamic ranking of the equipment importance in different unit states; and updates the benchmark model, solving the problem that dynamic risk assessment cannot be carried out and the importance of the equipment cannot be updated in time in different states of the unit, and realizing the dynamic evaluation of the shutdown and reactor trip risks of the nuclear power unit and the dynamic ranking of the equipment importance.

[0035] The details of one or more embodiments of the present application are set forth in the following drawings and description, so that the other features, objects and advantages of the present application become more concise and understandable. BRIEF DESCRIPTION OF THE DRAWINGS

[0036] The drawings described herein are used to provide a further understanding of the present application, and constitute a part of the present application. The illustrative embodiments and descriptions of the present application are used to explain the present application and do not constitute an improper limitation of the present application. In the drawings:

[0037] Figure 1 is the hardware structure block diagram of the terminal device of the method for dynamically evaluating the shutdown and reactor trip risks of a nuclear power unit provided in an embodiment of the present application;

[0038] Figure 2 is the flowchart of the method for dynamically evaluating the shutdown and reactor trip risks of a nuclear power unit provided in an embodiment of the present application;

[0039] Figure 3 is the preferred flowchart of the method for dynamically evaluating the shutdown and reactor trip risks of a nuclear power unit provided in an embodiment of the present application;

[0040] Figure 4 is the model optimization flowchart of the method for dynamically evaluating the shutdown and reactor trip risks of a nuclear power unit provided in an embodiment of the present application;

[0041] Figure 5 is the structure block diagram of the device for dynamically evaluating the shutdown and reactor trip risks of a nuclear power unit provided in an embodiment of the present application.

[0042] In the figure: 10, establishment module; 20, training module; 30, application module. Detailed implementation manners

[0043] To understand the purpose, technical solution and advantages of the present application more clearly, the present application will be described and illustrated below in conjunction with the accompanying drawings and embodiments.

[0044] Unless otherwise defined, the technical terms or scientific terms involved in the present application shall have the general meaning understood by those with ordinary skills in the technical field to which the present application belongs. In the present application, words such as "a", "one", "a kind of", "the", "these" and the like do not indicate a limitation in quantity, and they can be singular or plural. The terms "including", "comprising", "having" and any variants thereof involved in the present application are intended to cover non-exclusive inclusion; for example, a process, method, system, product or device including a series of steps or modules (units) is not limited to the listed steps or modules (units), but may include unlisted steps or modules (units), or may include other steps or modules (units) inherent in these processes, methods, products or devices. The terms "connected", "coupled" and the like involved in the present application are not limited to physical or mechanical connections, but may include electrical connections, whether directly or indirectly. The "multiple" involved in the present application means two or more. "And / or" describes the association relationship of associated objects and indicates that three relationships may exist. For example, "A and / or B" may mean: A exists alone, A and B exist simultaneously, and B exists alone. Usually, the character " / " indicates that the objects associated before and after are in an "or" relationship. The terms "first", "second", "third" and the like involved in the present application are only used to distinguish similar objects and do not represent a specific sorting of the objects.

[0045] In the method embodiment provided in this embodiment, it can be executed on a terminal, a computer or a similar computing device. For example, it runs on a terminal. Figure 1 It is the hardware structure block diagram of the terminal of the dynamic risk assessment method for the shutdown and reactor trip of a nuclear power unit in this embodiment. As Figure 1 shown, the terminal may include one or more ( Figure 1 only one is shown in Figure 1 the figure) processors 102 and a memory 104 for storing data. Among them, the processor 102 may include, but is not limited to, a processing device such as a microprocessor MCU or a programmable logic device FPGA. The above terminal may further include a transmission device 106 for communication functions and an input / output device 108. Those of ordinary skill in the art can understand that Figure 1 the structure shown inFigure 1 The different configurations shown.

[0046] The memory 104 can be used to store computer programs, for example, software programs and modules of application software, such as the computer program corresponding to the dynamic risk assessment method for the shutdown and reactor trip of a nuclear power unit in this embodiment. The processor 102 executes various functional applications and data processing by running the computer program stored in the memory 104, that is, implements the above method. The memory 104 may include high-speed random access memory and may also include non-volatile memory, such as one or more magnetic storage devices, flash memory, or other non-volatile solid-state memories. In some instances, the memory 104 may further include a memory remotely set relative to the processor 102, and these remote memories can be connected to the terminal through a network. Examples of the above network include but are not limited to the Internet, enterprise intranet, local area network, mobile communication network, and their combinations.

[0047] The transmission device 106 is used to receive or send data via a network. The above network includes the wireless network provided by the communication provider of the terminal. In one instance, the transmission device 106 includes a network adapter (abbreviated as NIC), which can be connected to other network devices through a base station and thus communicate with the Internet. In one instance, the transmission device 106 can be a radio frequency (RF) module, which is used to communicate with the Internet wirelessly.

[0048] In this embodiment, a dynamic risk assessment method for the shutdown and reactor trip of a nuclear power unit is provided. Figure 2 It is the flowchart of the dynamic risk assessment method for the shutdown and reactor trip of a nuclear power unit in this embodiment, as Figure 2 shown, and the process includes the following steps:

[0049] Step S210, establish a benchmark model of the fault tree for the shutdown and reactor trip of the unit; in the benchmark model, different states of the unit are set through room type events, and qualitative analysis is performed according to the logical values of the room type events in different states to obtain different cut set lists.

[0050] Specifically, a benchmark model for analyzing the shutdown and reactor trip events of the unit is established based on fault tree analysis. Fault tree analysis analyzes the phenomena, causes, and results of an accident by depicting the directed logic tree of the accident occurrence, so as to find measures to prevent the accident. The fault tree consists of three types of fault events, namely top events, basic events, and bottom events. In each branch of the fault tree, the upper-layer fault event is the result of the lower-layer fault event, and the lower-layer event is the cause of the upper-layer fault event, and the logical relationship between events is represented by logical gates.

[0051] It should be noted that the above benchmark model fully estimates different configuration states that the unit may present within different power level operating ranges and different operating conditions of the unit, and the logical values of the room type events in the fault tree can be "true" or "false". By setting these logical values, qualitative analysis of the unit under different configuration states can be carried out.

[0052] Furthermore, since different states of the unit are fully considered in the benchmark model of the fault tree and different configuration states of the unit are specified through room type events, the unit can be controlled according to the logical switches of the room type events. For example, the feedwater regulation of the main feedwater regulation system ARE includes bypass feedwater valve regulation and main path feedwater valve regulation. Set the logic of the room type event "unit operating power is greater than 20% of the rated power" to true, and the logic of the room type event "unit operating power is less than or equal to 20% of the rated power" to false. When the unit power is greater than 20% of the rated power, the branch event "power is less than 20%, bypass regulating valve opening is too large" where it is located will be blocked. Therefore, the event of too large an opening of the ARE bypass regulating valve will not appear in the top event analysis cut set.

[0053] Step S220: Obtain the real-time operating state of the unit and the real-time reliability level state of the equipment, and train the benchmark model through the real-time operating state and the real-time reliability level state to update the benchmark model to obtain the dynamic model of the unit's shutdown and reactor trip fault tree.

[0054] Specifically, the real-time operating state of the unit includes the power level of the unit, equipment state, maintenance and test state, etc., and the real-time reliability level state is determined by the equipment reliability database and the actual degradation situation of the equipment. The equipment reliability database collects demand data, operation data, fault data, etc. of different equipment categories, and statistically processes the data to obtain the reliability parameters of each equipment category.

[0055] Furthermore, in the equipment reliability database, the real-time reliability level state of the equipment is obtained according to the change situation of the equipment state. Input the real-time operating state and the real-time reliability level state into the shutdown and reactor trip fault tree benchmark model library, and then calculate through the fault tree benchmark model to obtain the real-time evaluated shutdown and reactor trip risk result of the unit, and formulate an optimization plan for the benchmark model according to the real-time risk assessment result, so as to update the benchmark model to obtain the dynamic model of the unit's shutdown and reactor trip fault tree.

[0056] Step S230: Based on the dynamic model, obtain the dynamic assessment of the shutdown and reactor trip risk under different unit states and the dynamic ranking of equipment importance.

[0057] Specifically, under different unit states, qualitative and quantitative analyses of the unit can be carried out through the dynamic model of the unit shutdown and reactor trip fault tree. Among them, qualitative analysis under different states is achieved through the logical values of the house events, and different cut set lists are obtained. A cut set is a set of bottom events that necessarily cause the top event to occur. Therefore, the dynamic ranking of the importance of different equipment can be judged according to the frequency of each bottom event appearing in the cut set. On the basis of qualitative analysis, quantitative analysis is carried out on the unit equipment failure data through the dynamic model, and the probability of the occurrence of the shutdown and reactor trip fault is calculated, so as to dynamically evaluate the shutdown and reactor trip risk.

[0058] Through the above steps, the reference model of the unit shutdown and reactor trip fault tree is established in this embodiment; in the reference model, different states of the unit are set through the house events, and qualitative analysis is carried out according to the logical values of the house events under different states to obtain different cut set lists; the real-time operation state of the unit and the real-time reliability level state of the equipment are obtained, and the reference model is trained through the real-time operation state and the real-time reliability level state to update the reference model to obtain the dynamic model of the unit shutdown and reactor trip fault tree; based on the dynamic model, the dynamic evaluation of the shutdown and reactor trip risk under different unit states and the dynamic ranking of the equipment importance are obtained.

[0059] The current equipment management solution, based on the key sensitive equipment management system, determines the elimination priority of single-failure equipment through qualitative analysis methods, and eliminates or mitigates the failure equipment according to the elimination priority. This method can reduce the number of shutdowns and reactor trips to a certain extent. However, under different states of the unit, dynamic risk assessment cannot be carried out and the importance of equipment cannot be updated in a timely manner, resulting in the prominent problem of unplanned shutdowns and reactor trips, and the resulting shutdown and reactor trip risk is relatively high. In this embodiment, by establishing the reference model of the unit shutdown and reactor trip fault tree, qualitative and quantitative analyses of the unit under different states can be further realized on the basis of the existing technology, and the reference model is trained according to the real-time operation state and the real-time reliability level state, and the dynamic model of the unit shutdown and reactor trip fault tree is updated. Therefore, based on the dynamic model, the dynamic evaluation of the shutdown and reactor trip risk under different unit states and the dynamic ranking of the equipment importance can be obtained. It can be seen that through fault tree analysis and dynamic model, the problem that dynamic risk assessment cannot be carried out and the importance of equipment cannot be updated in a timely manner under different states of the unit is solved.

[0060] In some of these embodiments, setting different states of the unit through the house events includes the following steps:

[0061] Preset different states of the unit under different power levels and different operating conditions;

[0062] Under different states of the unit, control the unit through the house events.

[0063] Specifically, within the operating range of the unit at 0 - 100% power level, as well as under different operating conditions such as testing and on-line maintenance, different configuration states that the unit may exhibit are fully predicted.

[0064] It should be noted that the logical value of the house event in the fault tree can be "true" or "false". By setting this logical value, qualitative analysis of the unit under different configuration states can be achieved, and further dynamic assessment of the risk of reactor trip and shutdown can be carried out.

[0065] Through this embodiment, different configuration states of the unit are set according to different power levels and operating conditions, and under different configuration states, qualitative analysis of the unit is carried out through the logical value of the house event, thereby solving the problem that the importance of different equipment cannot be dynamically sorted.

[0066] In some of these embodiments, after qualitative analysis is carried out according to the logical value of the house event in different states to obtain different cut set lists, the following steps are further included:

[0067] By means of the set of bottom events of the second-order cut sets in the qualitative analysis result of the benchmark model, equipment testing, on-line isolation maintenance of standby equipment, or the failure state of standby equipment are excluded, thereby dynamically identifying and managing key sensitive equipment.

[0068] Specifically, in the benchmark model of the reactor trip and shutdown fault tree, qualitative analysis in different states is achieved through the logical value of the house event to obtain different cut set lists, so as to timely update the key sensitive equipment that causes reactor trip and shutdown faults in different states. For example, when the unit is operating at a high power state, the failure of the bypass regulating valve of the main feed water system does not cause reactor trip and shutdown. At this time, this regulating valve is not a key sensitive equipment. If the unit is operating at a low power state, the failure of the main feed water regulating valve will cause reactor shutdown. At this time, this regulating valve is a key sensitive equipment. Thus, during the normal power operation of the unit, the failure of a certain equipment does not cause reactor trip and shutdown. However, under conditions such as equipment testing, on-line isolation maintenance of standby equipment, or the failure of standby equipment, the single failure of the equipment will cause reactor trip and shutdown, and thus this equipment will become a dynamic key sensitive equipment. Therefore, it is necessary to dynamically update the list of key sensitive equipment in different states.

[0069] It should be noted that key sensitive equipment refers to equipment whose single failure can cause reactor shutdown, unit shutdown, power reduction, and large power fluctuations in a nuclear power plant, and plays a key role in the nuclear power plant system. Therefore, by identifying and managing key sensitive equipment, the safety of the equipment in the nuclear power plant system can be effectively improved.

[0070] Through this embodiment, the unit equipment in different states is qualitatively analyzed according to the logical values of the room type events, and then different cut set lists are obtained, which can dynamically identify and manage key sensitive equipment excluding equipment tests, online isolation maintenance of standby equipment or the failure state of standby equipment, so as to realize the dynamic management of equipment on the basis of focusing on managing the key systems and equipment, and prevent the inaccurate identification of key sensitive equipment in different states, further improving the reliability, safety and economic benefits of the nuclear power plant system equipment.

[0071] In some of these embodiments, the reference model is trained through the real-time operating state and the real-time reliability level state, and the dynamic model of the unit shutdown and reactor trip fault tree is obtained by updating the reference model, including the following steps:

[0072] Input the real-time operating state and the real-time reliability level state into the reference model for calculation to obtain a calculation result;

[0073] Formulate an optimization plan for the reference model according to the calculation result;

[0074] Update the reference model through the optimization plan to obtain the dynamic model of the unit shutdown and reactor trip fault tree.

[0075] Specifically, the obtained real-time operating state includes different unit configuration states such as the power level and test state of the unit, and in the equipment reliability database, the change of the equipment state is converted into the real-time reliability level of the equipment according to the reliability parameters and then input into the shutdown and reactor trip fault tree reference model library, which can dynamically evaluate the shutdown and reactor trip risks in real time.

[0076] Furthermore, based on the training process of the reference model, an optimization plan for the reference model is formulated according to the shutdown and reactor trip risks dynamically evaluated in real time, and the reference model is updated, so as to obtain the dynamic model of the unit shutdown and reactor trip fault tree, thereby continuously improving the reference model.

[0077] Through this embodiment, the real-time operating state and the real-time reliability level state are input into the reference model, the reference model is trained and an optimization plan is formulated according to the shutdown and reactor trip risks evaluated in real time, thereby continuously improving the reference model. While obtaining the dynamic model of the unit shutdown and reactor trip fault tree, the optimized model is more adapted to the actual application process, and the shutdown and reactor trip risks evaluated dynamically are more accurate.

[0078] In some of these embodiments, formulating an optimization plan for the reference model according to the calculation result includes the following steps:

[0079] Based on the application process of the reference model, compare the shutdown and reactor trip risks of the unit quantitatively evaluated in real time with the shutdown and reactor trip risks corresponding to the reference model to obtain the comparison result of the shutdown and reactor trip risks;

[0080] Formulate an optimization plan based on the comparison results and modify the benchmark model in the shutdown and reactor trip fault tree benchmark model library.

[0081] Specifically, during the application process of the benchmark model of the fault tree, quantitatively analyze the real-time shutdown and reactor trip risks of the unit group through a computer, compare them with the shutdown and reactor trip risks corresponding to the benchmark model, determine the problems existing in the benchmark model according to the comparison results, and then formulate a specific optimization plan for the fault tree model. Further, correspondingly modify the original benchmark model to make it more adaptable to the actual application unit.

[0082] Through this embodiment, in actual application, by comparing the real-time dynamic shutdown and reactor trip risks with the shutdown and reactor trip risks corresponding to the benchmark model, discover the problems in the application process of the benchmark model and optimize them, so as to improve the accuracy of the shutdown and reactor trip risks output by the model.

[0083] In some of these embodiments, after obtaining the dynamic assessment of the shutdown and reactor trip risks and the dynamic ranking of the equipment importance under different unit states based on the dynamic model, the following steps are further included:

[0084] Determine the priority of equipment defect handling according to the dynamic assessment and the dynamic ranking, and handle the equipment defects one by one.

[0085] Specifically, obtain the dynamic assessment of the shutdown and reactor trip risks through the dynamic model, so as to dynamically assess the contribution of each equipment defect to the risk, and then determine the handling priority.

[0086] It should be noted that since the occurrence of equipment defects related to shutdown and reactor trip will increase the shutdown and reactor trip risks, by handling multiple equipment defects in the order of importance, the problem of limited resources in the nuclear power plant can be alleviated.

[0087] Through this embodiment, calculate the dynamic assessment of the shutdown and reactor trip risks and the dynamic ranking of the equipment importance according to the dynamic model, further evaluate the handling priority of the risks existing in different equipment defects, and thus orderly handle each equipment defect according to the priority. In the case of limited resources in the nuclear power plant, the procedure for handling equipment defects is optimized, and the efficiency of handling equipment defects and the utilization rate of nuclear power plant resources are improved.

[0088] In some of these embodiments, determining the priority of equipment defect handling according to the dynamic assessment and the dynamic ranking and handling the equipment defects one by one include the following steps:

[0089] Evaluate the defect or technical problem, judge the degree of influence of the defect or technical problem on the equipment availability, and thus change the equipment reliability data;

[0090] Input the changed equipment reliability data into the model for calculation to obtain the shutdown and reactor trip risks of the unit in the presence of defects or technical problems.

[0091] Judge whether the shutdown and reactor trip risks exceed the permitted range. If they exceed the range, immediately handle the defect or problem. If they do not exceed the range, prioritize according to the importance of the equipment involved in the defect or technical problem and the existing defects or technical problems of the unit, and handle them one by one.

[0092] Specifically, equipment reliability data is an important basis for nuclear power plants to carry out safety evaluations and reliability-related work such as probabilistic safety analysis, maintenance rules, and reliability-centered maintenance. Its accuracy will directly affect the results of the dynamic assessment of shutdown and reactor trip risks.

[0093] Furthermore, obtaining the shutdown and reactor trip risks of the unit in the corresponding state based on the changed equipment reliability data, then judging whether the shutdown and reactor trip risks exceed the permitted range, and carrying out corresponding processing can improve the accuracy of the dynamic assessment of shutdown and reactor trip risks, thereby enhancing the reliability of equipment defect handling.

[0094] The following describes and illustrates this embodiment through preferred embodiments.

[0095] Figure 3 is the preferred flowchart of the dynamic assessment method for the shutdown and reactor trip risks of the nuclear power unit in this embodiment. As Figure 3 shown, the dynamic assessment method for the shutdown and reactor trip risks includes the following steps:

[0096] Step S310, establish a benchmark model of the shutdown and reactor trip fault tree of the unit; in the benchmark model, set different states of the unit through house events, and conduct qualitative analysis according to the logical values of the house events in different states to obtain different cut set lists.

[0097] Step S320, exclude equipment tests, online isolation maintenance of standby equipment, or the failure state of standby equipment through the set of second-order cut set bottom events in the qualitative analysis results of the benchmark model to dynamically identify and manage key sensitive equipment.

[0098] Step S330, obtain the real-time operating state of the unit and the real-time reliability level state of the equipment, and train the benchmark model through the real-time operating state and the real-time reliability level state to update the benchmark model to obtain a dynamic model of the shutdown and reactor trip fault tree of the unit.

[0099] Step S340, based on the dynamic model, obtain the dynamic assessment of the shutdown and reactor trip risks in different unit states and the dynamic ranking of equipment importance.

[0100] Step S350: Determine the priority of equipment defect handling based on dynamic assessment and dynamic sorting, and handle equipment defects one by one.

[0101] Figure 4 It is the model optimization flowchart of the dynamic assessment method for the shutdown and reactor trip risk of a nuclear power unit in this embodiment. As Figure 4 shown, the dynamic assessment method for the shutdown and reactor trip risk includes the following steps:

[0102] Steps S410 to S430: In the equipment reliability database, convert the equipment status change situation into the real-time reliability level of the equipment according to the reliability parameters.

[0103] Steps S440 to S450: Input the real-time reliability level of the equipment and the unit configuration status into the shutdown and reactor trip fault tree benchmark model library.

[0104] Step S460: Update the benchmark model to obtain the dynamic model of the unit's shutdown and reactor trip fault tree.

[0105] Step S470: Based on the application process of the fault tree dynamic model, compare the shutdown and reactor trip risk of the unit evaluated in real time quantitatively with the shutdown and reactor trip risk corresponding to the benchmark model to obtain the comparison result of the shutdown and reactor trip risk;

[0106] Step S480: Develop an optimization plan according to the comparison result and modify the benchmark model in the shutdown and reactor trip fault tree benchmark model library.

[0107] Through the above preferred embodiments, as Figure 4 shown, the benchmark model is trained according to the real-time operation status of the unit and the real-time reliability level status of the equipment, and then based on the shutdown and reactor trip risk assessment result in the actual application process of the model, the problems of the benchmark model are found and the model is optimized, so as to continuously improve the benchmark model to obtain the dynamic model, thereby realizing each dynamic process of the unit and the equipment.

[0108] Based on the qualitative analysis of the benchmark model of the unit's shutdown and reactor trip fault tree, exclude the equipment test, online isolation maintenance of standby equipment or the failure state of standby equipment according to the set of second-order cut set bottom events, so as to realize the dynamic identification and management of key sensitive equipment. Further, determine the priority of equipment defect handling according to the results of dynamic assessment and dynamic sorting, and then handle equipment defects one by one in the order of importance. It can dynamically update the shutdown and reactor trip risk and the sorting of equipment importance, and timely and accurately handle relevant equipment defects, solve the problem that the importance of equipment cannot be sorted under different states and its timeliness affects the order of equipment defect handling, reduce the occurrence of unplanned shutdown and reactor trip faults, and reduce the shutdown and reactor trip risk.

[0109] It should be noted that the steps shown in the above process or the flowchart of the accompanying drawings can be executed in a computer system such as a set of computer-executable instructions. And although the logical order is shown in the flowchart, in some cases, the steps shown or described can be executed in a different order than here.

[0110] In this embodiment, a dynamic assessment device for the shutdown and reactor trip risks of a unit is also provided. This device is used to implement the above-mentioned embodiment and preferred implementation manners, and those that have been described will not be repeated here. The following terms such as "module", "unit", "sub-unit", etc. can be a combination of software and / or hardware that can achieve a predetermined function. Although the devices described in the following embodiments are preferably implemented in software, implementation in hardware, or a combination of software and hardware is also possible and contemplated.

[0111] Figure 5 is the structural block diagram of the dynamic assessment device for the shutdown and reactor trip risks of the nuclear power unit in this embodiment, as Figure 5 shown, this device includes: a building module 10, a training module 20, and an application module 30;

[0112] The building module 10 is used to build a benchmark model of the shutdown and reactor trip fault tree of the unit; in the benchmark model, different states of the unit are set through the top event, and qualitative analysis is performed according to the logical values of the top event in different states to obtain different cut set lists;

[0113] The training module 20 is used to obtain the real-time operating state of the unit and the real-time reliability level state of the equipment, and train the benchmark model through the real-time operating state and the real-time reliability level state to update the benchmark model to obtain a dynamic model of the shutdown and reactor trip fault tree of the unit;

[0114] The application module 30 is used to obtain the dynamic assessment of the shutdown and reactor trip risks under different unit states and the dynamic ranking of the equipment importance based on the dynamic model.

[0115] In some of these embodiments, this device further includes a dynamic identification module, which is used to exclude the equipment test, online isolation maintenance of standby equipment, or failure state of standby equipment according to the set of bottom events of the second-order cut sets in the qualitative analysis results of the benchmark model, so as to dynamically identify and manage key sensitive equipment.

[0116] In some of these embodiments, the above application module is further used for:

[0117] Through the dynamic model, quantitatively evaluate the shutdown and reactor trip risks of the unit at different powers in real time;

[0118] When the power grid requires the unit to operate at a reduced power, select the power level at which the unit operates with low risk.

[0119] In some of these embodiments, the above application module is further configured to:

[0120] Through a dynamic model, quantitatively evaluate the risk of unit shutdown and reactor trip in real time;

[0121] Based on the real-time shutdown and reactor trip risk and the unavailability of equipment during daily maintenance or tests, determine the risk-based daily maintenance or test plan.

[0122] In some of these embodiments, the device further includes a processing module, configured to determine the priority of equipment defect handling according to dynamic evaluation and dynamic ranking, and handle equipment defects one by one.

[0123] It should be noted that the above-mentioned each module can be a functional module or a program module, and can be implemented either by software or by hardware. For the modules implemented by hardware, the above-mentioned each module can be located in the same processor; or the above-mentioned each module can also be located in different processors in any combination form.

[0124] In this embodiment, a computer device is further provided, including a memory and a processor. A computer program is stored in the memory, and the processor is configured to run the computer program to execute the steps in any one of the above method embodiments.

[0125] Optionally, the above computer device may further include a transmission device and input / output devices. Among them, the transmission device is connected to the above processor, and the input / output devices are connected to the above processor.

[0126] It should be noted that the specific examples in this embodiment can refer to the examples described in the above embodiments and optional implementation manners, and will not be repeated in this embodiment.

[0127] In addition, in combination with the method for dynamic evaluation of the shutdown and reactor trip risk of a nuclear power unit provided in the above embodiments, a storage medium can also be provided to implement it in this embodiment. A computer program is stored on the storage medium; when the computer program is executed by a processor, it implements any one of the above methods for dynamic evaluation of the shutdown and reactor trip risk of a nuclear power unit.

[0128] It should be understood that the specific embodiments described here are only used to explain this application, rather than to limit it. According to the embodiments provided in this application, all other embodiments obtained by those of ordinary skill in the art without creative efforts fall within the protection scope of this application.

[0129] Obviously, the accompanying drawings are only some examples or embodiments of the present application. For those of ordinary skill in the art, the present application can also be applied to other similar situations based on these drawings without creative efforts. Additionally, it can be understood that although the work done during the development process may be complex and time-consuming, for those of ordinary skill in the art, certain design, manufacturing, or production changes based on the technical content disclosed in the present application are only routine technical means and should not be regarded as insufficient disclosure of the present application.

[0130] The term "embodiment" in the present application means that the specific features, structures, or characteristics described in connection with the embodiments can be included in at least one embodiment of the present application. The phrase appears in various positions in the specification and does not necessarily mean the same embodiment, nor does it mean being independent or alternative to other embodiments and mutually exclusive. Those of ordinary skill in the art can clearly or implicitly understand that the embodiments described in the present application can be combined with other embodiments without conflict.

[0131] The above-described embodiments merely represent several implementation manners of the present application. The description is relatively specific and detailed, but it should not be construed as a limitation on the scope of patent protection. It should be noted that for those of ordinary skill in the art, without departing from the concept of the present application, several modifications and improvements can still be made, and these all fall within the protection scope of the present application. Therefore, the protection scope of the present application shall be subject to the appended claims.

Claims

1. A dynamic risk assessment method for nuclear power unit shutdown and reactor trip, characterized in that The method includes: Establishing a benchmark model of the unit shutdown and reactor trip fault tree; in the benchmark model, setting different states of the unit through house events, and performing qualitative analysis according to the logical values of the house events in different states to obtain different cut set lists; Among them, setting different states of the unit through house events includes: presetting different states of the unit at different power levels and under different operating conditions; controlling the unit through the house events in different states of the unit; Obtaining the real-time operating state of the unit and the real-time reliability level state of the equipment, training the benchmark model through the real-time operating state and the real-time reliability level state, and updating the benchmark model to obtain the dynamic model of the unit shutdown and reactor trip fault tree; Among them, training the benchmark model through the real-time operating state and the real-time reliability level state, and updating the benchmark model to obtain the dynamic model of the unit shutdown and reactor trip fault tree includes: inputting the real-time operating state and the real-time reliability level state into the benchmark model for calculation to obtain a calculation result; formulating an optimization plan for the benchmark model according to the calculation result; updating the benchmark model through the optimization plan to obtain the dynamic model of the unit shutdown and reactor trip fault tree; Among them, formulating an optimization plan for the benchmark model according to the calculation result includes: based on the application process of the benchmark model, comparing the shutdown and reactor trip risks of the unit evaluated in real time quantitatively with the shutdown and reactor trip risks corresponding to the benchmark model to obtain a comparison result of the shutdown and reactor trip risks; formulating an optimization plan according to the comparison result and modifying the benchmark model in the benchmark model library of the shutdown and reactor trip fault tree; obtaining a dynamic assessment of the shutdown and reactor trip risks and a dynamic ranking of the equipment importance under different unit states based on the dynamic model.

2. The dynamic risk assessment method for nuclear power unit shutdown and reactor trip according to claim 1, characterized in that After performing qualitative analysis according to the logical values of the house events in different states to obtain different cut set lists, it further includes: Excluding equipment tests, online isolation maintenance of standby equipment, or failure states of standby equipment through the set of second-order cut set basic events in the qualitative analysis results of the benchmark model to dynamically identify and manage key sensitive equipment.

3. The dynamic risk assessment method for nuclear power unit shutdown and reactor trip according to claim 1, characterized in that After obtaining a dynamic assessment of the shutdown and reactor trip risks and a dynamic ranking of the equipment importance under different unit states based on the dynamic model, it further includes: Determining the treatment priorities of equipment defects according to the dynamic assessment and the dynamic ranking, and handling the equipment defects one by one.

4. The dynamic risk assessment method for nuclear power unit shutdown and reactor trip according to claim 3, characterized in that, Determining the treatment priorities of equipment defects according to the dynamic assessment and the dynamic ranking, and handling the equipment defects one by one includes: Evaluating the defects or technical problems, judging the influence degree of the defects or technical problems on the equipment availability, so as to change the equipment reliability data; Inputting the changed equipment reliability data into the model for calculation to obtain the shutdown and reactor trip risks of the unit in the presence of the defects or technical problems; Determine whether the shutdown and reactor trip risk exceeds the permitted range. If it exceeds the range, immediately handle the defect or technical problem. If it does not exceed the range, perform a priority ranking based on the importance of the equipment involved in the defect or technical problem and the existing defects or technical problems of the unit, and handle them one by one.

5. A dynamic assessment device for the shutdown risk of a nuclear power unit, characterized in that, The device includes: an establishment module, a training module, and an application module; The establishment module is used to establish a benchmark model of the unit's shutdown and reactor trip fault tree; in the benchmark model, set different states of the unit through house events, and perform qualitative analysis according to the logical values of the house events in different states to obtain different cut set lists; The establishment module is further used to preset different states of the unit under different power levels and different operating conditions; control the unit through the house events in different states of the unit; The training module is used to obtain the real-time operating state of the unit and the real-time reliability level state of the equipment, train the benchmark model through the real-time operating state and the real-time reliability level state, and update the benchmark model to obtain the dynamic model of the unit's shutdown and reactor trip fault tree; The training module is further used to input the real-time operating state and the real-time reliability level state into the benchmark model for calculation to obtain a calculation result; formulate an optimization plan for the benchmark model according to the calculation result; update the benchmark model through the optimization plan to obtain the dynamic model of the unit's shutdown and reactor trip fault tree; The training module is further used to compare the shutdown and reactor trip risk of the unit evaluated in real time quantitatively with the shutdown and reactor trip risk corresponding to the benchmark model based on the application process of the benchmark model to obtain a comparison result of the shutdown and reactor trip risk; formulate an optimization plan according to the comparison result, and modify the benchmark model in the shutdown and reactor trip fault tree benchmark model library; The application module is used to obtain the dynamic assessment of the shutdown and reactor trip risk and the dynamic ranking of the equipment importance under different unit states based on the dynamic model.

6. A computer device, comprising a memory and a processor, characterized in that, A computer program is stored in the memory, and the processor is set to run the computer program to execute the steps of the dynamic assessment method for the shutdown and reactor trip risk of a nuclear power unit according to any one of claims 1 to 5.

7. A computer-readable storage medium having a computer program stored thereon, characterized in that, When the computer program is executed by the processor, the steps of the dynamic assessment method for the shutdown and reactor trip risk of a nuclear power unit according to any one of claims 1 to 5 are implemented.

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