CN114997437A - Reactor core damage frequency calculation method and system based on nuclear power plant production task - Google Patents
Reactor core damage frequency calculation method and system based on nuclear power plant production task Download PDFInfo
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Abstract
The application provides a reactor core damage frequency calculation method and system based on a nuclear power plant production task, wherein the method comprises the following steps: acquiring work order information of each device when a nuclear power plant production task is executed within a preset time period; screening out work order information of equipment related to PSA risk; and calculating the reactor core damage frequency of the production task of the nuclear power plant based on the screened work order information. The technical scheme that this application provided can realize nuclear power production task reactor core damage frequency automatic calculation, promotes the interconnected intercommunication of data between reactor core damage frequency calculation and the production task, helps promoting staff work efficiency, and can acquire the risk level that reactor core damage frequency corresponds fast to optimize production task planning, promote nuclear power plant's production risk safety control ability, guarantee unit safety and stability operation.
Description
Technical Field
The application relates to the field of reactor core damage frequency calculation, in particular to a method and a system for calculating reactor core damage frequency based on a nuclear power plant production task.
Background
The nuclear safety related system and equipment exit from a normal operation state or a hot standby state due to work such as maintenance, test, operation, change (including temporary change) and the like, the configuration of an operation system is influenced, so that the safety level of a unit is reduced, the risk generated by the operation system must be evaluated and controlled, and the risk is ensured to be reduced to an acceptable level. Risk management measures that may be taken by a nuclear power plant are regulated. Risk management measures generally include the following: the plan is modified to avoid high risk configuration; reducing the duration of the high-risk configuration; taking compensation measures to reduce the risk of configuration (deleting risk sensitive activities from the planned work content, accelerating the recovery of the function of the decommissioned equipment, ensuring the availability of functional redundant equipment, paying attention to special activities which affect the stability of the unit, etc.); avoidance of sensitive Sulfide Stress Corrosion Cracking (SSC) that would form a higher risk configuration is not available. If the above management measures are invalid and an unacceptably high risk configuration may occur, the unit is pulled back to the appropriate admission mode.
Therefore, nuclear power plant production planning personnel and Safety analysis personnel need to perform Core loss evaluation by using a risk monitor every day to ensure that production task arrangement meets the requirements of nuclear power plant configuration risk management and Probability Safety Assessment (PSA), but at present, the nuclear power production planning personnel need to derive future planning work every day and submit the future planning work to the Safety analysis personnel for Core Damage Frequency (CDF) calculation, so that the Core damage Frequency calculation work consumes time and labor, and the efficiency is low.
Disclosure of Invention
The application provides a reactor core damage frequency calculation method and system based on nuclear power plant production tasks to solve at least that reactor core damage frequency calculation work is consuming time and is consuming effort, the technical problem of inefficiency.
The embodiment of the first aspect of the application provides a method for calculating the damage frequency of a reactor core based on a production task of a nuclear power plant, which is characterized by comprising the following steps:
acquiring work order information of each device when a nuclear power plant production task is executed within a preset time period;
screening out work order information of equipment related to PSA risk;
and calculating the reactor core damage frequency of the production task of the nuclear power plant based on the screened work order information.
Preferably, the work order information includes:
work order type, equipment work content, equipment encoding, equipment planned start time, equipment planned completion time, whether the equipment is relevant to PSA risk determination, PSA characterizing equipment information, and equipment isolation requirements.
Preferably, before the core damage frequency calculation of the nuclear power plant production task based on the screened work order information, the method includes:
judging whether the information of the PSA representation equipment in the screened work order information has a value or not;
when the information position of the PSA representation equipment in the work order information has no value, judging the work order type corresponding to the work order;
if the work order type is a preventive maintenance type, identifying PSA representation equipment information corresponding to the preventive maintenance type in preset PSA representation equipment information;
and if the work order type corresponding to the work order is a corrective maintenance type or a defect maintenance type, judging whether the maintenance type has an isolation requirement, if so, identifying PSA (pressure swing adsorption) representation equipment information in the historical maintenance record of the equipment corresponding to the work order, otherwise, deleting the work order, and not calculating the reactor core damage frequency of the production task of the nuclear power plant.
Further, the calculation of the reactor core damage frequency of the nuclear power plant production task based on the screened work order information includes:
and inputting the work order information into the risk monitor for calculation to obtain the core damage frequency of the equipment corresponding to the work order when the nuclear power plant production task is executed.
Preferably, the method further comprises:
and judging the risk grade corresponding to the core damage frequency, and displaying the risk grade.
Preferably, the method further comprises:
and when the core damage frequency is greater than a preset damage frequency threshold value, determining the reason, the starting time, the ending time, the core risk increment and the core damage probability increment of the equipment by using the risk monitor.
An embodiment of a second aspect of the present application provides a reactor core damage frequency calculation system based on a production task of a nuclear power plant, including:
the acquisition module is used for acquiring the work order information of each device when the nuclear power plant production task is executed within a preset time period;
the screening module is used for screening out the work order information of the equipment related to the PSA risk;
and the calculation module is used for calculating the reactor core damage frequency of the nuclear power plant production task based on the screened work order information.
Preferably, the work order information includes:
work order type, equipment work content, equipment code, equipment planned start time, equipment planned completion time, whether the equipment is relevant to PSA risk determination, PSA characterization equipment information, and equipment isolation requirements.
Preferably, the core damage frequency calculation system further includes:
the judging module is used for judging whether the information of the PSA representation equipment in the screened work order information has a value or not;
when the information position of PSA (pressure swing adsorption) representation equipment in the work order information has no value, judging the type of the work order corresponding to the work order;
if the work order type is a preventive maintenance type, identifying PSA representation equipment information corresponding to the preventive maintenance type in preset PSA representation equipment information;
and if the work order type corresponding to the work order is a corrective maintenance type or a defect maintenance type, judging whether the maintenance type has an isolation requirement, if so, identifying PSA (pressure swing adsorption) representation equipment information in the historical maintenance record of the equipment corresponding to the work order, otherwise, deleting the work order, and not calculating the reactor core damage frequency of the production task of the nuclear power plant.
Further, the calculation module is configured to:
and inputting the work order information into the risk monitor for calculation to obtain the core damage frequency of the equipment corresponding to the work order when the nuclear power plant production task is executed.
Further, the system further comprises:
and the display module is used for judging the risk grade corresponding to the core damage frequency and displaying the risk grade.
Further, the system further comprises:
and the determining module is used for determining the reason, the starting time, the ending time, the core risk increment and the core damage probability increment of the equipment by utilizing the risk monitor when the core damage frequency is greater than a preset damage frequency threshold.
The technical scheme provided by the embodiment of the application at least has the following beneficial effects:
the application provides a reactor core damage frequency calculation method and system based on a nuclear power plant production task, wherein the method comprises the following steps: acquiring work order information of each device when a nuclear power plant production task is executed within a preset time period; screening out work order information of equipment related to PSA risk; and calculating the reactor core damage frequency of the production task of the nuclear power plant based on the screened work order information. The technical scheme that this application provided can realize nuclear power production task reactor core damage frequency automatic calculation, promotes the interconnected intercommunication of data between reactor core damage frequency calculation and the production task, helps promoting staff work efficiency, and can acquire the risk level that reactor core damage frequency corresponds fast to optimize production task planning, promote nuclear power plant's production risk safety control ability, guarantee unit safety and stability operation.
Additional aspects and advantages of the present application will be set forth in part in the description which follows and, in part, will be obvious from the description, or may be learned by practice of the present application.
Drawings
The foregoing and/or additional aspects and advantages of the present application will become apparent and readily appreciated from the following description of the embodiments, taken in conjunction with the accompanying drawings of which:
FIG. 1 is a flow chart of a method for calculating core damage frequency based on nuclear power plant production tasks according to an embodiment of the present application;
FIG. 2 is a first block diagram of a nuclear power plant production mission based core damage frequency calculation system according to an embodiment of the present application;
FIG. 3 is a second block diagram of a nuclear power plant production mission based core damage frequency calculation system according to an embodiment of the present application;
FIG. 4 is a third block diagram of a nuclear power plant production mission based core damage frequency calculation system according to an embodiment of the present application;
FIG. 5 is a fourth block diagram of a nuclear power plant production mission based core damage frequency calculation system according to an embodiment of the present application.
Detailed Description
Reference will now be made in detail to the embodiments of the present application, examples of which are illustrated in the accompanying drawings, wherein like reference numerals refer to the same or similar elements or elements having the same or similar functions throughout. The embodiments described below with reference to the drawings are exemplary and intended to be used for explaining the present application and should not be construed as limiting the present application.
The application provides a reactor core damage frequency calculation method and system based on nuclear power plant production tasks, the method comprises the following steps: acquiring work order information of each device when a nuclear power plant production task is executed within a preset time period; screening out work order information of equipment related to PSA risk; and calculating the reactor core damage frequency of the production task of the nuclear power plant based on the screened work order information. The technical scheme that this application provided can realize nuclear power production task reactor core damage frequency automatic calculation, promotes the interconnected intercommunication of data between reactor core damage frequency calculation and the production task, helps promoting staff work efficiency, and can acquire the risk level that reactor core damage frequency corresponds fast to optimize production task planning, promote nuclear power plant's production risk safety control ability, guarantee unit safety and stability operation.
The following describes a core damage frequency calculation method and system based on a nuclear power plant production task according to an embodiment of the present application with reference to the drawings.
Example one
Fig. 1 is a flowchart of a core damage frequency calculation method based on a nuclear power plant production task according to an embodiment of the present application, where the method includes:
step 1: acquiring work order information of each device when a nuclear power plant production task is executed within a preset time period;
it should be noted that, first, a device information management module of the power plant production management information system may be used to mark devices related to the Probabilistic Safety Analysis (PSA) to indicate that the devices are related to PSA risks, or a "PSA characterization device" field may be introduced for PSA related devices to display various impact function descriptions generated when the devices are faulty, which are clear in the maintenance rules, and power plant personnel may clearly determine the functional impact generated by the work according to the work needs.
Then, when a work order is created according to equipment in a power plant production management information system, basic equipment information can be brought into the work order, so that PSA (pressure swing adsorption) related and PSA characterization equipment information (including influence function description determined by maintenance rules) can be obtained in the work order after PSA related equipment is quoted to create the work order, different PSA characterization equipment information needs to be selected by maintenance preparers or power plant safety analysts aiming at different fault types, influence function description corresponding to the work is determined, for preventive maintenance work, corresponding PSA related and PSA characterization equipment information can be recorded when a standard work order or a template work order is prepared, and input is provided for core damage probability calculation of a work order of a subsequent preventive maintenance type.
Wherein the work order information includes: work order type, equipment work content, equipment code, equipment planned start time, equipment planned completion time, whether the equipment is relevant to PSA risk determination, PSA characterization equipment information, and equipment isolation requirements.
Furthermore, the safety analysis personnel of the power plant performs PSA (pressure swing adsorption) characterization equipment identification and improvement on the three rolling work orders every day, and the improved information is written into a field of the PSA characterization equipment of the work orders, so that the reactor core damage probability can be directly calculated even if the planning time of the work orders is adjusted.
Step 2: screening out work order information of equipment related to PSA risk;
the step 2 specifically comprises: and screening out the work order information corresponding to the equipment marked by the equipment information management module of the power plant production management information system in the step 1 from the obtained work order information of each equipment when the nuclear power plant production task is executed in the preset time period.
And step 3: and calculating the reactor core damage frequency of the production task of the nuclear power plant based on the screened work order information.
Before step 3, the method includes:
judging whether the information of the PSA representation equipment in the screened work order information has a value or not;
when the information position of the PSA representation equipment in the work order information has no value, judging the work order type corresponding to the work order;
if the work order type is a preventive maintenance type, PSA representation equipment information corresponding to the preventive maintenance type is identified in preset PSA representation equipment information;
and if the work order type corresponding to the work order is a corrective maintenance type or a defect maintenance type, judging whether the maintenance type has an isolation requirement, if so, identifying PSA (pressure swing adsorption) representation equipment information in the historical maintenance record of the equipment corresponding to the work order, otherwise, deleting the work order, and not calculating the reactor core damage frequency of the production task of the nuclear power plant.
Specifically, the step 3 includes:
and inputting the work order information into the risk monitor for calculation to obtain the core damage frequency of the equipment corresponding to the work order when the nuclear power plant production task is executed.
In an embodiment of the disclosure, the method further comprises:
and judging the risk grade corresponding to the core damage frequency, and displaying the risk grade.
The risk level is determined based on a preset risk level range corresponding to the core damage frequency;
when the risk grade is displayed, the severity degree of the risk grade is respectively corresponding to red, orange and green; when the displayed risk grade corresponds to red or orange, the production planning personnel should properly adjust the production task plan until the risk grade corresponding to the calculation result of the reactor core damage frequency CDF is green. If the site working condition requires that the work is carried out under the condition that the risk level is displayed in red, the production task is executed by the factory leader for approval, and the work execution department and the operation department can compile an emergency plan to ensure that the risk is controllable; if site conditions require that work must be done with the risk level shown as orange, approval by the plant management layer must be obtained when performing the production task.
In an embodiment of the disclosure, the method further comprises:
and when the core damage frequency is greater than a preset damage frequency threshold value, determining the reason, the starting time, the ending time, the core risk increment and the core damage probability increment of the equipment by using the risk monitor.
It should be noted that the method provided by the embodiment is applicable to different types of reactor units, such as a high temperature gas cooled reactor, a pressurized water reactor, a heavy water reactor, and a sodium cooled fast reactor.
In summary, according to the reactor core damage frequency calculation method based on the nuclear power plant production task provided by the embodiment, the reactor core damage frequency of the nuclear power production task can be automatically calculated, interconnection and intercommunication of data between the reactor core damage frequency calculation and the production task are promoted, the working efficiency of workers is improved, the risk level corresponding to the reactor core damage frequency can be quickly obtained, the production task planning arrangement is optimized, the production risk safety control capability of the nuclear power plant is improved, and the safe and stable operation of a unit is guaranteed.
Example two
FIG. 2 is a core damage frequency calculation system based on nuclear power plant production tasks according to an embodiment of the present application, including:
the acquisition module 100 is configured to acquire work order information of each device when a nuclear power plant production task is executed within a preset time period;
a screening module 200 for screening out work order information for equipment associated with PSA risk;
and the calculation module 300 is used for calculating the reactor core damage frequency of the nuclear power plant production task based on the screened work order information.
In an embodiment of the present disclosure, the work order information includes:
work order type, equipment work content, equipment code, equipment planned start time, equipment planned completion time, whether the equipment is relevant to PSA risk determination, PSA characterization equipment information, and equipment isolation requirements.
In an embodiment of the present disclosure, as shown in fig. 3, the core damage frequency calculation system further includes:
a judging module 400, configured to judge whether there is a value at a PSA representation device information location in the screened work order information;
when the information position of PSA (pressure swing adsorption) representation equipment in the work order information has no value, judging the type of the work order corresponding to the work order;
if the work order type is a preventive maintenance type, PSA representation equipment information corresponding to the preventive maintenance type is identified in preset PSA representation equipment information;
and if the work order type corresponding to the work order is a corrective maintenance type or a defect maintenance type, judging whether the maintenance type has an isolation requirement, if so, identifying PSA (pressure swing adsorption) representation equipment information in the historical maintenance record of the equipment corresponding to the work order, otherwise, deleting the work order, and not calculating the reactor core damage frequency of the production task of the nuclear power plant.
Further, the calculation module 300 is configured to:
and inputting the work order information into the risk monitor for calculation to obtain the core damage frequency of the equipment corresponding to the work order when the nuclear power plant production task is executed.
Further, as shown in fig. 4, the system further includes:
and the display module 500 is configured to judge a risk level corresponding to the core damage frequency and display the risk level.
Further, as shown in fig. 5, the system further includes:
a determining module 600, configured to determine, by using the risk monitor, a cause, a start time, an end time, a core risk increase amount, and a core damage probability increment of the equipment for the core damage frequency change when the core damage frequency is greater than a preset damage frequency threshold.
In conclusion, the reactor core damage frequency calculation system based on the nuclear power plant production task, which is provided by the embodiment, can realize automatic calculation of the reactor core damage frequency of the nuclear power plant production task, promote interconnection and intercommunication of data between the reactor core damage frequency calculation and the production task, is beneficial to improving the working efficiency of workers, and can quickly acquire the risk level corresponding to the reactor core damage frequency so as to optimize the plan arrangement of the production task, improve the production risk safety control capability of the nuclear power plant, and ensure the safe and stable operation of a unit.
In the description herein, reference to the description of the term "one embodiment," "some embodiments," "an example," "a specific example," or "some examples," etc., means that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the application. In this specification, the schematic representations of the terms used above are not necessarily intended to refer to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples. Furthermore, various embodiments or examples and features of different embodiments or examples described in this specification can be combined and combined by one skilled in the art without contradiction.
Any process or method descriptions in flow charts or otherwise described herein may be understood as representing modules, segments, or portions of code which include one or more executable instructions for implementing steps of a custom logic function or process, and alternate implementations are included within the scope of the preferred embodiment of the present application in which functions may be executed out of order from that shown or discussed, including substantially concurrently or in reverse order, depending on the functionality involved, as would be understood by those reasonably skilled in the art of the present application.
Although embodiments of the present application have been shown and described above, it is understood that the above embodiments are exemplary and should not be construed as limiting the present application, and that variations, modifications, substitutions and alterations may be made to the above embodiments by those of ordinary skill in the art within the scope of the present application.
Claims (10)
1. A method for calculating the damage frequency of a reactor core based on the production task of a nuclear power plant is characterized by comprising the following steps:
acquiring work order information of each device when a nuclear power plant production task is executed within a preset time period;
screening out work order information of equipment related to PSA risk;
and calculating the reactor core damage frequency of the production task of the nuclear power plant based on the screened work order information.
2. The method of claim 1, wherein the work order information comprises:
work order type, equipment work content, equipment code, equipment planned start time, equipment planned completion time, whether the equipment is relevant to PSA risk determination, PSA characterization equipment information, and equipment isolation requirements.
3. The method of claim 2, wherein prior to performing core damage frequency calculations for nuclear power plant production tasks based on the screened work order information, comprising:
judging whether the information of the PSA representation equipment in the screened work order information has a value or not;
when the information position of the PSA representation equipment in the work order information has no value, judging the work order type corresponding to the work order;
if the work order type is a preventive maintenance type, PSA representation equipment information corresponding to the preventive maintenance type is identified in preset PSA representation equipment information;
and if the work order type corresponding to the work order is a corrective maintenance type or a defect maintenance type, judging whether the maintenance type has an isolation requirement, if so, identifying PSA (pressure swing adsorption) representation equipment information in the historical maintenance record of the equipment corresponding to the work order, otherwise, deleting the work order, and not calculating the reactor core damage frequency of the production task of the nuclear power plant.
4. The method of claim 3, wherein the performing core damage frequency calculations for nuclear power plant production tasks based on the screened work order information comprises:
and inputting the work order information into the risk monitor for calculation to obtain the core damage frequency of the equipment corresponding to the work order when the nuclear power plant production task is executed.
5. The method of claim 4, wherein the method further comprises:
and judging the risk grade corresponding to the core damage frequency, and displaying the risk grade.
6. The method of claim 5, wherein the method further comprises:
and when the core damage frequency is greater than a preset damage frequency threshold value, determining the reason, the starting time, the ending time, the core risk increment and the core damage probability increment of the equipment by using the risk monitor.
7. A reactor core damage frequency calculation system based on nuclear power plant production tasks, comprising:
the acquisition module is used for acquiring the work order information of each device when the nuclear power plant production task is executed within a preset time period;
the screening module is used for screening out the work order information of the equipment related to the PSA risk;
and the calculation module is used for calculating the reactor core damage frequency of the nuclear power plant production task based on the screened work order information.
8. The core damage frequency calculation system of claim 7 wherein the work order information comprises:
work order type, equipment work content, equipment code, equipment planned start time, equipment planned completion time, whether the equipment is relevant to PSA risk determination, PSA characterization equipment information, and equipment isolation requirements.
9. The core impairment frequency calculation system of claim 8 wherein the core impairment frequency calculation system further comprises:
the judging module is used for judging whether the information of the PSA representation equipment in the screened work order information has a value or not;
when the information position of PSA (pressure swing adsorption) representation equipment in the work order information has no value, judging the type of the work order corresponding to the work order;
if the work order type is a preventive maintenance type, identifying PSA representation equipment information corresponding to the preventive maintenance type in preset PSA representation equipment information;
and if the work order type corresponding to the work order is a corrective maintenance type or a defect maintenance type, judging whether the maintenance type has an isolation requirement, if so, identifying PSA (pressure swing adsorption) representation equipment information in the historical maintenance record of the equipment corresponding to the work order, otherwise, deleting the work order, and not calculating the reactor core damage frequency of the production task of the nuclear power plant.
10. The core damage frequency calculation system of claim 9 wherein the calculation module is to:
and inputting the work order information into the risk monitor for calculation to obtain the core damage frequency of the equipment corresponding to the work order when the nuclear power plant production task is executed.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
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| CN202210662156.0A CN114997437B (en) | 2022-06-13 | 2022-06-13 | Core damage frequency calculation method and system based on production tasks of nuclear power plant |
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| CN202210662156.0A CN114997437B (en) | 2022-06-13 | 2022-06-13 | Core damage frequency calculation method and system based on production tasks of nuclear power plant |
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| CN114997437B CN114997437B (en) | 2023-08-29 |
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