CN114743703A - Reliability analysis method, device, equipment and storage medium for nuclear power station unit - Google Patents
Reliability analysis method, device, equipment and storage medium for nuclear power station unit Download PDFInfo
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- CN114743703A CN114743703A CN202210357362.0A CN202210357362A CN114743703A CN 114743703 A CN114743703 A CN 114743703A CN 202210357362 A CN202210357362 A CN 202210357362A CN 114743703 A CN114743703 A CN 114743703A
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- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
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- Y04S—SYSTEMS INTEGRATING TECHNOLOGIES RELATED TO POWER NETWORK OPERATION, COMMUNICATION OR INFORMATION TECHNOLOGIES FOR IMPROVING THE ELECTRICAL POWER GENERATION, TRANSMISSION, DISTRIBUTION, MANAGEMENT OR USAGE, i.e. SMART GRIDS
- Y04S10/00—Systems supporting electrical power generation, transmission or distribution
- Y04S10/50—Systems or methods supporting the power network operation or management, involving a certain degree of interaction with the load-side end user applications
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Abstract
The application relates to a reliability analysis method, a device, equipment and a storage medium for a nuclear power station unit. The method comprises the following steps: acquiring a fault tree model of the nuclear power station unit; acquiring running state information of nuclear power equipment corresponding to a bottom event of the fault tree model; and when the nuclear power equipment fails, calculating the fault tree model layer by layer according to actual failure data of the nuclear power equipment and the sequence from the bottom layer to the top layer to obtain a power generation reliability index of the nuclear power station unit. According to the method, after some nuclear power equipment fails, the influence of the nuclear power equipment failure on the power generation reliability index of the nuclear power station unit can be quantitatively analyzed through the logical relation between events provided by the fault tree model, the participation degree of human factors is reduced, the analysis result is more objective, and the accuracy of the analysis result is improved.
Description
Technical Field
The present application relates to the technical field of safety management of nuclear power plants, and in particular, to a method, an apparatus, a device, and a storage medium for analyzing reliability of a unit of a nuclear power plant.
Background
For the daily operation of a nuclear power plant, the power generation reliability of a nuclear power plant unit is one of the most important indexes. In the traditional technology, a qualitative method is generally adopted to estimate the influence on the power generation reliability of a nuclear power station unit after the failure of relevant nuclear power equipment, and the accuracy of an analysis result is low due to the lack of a means of quantitative analysis and evaluation.
Disclosure of Invention
The application provides a reliability analysis method, a device, equipment and a storage medium for a nuclear power station unit.
In a first aspect, an embodiment of the present application provides a method for analyzing reliability of a nuclear power plant unit, including:
acquiring a fault tree model of the nuclear power station unit;
acquiring running state information of nuclear power equipment corresponding to a bottom event of the fault tree model;
and when the nuclear power equipment fails, calculating the fault tree model layer by layer according to actual failure data of the nuclear power equipment and the sequence from the bottom layer to the top layer to obtain a power generation reliability index of the nuclear power station unit.
In a second aspect, an embodiment of the present application provides a reliability analysis apparatus for a nuclear power plant unit, including:
the first acquisition module is used for acquiring a fault tree model of the nuclear power station unit;
the second acquisition module is used for acquiring the running state information of the nuclear power equipment corresponding to the bottom event of the fault tree model;
and the processing module is used for calculating the fault tree model layer by layer according to the actual failure data of the nuclear power equipment and the sequence from the bottom layer to the top layer when the nuclear power equipment fails to obtain the power generation reliability index of the nuclear power station unit.
In a third aspect, an embodiment of the present application provides an electronic device, which includes a memory and a processor, where the memory stores a computer program, and the processor implements the steps of the method for analyzing the reliability of the nuclear power plant unit provided in the first aspect of the embodiment of the present application when executing the computer program.
In a fourth aspect, an embodiment of the present application provides a computer-readable storage medium, on which a computer program is stored, where the computer program, when executed by a processor, implements the steps of the method for analyzing reliability of a nuclear power plant unit provided in the first aspect of the embodiment of the present application.
According to the technical scheme provided by the embodiment of the application, the fault tree model of the nuclear power station unit is obtained, the running state information of the nuclear power equipment corresponding to the bottom event of the fault tree model is obtained, and when the nuclear power equipment fails, the fault tree model is calculated layer by layer according to the actual failure data of the nuclear power equipment and the sequence from the bottom layer to the top layer, so that the power generation reliability index of the nuclear power station unit is obtained. That is to say, after some nuclear power equipment fails, the influence of the nuclear power equipment failure on the power generation reliability index of the nuclear power station unit can be quantitatively analyzed through the logical relationship between events provided by the fault tree model, the participation degree of human factors is reduced, the analysis result is more objective, and the accuracy of the analysis result is improved.
Drawings
Fig. 1 is a schematic flowchart of a method for analyzing reliability of a nuclear power plant unit according to an embodiment of the present application;
FIG. 2 is a schematic flow chart of the screening of key nuclear power plants provided in the embodiments of the present application;
fig. 3 is a schematic structural diagram of a reliability analysis apparatus for a nuclear power plant unit according to an embodiment of the present application;
fig. 4 is a schematic structural diagram of an electronic device according to an embodiment of the present application.
Detailed Description
In order to make the objects, technical solutions and advantages of the present application more apparent, the technical solutions in the embodiments of the present application are further described in detail by the following embodiments in combination with the accompanying drawings. It should be understood that the specific embodiments described herein are merely illustrative of the present application and are not intended to limit the present application.
It should be noted that the execution subject of the following method embodiments may be a reliability analysis device of a nuclear power plant unit, and the device may be implemented as part or all of an electronic device by software, hardware, or a combination of software and hardware. Alternatively, the electronic device may be various types of devices, and the electronic device may perform information interaction with an external device. Alternatively, the electronic device may be any one of a PDA (personal digital assistant), a PAD (tablet computer), a PMP (portable multimedia player), a vehicle-mounted terminal (e.g., a car navigation terminal), a mobile phone, a PC (personal computer), and the like. The method embodiments described below are described by taking as an example that the execution subject is an electronic device.
Fig. 1 is a schematic flow chart of a method for analyzing the reliability of a nuclear power plant unit according to an embodiment of the present application. As shown in fig. 1, the method may include:
and S101, obtaining a fault tree model of the nuclear power station unit.
Wherein the fault tree model may include: top event, middle event, and bottom event. The top event can be various fault phenomena of the nuclear power station unit, each top event corresponds to a fault tree and serves as a first node of the fault tree, and for example, the top event of the fault tree model can be reactor shutdown, steam turbine shutdown, large-amplitude power reduction and the like. The intermediate event is a process node in a fault path of the nuclear power plant unit, for example, the intermediate event of a top event "reactor shutdown" may be high water temperature of a bearing of the reactor cooling pump 1A. The bottom event is the smallest component causing various fault phenomena of the nuclear power plant unit, namely the basic component which cannot be continuously expanded and has faults in the fault tree, and serves as a tail node of the fault tree, for example, the bottom event of the middle event "the water temperature of the bearing of the reactor cooling pump 1A is high" can be a mechanical fault of a main pump, the operation of a temperature sensor is failed, and the like.
In practical application, a fault tree model of the nuclear power plant unit can be constructed in advance. The method comprises the steps of constructing a top event, a middle event and a tail event of a fault tree model, and forming the fault tree model of the nuclear power station unit according to a logic relation of fault occurrence. For example, taking the top event "reactor trip" as an example, a fault tree model of a reactor trip of a nuclear power plant is drawn by combining automatic trip logic, manual trip logic and failure mode analysis.
In general, all nodes of the fault tree model are faults, and faults occurring at child nodes are fault reasons of faults occurring at parent nodes. The logic gates between the parent node and the child node may include, but are not limited to, and gates, or gates, not gates, nand gates, and the like. For example, an and gate is defined such that a parent node will fail only if all devices corresponding to child nodes fail. An or gate is defined as a parent node that fails when a device corresponding to at least one child node fails. The NOT gate definition is used for indicating that the parent node fails when the device corresponding to the child node does not fail. A nand gate functions similarly to a combination of and not gates to indicate that a parent node fails when at least one of the child nodes does not fail.
And S102, obtaining the running state information of the nuclear power equipment corresponding to the bottom event of the fault tree model.
The operation state information is used for representing whether the nuclear power equipment normally operates, namely whether the nuclear power equipment is in fault or is in a preventive maintenance stage needs to be determined. A nuclear power plant may be determined to be malfunctioning when the nuclear power plant fails or is in a preventive maintenance phase. In practical application, whether the nuclear power equipment is in a preventive maintenance stage or not can be determined through preset maintenance plan information.
S103, when the nuclear power equipment fails, calculating the fault tree model layer by layer according to actual failure data of the nuclear power equipment and the sequence from the bottom layer to the top layer to obtain a power generation reliability index of the nuclear power plant unit.
Optionally, the power generation reliability indicator may include a reactor shutdown risk, a turbine shutdown risk, and/or a power droop risk that causes a magnitude to exceed a preset ratio. Of course, other risks for characterizing a nuclear power plant unit failure may also be included.
When the nuclear power equipment is determined to be out of order based on the operation state information of the nuclear power equipment, calculation can be carried out from the bottom layer of the fault tree model to the top layer by layer according to the logical relation between events based on the actual failure data of the nuclear power equipment so as to determine the probability of the top layer event of the nuclear power unit caused by the failure of the nuclear power equipment, and therefore the power generation reliability index of the nuclear power unit is obtained. For example, after a certain nuclear power equipment fails, the shutdown risk value of the nuclear power plant unit can be calculated through the logical relationship provided by the actual failure data of the nuclear power equipment and the fault tree model. Therefore, the influence degree of the failure of the nuclear power equipment on the nuclear power station unit can be obtained, and a basis is provided for a series of subsequent maintenance decisions.
In practical applications, there may be a case, for example, a certain event set causing a power reduction with a magnitude greater than 10% also has a certain influence on the shutdown of the steam turbine, and at this time, in order to improve the accuracy of the determined power generation reliability index of the nuclear power plant unit, in the process of calculating the power generation reliability index, a redundant bottom event in the fault tree model needs to be removed, so that repeated calculation of the same bottom event is avoided.
In an embodiment, optionally, when the power generation reliability index exceeds a preset threshold, the information of the nuclear power plant is highlighted. Specifically, the information of the nuclear power equipment can be highlighted and displayed on the current interface, and the information of the nuclear power equipment can also be output in a voice broadcasting mode so as to remind maintenance personnel to pay attention to the nuclear power equipment.
After the nuclear power equipment fails, the influence of the nuclear power equipment failure on the failure risk of the nuclear power station unit is determined through the logical relation between the actual failure data of the nuclear power equipment and the events provided by the fault tree model, so that preventive maintenance, state monitoring strategy formulation, nuclear power equipment maintenance window determination, maintenance scheme formulation, decision of system and equipment change modification, decision basis for judging whether important equipment enters overhaul in advance when being degraded and the like can be facilitated.
According to the reliability analysis method for the nuclear power station unit, the fault tree model of the nuclear power station unit is obtained, the running state of the nuclear power equipment corresponding to the bottom event of the fault tree model is obtained, and when the nuclear power equipment fails, the fault tree model is calculated layer by layer according to the actual failure data of the nuclear power equipment from the bottom layer to the top layer, so that the power generation reliability index of the nuclear power station unit is obtained. That is to say, after some nuclear power equipment fails, the influence of the nuclear power equipment failure on the power generation reliability index of the nuclear power station unit can be quantitatively analyzed through the logical relationship between the events provided by the fault tree model, the participation degree of human factors is reduced, the analysis result is more objective, and the accuracy of the analysis result is improved.
In an embodiment, optionally, the power generation reliability index may be further analyzed according to a preset quantization strategy to determine whether a deviation between the power generation reliability index and the quantization index exceeds a preset range; and if so, correcting the fault tree model.
Wherein the quantization strategy comprises at least one of the following parameters: industry experience feedback information and a probabilistic risk assessment model.
That is, in order to further improve the accuracy of the reliability analysis result of the nuclear power plant unit, the power generation reliability index calculated by the fault tree model may be compared with the industry experience feedback information or the evaluation result information fed back by the probability risk evaluation model, and if the deviation between the power generation reliability index and the industry experience feedback information or the evaluation result information is large, the logic of the fault tree model or the initial failure probability of each bottom event in the fault tree model may be corrected according to the historical fault record of the nuclear power plant unit, so that the fault tree model better conforms to the actual operation condition of the nuclear power plant. The quantitative index can be industry experience feedback information or evaluation result information fed back by a probability risk evaluation model. Subsequently, the reliability of the nuclear power plant unit can be analyzed according to the corrected fault tree model.
In this embodiment, the calculated power generation reliability index may be analyzed through a preset quantization strategy, and the fault tree model of the nuclear power plant unit is corrected based on the analysis result, so that the fault tree model better conforms to the actual operation condition of the nuclear power plant, and the accuracy of the reliability analysis result of the nuclear power plant unit after the nuclear power equipment fails is further improved.
In one embodiment, key nuclear power equipment which has a large influence on the power generation reliability index of the nuclear power plant unit can be screened out for key monitoring, so that the normal operation of the nuclear power plant unit is ensured. For this purpose, optionally, on the basis of the foregoing embodiment, as shown in fig. 2, the method may further include:
s201, determining the importance of each bottom event in the fault tree model.
And the importance is used for representing the influence degree on the power generation reliability index of the nuclear power station unit. The number of bottom events in the fault tree model is large, but the occurrence of all the bottom events can not bring large influence on the occurrence of the top event of the fault tree model, that is, some bottom events have large influence on the power generation reliability index of the nuclear power plant unit, and some bottom events have small influence on the power generation reliability index of the nuclear power plant unit. In this embodiment, a bottom event having a large influence on the power generation reliability index of the nuclear power plant unit needs to be focused.
Specifically, first, the initial failure probability of each bottom event in the fault tree model is obtained. In the embodiment of the application, each base event can be respectively assigned with the initial failure probability according to the expert experience and the size of the failure probability.
Then, acquiring a historical failure record, respectively counting the occurrence frequency of each bottom event based on the historical failure record, and determining the corrected failure probability of each bottom event according to the occurrence frequency of each bottom event. For any base event, the correction failure probability of the base event is positively correlated with the occurrence frequency of the base event, that is, if the occurrence frequency of a base event is more, the correction failure probability is higher, and conversely, if the occurrence frequency of a base event is less, the correction failure probability is lower.
And then, determining the target failure probability of each bottom event according to the initial failure probability and the corrected failure probability of each bottom event. Here, the product of the initial failure probability and the corrected failure probability may be determined as the target failure probability of each bottom event, or the corrected failure probability may be used to update the initial failure probability, so as to obtain the target failure probability of each bottom event.
And further, calculating the fault tree model layer by layer according to the target failure probability of each bottom event and the sequence from the bottom layer to the top layer to obtain the importance of each bottom event. After the target failure probability of each bottom event is obtained, the influence degree of each bottom event on the top event can be sequentially calculated according to the logical relationship provided by the fault tree model, so that the importance of each bottom event is obtained.
And S202, determining target base events from the base events according to the importance degrees.
The target bottom event is a bottom event which greatly influences the power generation reliability index of the nuclear power station unit. After the importance of each event is obtained, the event with the importance greater than or equal to the preset value can be determined as a target event, and the events can be sorted according to the importance, and the target event is determined based on the sorting result.
And S203, outputting the information of the key nuclear power equipment corresponding to the target base event.
After the target bottom event is determined, the nuclear power equipment corresponding to the target bottom event can be determined as key nuclear power equipment, and information of the key nuclear power equipment is output. The failure of the key nuclear power equipment has a great influence on the power generation reliability index of the nuclear power plant unit, so the key nuclear power equipment needs to be monitored in a key mode.
Further, key nuclear power equipment is monitored in a key mode, when the key nuclear power equipment is monitored to have a fault, solution information corresponding to the fault can be searched from a preset database, and the solution information is sent to terminal equipment where maintenance personnel are located. Thus, maintenance personnel can carry out fault treatment on the key nuclear power equipment according to the solution information.
In this embodiment, the importance of each event in the fault tree model can be determined, a target event is determined from each event according to each importance, and information of the key nuclear power equipment corresponding to the target event is output, so that the key nuclear power equipment which has a large influence on the power generation reliability index of the nuclear power plant unit is obtained, and further the key nuclear power equipment is subjected to key monitoring, so that normal operation of the nuclear power plant unit is ensured, and potential safety hazards are effectively avoided.
Fig. 3 is a schematic structural diagram of a reliability analysis apparatus for a nuclear power plant unit according to an embodiment of the present application. As shown in fig. 3, the apparatus may include: a first acquisition module 301, a second acquisition module 302 and a processing module 303.
Specifically, the first obtaining module 301 is configured to obtain a fault tree model of the nuclear power plant unit;
the second obtaining module 302 is configured to obtain operation state information of the nuclear power equipment corresponding to a bottom event of the fault tree model;
the processing module 303 is configured to perform layer-by-layer calculation on the fault tree model according to the actual failure data of the nuclear power equipment and the sequence from the bottom layer to the top layer when the nuclear power equipment fails, so as to obtain a power generation reliability index of the nuclear power plant unit.
The reliability analysis device for the nuclear power station unit, provided by the embodiment of the application, acquires a fault tree model of the nuclear power station unit and acquires running state information of nuclear power equipment corresponding to a bottom event of the fault tree model, and when the nuclear power equipment fails, calculates the fault tree model layer by layer according to actual failure data of the nuclear power equipment from the bottom layer to the top layer to obtain a power generation reliability index of the nuclear power station unit. That is to say, after some nuclear power equipment fails, the influence of the nuclear power equipment failure on the power generation reliability index of the nuclear power station unit can be quantitatively analyzed through the logical relationship between the events provided by the fault tree model, the participation degree of human factors is reduced, the analysis result is more objective, and the accuracy of the analysis result is improved.
Optionally, the power generation reliability indicator comprises a reactor shutdown risk, a turbine shutdown risk, and/or a derating risk that causes a magnitude to exceed a preset proportion.
On the basis of the foregoing embodiment, optionally, the apparatus further includes: the device comprises a first determining module, a second determining module and an output module.
Specifically, the first determining module is configured to determine importance of each bottom event in the fault tree model; the importance is used for representing the influence degree on the power generation reliability index of the nuclear power station unit;
the second determining module is used for determining target bottom events from the bottom events according to the importance degrees;
and the output module is used for outputting the information of the key nuclear power equipment corresponding to the target base event.
On the basis of the foregoing embodiment, optionally, the first determining module is specifically configured to obtain an initial failure probability of each bottom event in the fault tree model; acquiring a historical failure record, respectively counting the occurrence frequency of each bottom event based on the historical failure record, and determining the corrected failure probability of each bottom event according to the occurrence frequency of each bottom event; determining the target failure probability of each bottom event according to the initial failure probability and the corrected failure probability of each bottom event; and calculating the fault tree model layer by layer according to the target failure probability of each bottom event and the sequence from the bottom layer to the top layer to obtain the importance of each bottom event.
On the basis of the foregoing embodiment, optionally, the apparatus further includes: and a searching module.
Specifically, the searching module is used for monitoring the key nuclear power equipment, searching solution information corresponding to a fault from a preset database when the key nuclear power equipment fails, and sending the solution information to the terminal equipment where a maintenance worker is located.
On the basis of the foregoing embodiment, optionally, the apparatus further includes: the device comprises a quantitative analysis module and a correction module.
Specifically, the quantitative analysis module is configured to analyze the power generation reliability index according to a preset quantitative strategy to determine whether a deviation between the power generation reliability index and the quantitative index exceeds a preset range;
the correction module is used for correcting the fault tree model when the quantitative analysis module determines that the deviation between the power generation reliability index and the quantitative index exceeds a preset range;
wherein the quantization strategy comprises at least one of the following parameters: industry experience feedback information and a probabilistic risk assessment model.
On the basis of the foregoing embodiment, optionally, the apparatus further includes: and a display module.
Specifically, the display module is used for displaying the information of the nuclear power equipment in a highlighted manner when the power generation reliability index exceeds a preset threshold value.
In one embodiment, an electronic device is provided, the internal structure of which may be as shown in FIG. 4. The electronic device includes a processor, memory, and a network interface and database connected by a system bus. Wherein the processor of the electronic device is configured to provide computing and control capabilities. The memory of the electronic equipment comprises a nonvolatile storage medium and an internal memory. The non-volatile storage medium stores an operating system, a computer program, and a database. The internal memory provides an environment for the operation of an operating system and computer programs in the non-volatile storage medium. The network interface of the electronic device is used for connecting and communicating with an external terminal through a network. The database of the electronic equipment is used for storing data related to the reliability analysis process of the nuclear power plant unit. The computer program is executed by a processor to implement a method for analyzing the reliability of a nuclear power plant unit.
Those skilled in the art will appreciate that the configuration shown in fig. 4 is a block diagram of only a portion of the configuration associated with the present application, and does not constitute a limitation on the electronic device to which the present application is applied, and a particular electronic device may include more or less components than those shown in the drawings, or combine certain components, or have a different arrangement of components.
In one embodiment, an electronic device is provided, comprising a memory and a processor, the memory having a computer program stored therein, the processor implementing the following steps when executing the computer program:
acquiring a fault tree model of the nuclear power station unit;
acquiring running state information of nuclear power equipment corresponding to a bottom event of the fault tree model;
and when the nuclear power equipment fails, calculating the fault tree model layer by layer according to actual failure data of the nuclear power equipment and the sequence from the bottom layer to the top layer to obtain a power generation reliability index of the nuclear power station unit.
Optionally, the power generation reliability indicator comprises a reactor trip risk, a turbine trip risk, and/or a derating risk that causes a magnitude to exceed a preset proportion.
In one embodiment, the processor, when executing the computer program, further performs the steps of: determining the importance of each bottom event in the fault tree model; the importance is used for representing the influence degree on the power generation reliability index of the nuclear power station unit; determining target base events from the base events according to the importance degrees; and outputting the information of the key nuclear power equipment corresponding to the target bottom event.
In one embodiment, the processor, when executing the computer program, further performs the steps of: acquiring the initial failure probability of each bottom event in the fault tree model; acquiring a historical failure record, respectively counting the occurrence frequency of each bottom event based on the historical failure record, and determining the corrected failure probability of each bottom event according to the occurrence frequency of each bottom event; determining the target failure probability of each bottom event according to the initial failure probability and the corrected failure probability of each bottom event; and calculating the fault tree model layer by layer according to the target failure probability of each bottom event and the sequence from the bottom layer to the top layer to obtain the importance of each bottom event.
In one embodiment, the processor, when executing the computer program, further performs the steps of: monitoring the key nuclear power equipment, searching solution information corresponding to the fault from a preset database when the key nuclear power equipment fails, and sending the solution information to terminal equipment where maintenance personnel are located.
In one embodiment, the processor, when executing the computer program, further performs the steps of: analyzing the power generation reliability index according to a preset quantization strategy to determine whether the deviation between the power generation reliability index and the quantization index exceeds a preset range; if so, correcting the fault tree model; wherein the quantization strategy comprises at least one of the following parameters: industry experience feedback information and a probabilistic risk assessment model.
In one embodiment, the processor, when executing the computer program, further performs the steps of: and when the power generation reliability index exceeds a preset threshold value, the information of the nuclear power equipment is prominently displayed.
In one embodiment, a computer-readable storage medium is provided, having a computer program stored thereon, which when executed by a processor, performs the steps of:
acquiring a fault tree model of the nuclear power station unit;
acquiring running state information of nuclear power equipment corresponding to a bottom event of the fault tree model;
and when the nuclear power equipment fails, calculating the fault tree model layer by layer according to actual failure data of the nuclear power equipment and the sequence from the bottom layer to the top layer to obtain a power generation reliability index of the nuclear power station unit.
The reliability analysis device, the equipment and the storage medium for the nuclear power plant unit provided in the above embodiments can execute the reliability analysis method for the nuclear power plant unit provided in any embodiment of the present application, and have corresponding functional modules and beneficial effects for executing the method. For technical details that are not described in detail in the above embodiments, reference may be made to a method for analyzing reliability of a nuclear power plant unit provided in any embodiment of the present application.
All possible combinations of the technical features of the above embodiments may not be described for the sake of brevity, but should be considered as within the scope of the present disclosure as long as there is no contradiction between the combinations of the technical features.
The above-mentioned embodiments only express several embodiments of the present application, and the description thereof is more specific and detailed, but not construed as limiting the scope of the present application. It should be noted that, for a person skilled in the art, several variations and modifications can be made without departing from the concept of the present application, which falls within the scope of protection of the present application. Therefore, the protection scope of the present patent shall be subject to the appended claims.
Claims (10)
1. A reliability analysis method for a nuclear power station unit is characterized by comprising the following steps:
acquiring a fault tree model of the nuclear power station unit;
acquiring running state information of nuclear power equipment corresponding to a bottom event of the fault tree model;
and when the nuclear power equipment fails, calculating the fault tree model layer by layer according to actual failure data of the nuclear power equipment and the sequence from the bottom layer to the top layer to obtain a power generation reliability index of the nuclear power station unit.
2. The method of claim 1, wherein the power generation reliability indicator comprises a reactor trip risk, a turbine trip risk, and/or a derating risk that causes a magnitude to exceed a preset ratio.
3. The method of claim 1, further comprising:
determining the importance of each bottom event in the fault tree model; the importance is used for representing the influence degree on the power generation reliability index of the nuclear power station unit;
determining target base events from the base events according to the importance degrees;
and outputting the information of the key nuclear power equipment corresponding to the target base event.
4. The method of claim 3, wherein determining the importance of each base event in the fault tree model comprises:
acquiring the initial failure probability of each bottom event in the fault tree model;
acquiring a historical failure record, respectively counting the occurrence frequency of each bottom event based on the historical failure record, and determining the corrected failure probability of each bottom event according to the occurrence frequency of each bottom event;
determining the target failure probability of each bottom event according to the initial failure probability and the corrected failure probability of each bottom event;
and calculating the fault tree model layer by layer according to the target failure probability of each bottom event and the sequence from the bottom layer to the top layer to obtain the importance of each bottom event.
5. The method of claim 3, further comprising:
monitoring the key nuclear power equipment, searching solution information corresponding to the fault from a preset database when the key nuclear power equipment fails, and sending the solution information to terminal equipment where maintenance personnel are located.
6. The method of any of claims 1 to 5, further comprising:
analyzing the power generation reliability index according to a preset quantization strategy to determine whether the deviation between the power generation reliability index and the quantization index exceeds a preset range;
if so, correcting the fault tree model;
wherein the quantization strategy comprises at least one of the following parameters: industry experience feedback information and a probabilistic risk assessment model.
7. The method of claim 1, further comprising:
and when the power generation reliability index exceeds a preset threshold value, the information of the nuclear power equipment is prominently displayed.
8. A reliability analysis device of a nuclear power station unit is characterized by comprising:
the first acquisition module is used for acquiring a fault tree model of the nuclear power station unit;
the second acquisition module is used for acquiring the running state information of the nuclear power equipment corresponding to the bottom event of the fault tree model;
and the processing module is used for calculating the fault tree model layer by layer according to the actual failure data of the nuclear power equipment and the sequence from the bottom layer to the top layer when the nuclear power equipment fails to work, so as to obtain the power generation reliability index of the nuclear power station unit.
9. An electronic device comprising a memory and a processor, the memory storing a computer program, wherein the processor implements the steps of the method of any one of claims 1 to 7 when executing the computer program.
10. A computer-readable storage medium, on which a computer program is stored, which, when being executed by a processor, carries out the steps of the method according to any one of claims 1 to 7.
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| CN202210357362.0A CN114743703A (en) | 2022-04-06 | 2022-04-06 | Reliability analysis method, device, equipment and storage medium for nuclear power station unit |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2024087404A1 (en) * | 2022-10-25 | 2024-05-02 | 中广核研究院有限公司 | Nuclear reactor fault determination method, apparatus, device, storage medium, and product |
| CN118194583A (en) * | 2024-04-03 | 2024-06-14 | 中国电子产品可靠性与环境试验研究所（（工业和信息化部电子第五研究所）（中国赛宝实验室）） | Component structure analysis method, device, computer equipment and storage medium |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2024087404A1 (en) * | 2022-10-25 | 2024-05-02 | 中广核研究院有限公司 | Nuclear reactor fault determination method, apparatus, device, storage medium, and product |
| CN118194583A (en) * | 2024-04-03 | 2024-06-14 | 中国电子产品可靠性与环境试验研究所（（工业和信息化部电子第五研究所）（中国赛宝实验室）） | Component structure analysis method, device, computer equipment and storage medium |
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