CN117994073A - Nuclear power station water intake safety management system and method based on multi-source data - Google Patents
Nuclear power station water intake safety management system and method based on multi-source data Download PDFInfo
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Abstract
The invention relates to the technical field of nuclear power station safety supervision. The system and the method for safely managing the water intake of the nuclear power station comprise a data acquisition module, a data analysis module, a safety supervision module and an alarm reminding module; the data acquisition module is used for acquiring data information of the nuclear power station and data information monitored by the sensor in real time; the data analysis module is used for analyzing the power generation efficiency of the nuclear power station and the fault reason of the nuclear power station; the safety supervision module is used for analyzing the safety score of the water intake of the nuclear power station and determining the abnormal grade of the water intake of the nuclear power station; the alarm reminding module carries out alarm reminding based on the abnormal grade of the water intake of the nuclear power station and adopts corresponding safety measures. According to the invention, corresponding safety measures are started aiming at the abnormal level of the water intake of the target nuclear power station, so that the problems that equipment such as a water pump and the like are failed due to the blockage of the water intake, the stable operation of the nuclear power station is influenced, and safety accidents are caused are avoided.
Description
Technical Field
The invention relates to the technical field of nuclear power station safety supervision, in particular to a nuclear power station water intake safety management system and method based on multi-source data.
Background
The water intake of the nuclear power station is an important component of the nuclear power station and is responsible for providing cooling water for the reactor and maintaining the normal operation of the reactor; the water intake of a nuclear power plant is usually located close to the sea or large river in order to utilize abundant water resources. In the operation process of the nuclear power station, the water intake can introduce cooling water into the reactor, absorb heat generated by the reactor and then discharge the heat, so that a circulating cooling system is formed. The system is critical to the safe and stable operation of the nuclear power station, so that the water intake needs to be checked and maintained regularly to ensure the normal operation of the water intake.
Under the prior art, because the environmental factors of water intake work are complex, the problems of water intake blockage are possibly caused by invasion of foreign matters and the like, the current monitoring and maintenance strategies of the water intake are possibly imperfect, the problems cannot be found and treated in time, the water intake cannot be treated in time when faults or abnormal conditions occur, the operation of the whole circulating cooling water system is affected, and the nuclear power station cannot operate safely and stably.
Disclosure of Invention
The invention aims to provide a nuclear power station water intake safety management system and method based on multi-source data, which are used for solving the problems in the background technology.
In order to solve the technical problems, the invention provides the following technical scheme: a nuclear power station water intake safety management method based on multi-source data specifically comprises the following steps:
S100, acquiring data information of the nuclear power plant according to a nuclear energy mechanism or a database provided by a nuclear power plant operator or a supplier, and analyzing and obtaining heat energy generated by a target nuclear power plant based on the data information of the nuclear power plant because the heat energy generated by the nuclear power plant is not fixed and unchanged due to the need of acquiring heat energy variation generated by the current analysis nuclear power plant; the nuclear energy mechanism or the database provided by the nuclear power station operator or the supplier contains detailed information such as the type of the reactor, the fuel type and the like, and the data information of the nuclear power station comprises the type of the reactor, the fuel type and the like;
S200, acquiring electric energy generated by a target nuclear power station in unit time based on real-time data information of monitoring equipment, analyzing and judging the power generation efficiency of the target nuclear power station according to the electric energy generated by the target nuclear power station in unit time and the generated heat energy, and judging whether the target nuclear power station has a fault or not according to the power generation efficiency to determine a fault reason;
S300, constructing an abnormal grade evaluation model according to the fault cause of the nuclear power station, and evaluating the abnormal grade of the nuclear power station based on the abnormal grade evaluation model;
S400, determining an abnormal grade of the nuclear power station, and starting corresponding safety measures according to the abnormal grade.
Further, the specific method for analyzing the heat energy generated by the target nuclear power station in S100 is as follows:
S101, acquiring data information of the nuclear power station according to a data report provided by a nuclear energy mechanism, a nuclear power plant data information set Si is generated, si= { Si1, si2, si 3..sij.. SiJ }, i=1, 2, 3..i., I represents the total number of nuclear plants in the data report provided for the nuclear power institution, j=1, 2, 3..j, J being the number of acquired nuclear power plant data information; si is represented as the data information set of the i-th nuclear power plant, and Sij is represented as the j-th data information of the i-th nuclear power plant; according to the formula:
J(Si，Sa)＝|Si∩Sa|/|Si∪Sa|
Calculating to obtain the similarity of the data information set of the target nuclear power plant and the data information set of the nuclear power plant in a data report provided by a nuclear energy mechanism, wherein J (Si, sa) is represented as the similarity of the data information set Sa of the target nuclear power plant and the data information set of the ith nuclear power plant, |Si n Sa|is represented as the number of subsets of intersection sets of the data information set of the ith nuclear power plant and the target nuclear power plant, |Si n Sa is represented as the number of subsets of union sets of the data sets of the ith nuclear power plant and the target nuclear power plant, and Sa is represented as the data information set of the target nuclear power plant;
S102, sorting the nuclear power stations according to the sequence from high to low of the similarity of the data information sets among the nuclear power stations, selecting the nuclear power station with the highest similarity for marking, and marking the data information set as Si ', I' epsilon {1, 2, 3.. I }; since the thermal power of each nuclear power plant is not known to be present and the thermal power of the nuclear power plant is determined according to various factors such as the type, fuel type, design parameters, operating state and the like of the nuclear reactor, it is necessary to calculate the similarity according to the data information set of the nuclear power plant known originally, and calculate the nuclear power plant with the highest similarity so as to be able to predict the thermal power of the target nuclear power plant, so that the calculation formula of the thermal power of the nuclear reactor is utilized according to the data information set Si': p=v×u, and the heat generated by each nuclear reaction in the unit time can be obtained through calculation; wherein p is represented as the thermal power of a nuclear reactor in the nuclear power plant, v is represented as the nuclear reaction rate generated by fuel, u is represented as the average energy released by each nuclear reaction, the power heat depends on the rate of the nuclear reaction and the energy released by each nuclear reaction, and the thermal power of the nuclear reactor determines the power generation capacity and efficiency of the nuclear power plant;
S103, obtaining the number of nuclear reactors in the target nuclear power station, and calculating to obtain the total thermal power P=n×p generated by the target nuclear power station in unit time, wherein n is the total number of the nuclear reactors in the target nuclear power station.
Further, the specific method for analyzing and judging the power generation efficiency of the target nuclear power plant and judging the fault of the target nuclear power plant and determining the cause of the fault in S200 is as follows:
S201, acquiring the generated energy of the core power station in unit time as z according to the data information of the monitoring equipment for real-time monitoring of the target nuclear power station, and according to the formula: η= (z/P) ×100% and calculating to obtain the power generation efficiency η of the target nuclear power plant; when the power generation efficiency of the target nuclear power plant does not belong to a preset power generation efficiency threshold value range [ A, B ], judging that the target nuclear power plant has faults, wherein A is represented as a lower limit of the preset power generation efficiency threshold value, and B is represented as an upper limit of the preset power generation efficiency threshold value;
s202, when eta is more than or equal to B, judging that a nuclear power station data information set Si ' does not have timeliness and identifying the nuclear power station data information set Si ' in a data report provided by a nuclear energy mechanism and rejecting the nuclear power station data information set Si ' from a database because the internal equipment of a reactor is subjected to abrasion and ageing along with the operation of the nuclear power station when the thermal power P of a target nuclear power station is obtained by utilizing the similarity prediction of data information among the nuclear power stations, thereby influencing the performance of the internal equipment and further influencing the output of the thermal power;
When eta is less than or equal to A, the thermal power P of the target nuclear power station predicted by the similarity of data information among the nuclear power stations is larger than the thermal power of the target nuclear power station, so that the power generation efficiency of the nuclear power station is not in the preset power generation efficiency threshold range, the predicted thermal power of the target nuclear power station is judged to be larger than the actual thermal power, and cooling water is provided for the reactor due to the effect of a water intake, so that the normal operation of the reactor is maintained; when the cooling water is not supplied enough, the heat power output of the reactor is affected, namely, the water intake of the nuclear power station is judged to be abnormal, and warning and reminding are carried out.
Further, in S300: the specific method for evaluating the abnormal grade of the nuclear power station based on the abnormal grade evaluation model comprises the following steps:
S301, extracting water flow of a water intake through real-time monitoring data uploaded to a platform by a sensor in a target nuclear power station, wherein r=1, 2 and 3. Accumulating the number of the sensors with the value (vr/V) being less than or equal to V 'to obtain M [ (vr/V) being less than or equal to V' ], and when R-M [ (vr/V) being less than or equal to V '] is greater than or equal to M [ (vr/V) being less than or equal to V' ], indicating that the number of the sensors with normal water flow monitored at the water intake of the target nuclear power station is greater than or equal to the number of the sensors with abnormal water flow monitored, indicating that the data monitored by the sensors exist at the water intake of the target nuclear power station are inaccurate, thereby reducing the monitoring coverage rate of the water intake; according to the formula:
f＝F-k1/v-k2/{M[(vr/V)≤v’]/R}
Calculating to obtain the safety score of the water intake of the target nuclear power station; wherein F is expressed as a safety score of the water intake of the target nuclear power station, F is expressed as a safety initial score of the water intake of the nuclear power station, V is expressed as a maximum water flow allowed by the water intake of the target nuclear power station, V' is expressed as a preset threshold value of a water flow ratio of the water intake of the target nuclear power station, and k1 and k2 are respectively expressed as weight values;
S302, constructing an abnormal grade evaluation model:
Calculating to obtain the abnormal grade of the water intake of the target nuclear power station, and judging that the abnormal grade of the water intake of the target nuclear power station is high when Q=3; when q=2, determining that the abnormal grade of the water intake of the target nuclear power station is medium; when q=1, determining that the abnormality level of the water intake of the target nuclear power station is low; wherein Q is represented by a target nuclear power station water intake anomaly level, alpha is represented by an upper limit of a water intake safety score when the target nuclear power station water intake anomaly level is highest, beta is represented by an upper limit of a water intake safety score when the target nuclear power station water intake anomaly level is middle, and gamma is represented by an error value of the target nuclear power station water intake safety score because the safety score of the target nuclear power station water intake is unlikely to be full.
Further, the specific method for starting the corresponding security measures according to the abnormal level in S400 is as follows: the specific method for starting the corresponding security measures according to the abnormal level in S400 is as follows: when the abnormal level Q=3 of the water intake of the target nuclear power station, the water intake of the target nuclear power station is seriously blocked, so that a reactor in the nuclear power station is overheated and even a safety accident is caused; the blockage of the water intake can cause the faults of equipment such as a water pump, a cooling tower and the like, thereby affecting the stable operation of the nuclear power station, so that the operation of the nuclear power station needs to be stopped by emergency alarm and workers are arranged to completely maintain and overhaul the water intake of the nuclear power station immediately; when the abnormal level Q=2 of the water intake of the target nuclear power station, carrying out alarm reminding and reducing the operation load of the nuclear power station so as to reduce the requirement of cooling water; when the abnormal level Q=1 of the water intake of the target nuclear power station, reminding is carried out, and the abnormal condition is recorded and the personnel to be maintained.
The system and the method for safely managing the water intake of the nuclear power station comprise a data acquisition module, a data analysis module, a safety supervision module and an alarm reminding module; the output end of the data acquisition module is connected with the input end of the data analysis module, the output end of the data analysis module is connected with the input end of the safety supervision module, and the output end of the safety supervision module is connected with the input end of the alarm reminding module; the data acquisition module is used for acquiring data information of the nuclear power station and data information monitored by the sensor in real time; the data analysis module is used for analyzing the power generation efficiency of the nuclear power station and the fault reason of the nuclear power station; the safety supervision module analyzes the safety score of the water intake of the nuclear power station and determines the abnormal grade of the water intake of the nuclear power station, and corresponding emergency measures can be taken based on the abnormal grade of the water intake of the nuclear power station; the alarm reminding module carries out alarm reminding based on the abnormal grade of the water intake of the nuclear power station and takes safety measures corresponding to the abnormal grade of the water intake.
Further, the data acquisition module comprises a nuclear power station data information acquisition unit and a sensor monitoring data acquisition unit; the nuclear power station data information acquisition unit is used for acquiring data information of a nuclear power station, and according to the data information of the nuclear power station, the thermal power of the nuclear power station can be predicted so as to analyze and judge whether the power generation efficiency of the nuclear power station belongs to a normal range or not and further determine the cause of the nuclear power station fault; the sensor monitoring data acquisition unit is used for acquiring real-time monitoring data uploaded to the platform by the sensor after determining the fault cause of the nuclear power station.
Further, the data analysis module comprises a nuclear power station power generation efficiency analysis unit and a nuclear power station fault cause analysis unit; the power generation efficiency analysis unit of the nuclear power plant analyzes the power generation efficiency of the nuclear power plant according to the predicted thermal power of the nuclear power plant, and determines the cause of the failure of the nuclear power plant according to whether the power generation efficiency of the nuclear power plant belongs to a normal range; the nuclear power station fault cause analysis unit is used for analyzing the fault cause of the nuclear power station according to the efficiency of the nuclear power station.
Further, the safety supervision module comprises a nuclear power station water intake safety score analysis unit and an abnormal grade evaluation model construction unit; the safety score analysis unit of the water intake of the nuclear power station analyzes the safety score of the water intake of the nuclear power station according to the real-time monitoring data uploaded to the platform by the sensor; the abnormal grade evaluation model construction unit is used for constructing an abnormal grade evaluation model based on the safety score of the water intake of the nuclear power station, carrying out different grades of alarm reminding through the abnormal grade evaluation model and taking corresponding safety measures.
Further, the alarm reminding module comprises an alarm reminding unit and a safety measure decision unit; the alarm reminding unit carries out alarm reminding of different levels based on abnormal levels of the water intake of the nuclear power station; the security measure decision unit decides the security measure according to the alarm reminding level.
Compared with the prior art, the invention has the following beneficial effects: according to the method, the power generation efficiency of the target nuclear power station is predicted by utilizing the similarity between the data information of the nuclear power station, and when the power generation efficiency of the target nuclear power station does not belong to a normal efficiency range, the fault cause of the target nuclear power station can be determined, so that errors caused by inaccurate monitoring of a sensor are reduced; and the abnormal grade of the water intake of the target nuclear power station is determined, corresponding safety measures are started aiming at the abnormal grade of the water intake of the target nuclear power station, and the problems that equipment such as a water pump, a cooling tower and the like are failed due to the blocking of the water intake are avoided, so that a reactor in the nuclear power station is overheated, the stable operation of the nuclear power station is influenced, and safety accidents are caused.
Drawings
The accompanying drawings are included to provide a further understanding of the invention and are incorporated in and constitute a part of this specification, illustrate the invention and together with the embodiments of the invention, serve to explain the invention. In the drawings:
fig. 1 is a schematic structural diagram of a nuclear power station water intake safety management system based on multi-source data.
Detailed Description
The following description of the embodiments of the present invention will be made clearly and completely with reference to the accompanying drawings, in which it is apparent that the embodiments described are only some embodiments of the present invention, but not all embodiments. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to be within the scope of the invention.
Referring to fig. 1, the present invention provides the following technical solutions: a nuclear power station water intake safety management method based on multi-source data specifically comprises the following steps:
S100, acquiring data information of the nuclear power plant according to a nuclear energy mechanism or a database provided by a nuclear power plant operator or a supplier, and analyzing and obtaining heat energy generated by a target nuclear power plant based on the data information of the nuclear power plant because the heat energy generated by the nuclear power plant is not fixed and unchanged due to the need of acquiring heat energy variation generated by the current analysis nuclear power plant; the nuclear energy mechanism or the database provided by the nuclear power station operator or the supplier contains detailed information such as the type of the reactor, the fuel type and the like, and the data information of the nuclear power station comprises the type of the reactor, the fuel type and the like;
S200, acquiring electric energy generated by a target nuclear power station in unit time based on real-time data information of monitoring equipment, analyzing and judging the power generation efficiency of the target nuclear power station according to the electric energy generated by the target nuclear power station in unit time and the generated heat energy, and judging whether the target nuclear power station has a fault or not according to the power generation efficiency to determine a fault reason;
S300, constructing an abnormal grade evaluation model according to the fault cause of the nuclear power station, and evaluating the abnormal grade of the nuclear power station based on the abnormal grade evaluation model;
S400, determining an abnormal grade of the nuclear power station, and starting corresponding safety measures according to the abnormal grade.
Further, the specific method for analyzing the heat energy generated by the target nuclear power station in S100 is as follows:
S101, acquiring data information of the nuclear power station according to a data report provided by a nuclear energy mechanism, a nuclear power plant data information set Si is generated, si= { Si1, si2, si 3..sij.. SiJ }, i=1, 2, 3..i., I represents the total number of nuclear plants in the data report provided for the nuclear power institution, j=1, 2, 3..j, J being the number of acquired nuclear power plant data information; si is represented as the data information set of the i-th nuclear power plant, and Sij is represented as the j-th data information of the i-th nuclear power plant; according to the formula:
J(Si，Sa)＝|Si∩Sa|/|Si∪Sa|
Calculating to obtain the similarity of the data information set of the target nuclear power plant and the data information set of the nuclear power plant in a data report provided by a nuclear energy mechanism, wherein J (Si, sa) is represented as the similarity of the data information set Sa of the target nuclear power plant and the data information set of the ith nuclear power plant, |Si n Sa|is represented as the number of subsets of intersection sets of the data information set of the ith nuclear power plant and the target nuclear power plant, |Si n Sa is represented as the number of subsets of union sets of the data sets of the ith nuclear power plant and the target nuclear power plant, and Sa is represented as the data information set of the target nuclear power plant;
S102, sorting the nuclear power stations according to the sequence from high to low of the similarity of the data information sets among the nuclear power stations, selecting the nuclear power station with the highest similarity for marking, and marking the data information set as Si ', I' epsilon {1, 2, 3.. I }; since the thermal power of each nuclear power plant is not known to be present and the thermal power of the nuclear power plant is determined according to various factors such as the type, fuel type, design parameters, operating state and the like of the nuclear reactor, it is necessary to calculate the similarity according to the data information set of the nuclear power plant known originally, and calculate the nuclear power plant with the highest similarity so as to be able to predict the thermal power of the target nuclear power plant, so that the calculation formula of the thermal power of the nuclear reactor is utilized according to the data information set Si': p=v×u, and the heat generated by each nuclear reaction in the unit time can be obtained through calculation; wherein p is represented as the thermal power of a nuclear reactor in the nuclear power plant, v is represented as the nuclear reaction rate generated by fuel, u is represented as the average energy released by each nuclear reaction, the power heat depends on the rate of the nuclear reaction and the energy released by each nuclear reaction, and the thermal power of the nuclear reactor determines the power generation capacity and efficiency of the nuclear power plant;
S103, obtaining the number of nuclear reactors in the target nuclear power station, and calculating to obtain the total thermal power P=n×p generated by the target nuclear power station in unit time, wherein n is the total number of the nuclear reactors in the target nuclear power station.
Further, the specific method for analyzing and judging the power generation efficiency of the target nuclear power plant and judging the fault of the target nuclear power plant and determining the cause of the fault in S200 is as follows:
S201, acquiring the generated energy of the core power station in unit time as z according to the data information of the monitoring equipment for real-time monitoring of the target nuclear power station, and according to the formula: η= (z/P) ×100% and calculating to obtain the power generation efficiency η of the target nuclear power plant; when the power generation efficiency of the target nuclear power plant does not belong to a preset power generation efficiency threshold value range [ A, B ], judging that the target nuclear power plant has faults, wherein A is represented as a lower limit of the preset power generation efficiency threshold value, and B is represented as an upper limit of the preset power generation efficiency threshold value;
s202, when eta is more than or equal to B, judging that a nuclear power station data information set Si ' does not have timeliness and identifying the nuclear power station data information set Si ' in a data report provided by a nuclear energy mechanism and rejecting the nuclear power station data information set Si ' from a database because the internal equipment of a reactor is subjected to abrasion and ageing along with the operation of the nuclear power station when the thermal power P of a target nuclear power station is obtained by utilizing the similarity prediction of data information among the nuclear power stations, thereby influencing the performance of the internal equipment and further influencing the output of the thermal power;
When eta is less than or equal to A, the thermal power P of the target nuclear power station predicted by the similarity of data information among the nuclear power stations is larger than the thermal power of the target nuclear power station, so that the power generation efficiency of the nuclear power station is not in the preset power generation efficiency threshold range, the predicted thermal power of the target nuclear power station is judged to be larger than the actual thermal power, and cooling water is provided for the reactor due to the effect of a water intake, so that the normal operation of the reactor is maintained; when the cooling water is not supplied enough, the heat power output of the reactor is affected, namely, the water intake of the nuclear power station is judged to be abnormal, and warning and reminding are carried out.
Further, in S300: the specific method for evaluating the abnormal grade of the nuclear power station based on the abnormal grade evaluation model comprises the following steps:
S301, extracting water flow of a water intake through real-time monitoring data uploaded to a platform by a sensor in a target nuclear power station, wherein r=1, 2 and 3. Accumulating the number of the sensors with the value (vr/V) being less than or equal to V 'to obtain M [ (vr/V) being less than or equal to V' ], and when R-M [ (vr/V) being less than or equal to V '] is greater than or equal to M [ (vr/V) being less than or equal to V' ], indicating that the number of the sensors with normal water flow monitored at the water intake of the target nuclear power station is greater than or equal to the number of the sensors with abnormal water flow monitored, indicating that the data monitored by the sensors exist at the water intake of the target nuclear power station are inaccurate, thereby reducing the monitoring coverage rate of the water intake; according to the formula:
f＝F-k1/v-k2/{M[(vr/V)≤v’]/R}
Calculating to obtain the safety score of the water intake of the target nuclear power station; wherein F is expressed as a safety score of the water intake of the target nuclear power station, F is expressed as a safety initial score of the water intake of the nuclear power station, V is expressed as a maximum water flow allowed by the water intake of the target nuclear power station, V' is expressed as a preset threshold value of a water flow ratio of the water intake of the target nuclear power station, and k1 and k2 are respectively expressed as weight values;
S302, constructing an abnormal grade evaluation model:
Calculating to obtain the abnormal grade of the water intake of the target nuclear power station, and judging that the abnormal grade of the water intake of the target nuclear power station is high when Q=3; when q=2, determining that the abnormal grade of the water intake of the target nuclear power station is medium; when q=1, determining that the abnormality level of the water intake of the target nuclear power station is low; wherein Q is represented by a target nuclear power station water intake anomaly level, alpha is represented by an upper limit of a water intake safety score when the target nuclear power station water intake anomaly level is highest, beta is represented by an upper limit of a water intake safety score when the target nuclear power station water intake anomaly level is middle, and gamma is represented by an error value of the target nuclear power station water intake safety score because the safety score of the target nuclear power station water intake is unlikely to be full.
Further, the specific method for starting the corresponding security measures according to the abnormal level in S400 is as follows: the specific method for starting the corresponding security measures according to the abnormal level in S400 is as follows: when the abnormal level Q=3 of the water intake of the target nuclear power station, the water intake of the target nuclear power station is seriously blocked, so that a reactor in the nuclear power station is overheated and even a safety accident is caused; the blockage of the water intake can cause the faults of equipment such as a water pump, a cooling tower and the like, thereby affecting the stable operation of the nuclear power station, so that the operation of the nuclear power station needs to be stopped by emergency alarm and workers are arranged to completely maintain and overhaul the water intake of the nuclear power station immediately; when the abnormal level Q=2 of the water intake of the target nuclear power station, carrying out alarm reminding and reducing the operation load of the nuclear power station so as to reduce the requirement of cooling water; when the abnormal level Q=1 of the water intake of the target nuclear power station, reminding is carried out, and the abnormal condition is recorded and the personnel to be maintained.
The system and the method for safely managing the water intake of the nuclear power station comprise a data acquisition module, a data analysis module, a safety supervision module and an alarm reminding module; the output end of the data acquisition module is connected with the input end of the data analysis module, the output end of the data analysis module is connected with the input end of the safety supervision module, and the output end of the safety supervision module is connected with the input end of the alarm reminding module; the data acquisition module is used for acquiring data information of the nuclear power station and data information monitored by the sensor in real time; the data analysis module is used for analyzing the power generation efficiency of the nuclear power station and the fault reason of the nuclear power station; the safety supervision module analyzes the safety score of the water intake of the nuclear power station and determines the abnormal grade of the water intake of the nuclear power station, and corresponding emergency measures can be taken based on the abnormal grade of the water intake of the nuclear power station; the alarm reminding module carries out alarm reminding based on the abnormal grade of the water intake of the nuclear power station and takes safety measures corresponding to the abnormal grade of the water intake.
Further, the data acquisition module comprises a nuclear power station data information acquisition unit and a sensor monitoring data acquisition unit; the nuclear power station data information acquisition unit is used for acquiring data information of a nuclear power station, and according to the data information of the nuclear power station, the thermal power of the nuclear power station can be predicted so as to analyze and judge whether the power generation efficiency of the nuclear power station belongs to a normal range or not and further determine the cause of the nuclear power station fault; the sensor monitoring data acquisition unit is used for acquiring real-time monitoring data uploaded to the platform by the sensor after determining the fault cause of the nuclear power station.
Further, the data analysis module comprises a nuclear power station power generation efficiency analysis unit and a nuclear power station fault cause analysis unit; the power generation efficiency analysis unit of the nuclear power plant analyzes the power generation efficiency of the nuclear power plant according to the predicted thermal power of the nuclear power plant, and determines the cause of the failure of the nuclear power plant according to whether the power generation efficiency of the nuclear power plant belongs to a normal range; the nuclear power station fault cause analysis unit is used for analyzing the fault cause of the nuclear power station according to the efficiency of the nuclear power station.
Further, the safety supervision module comprises a nuclear power station water intake safety score analysis unit and an abnormal grade evaluation model construction unit; the safety score analysis unit of the water intake of the nuclear power station analyzes the safety score of the water intake of the nuclear power station according to the real-time monitoring data uploaded to the platform by the sensor; the abnormal grade evaluation model construction unit is used for constructing an abnormal grade evaluation model based on the safety score of the water intake of the nuclear power station, carrying out different grades of alarm reminding through the abnormal grade evaluation model and taking corresponding safety measures.
Further, the alarm reminding module comprises an alarm reminding unit and a safety measure decision unit; the alarm reminding unit carries out alarm reminding of different levels based on abnormal levels of the water intake of the nuclear power station; the security measure decision unit decides the security measure according to the alarm reminding level.
In this embodiment:
Acquiring data information of the nuclear power station according to a data report provided by a nuclear energy mechanism, and generating a nuclear power station data information set Si; according to the formula:
J(Si，Sa)＝|Si∩Sa|/|Si∪Sa|
Calculating to obtain the similarity of the data information set of the target nuclear power plant and the data information set of the nuclear power plant in a data report provided by the nuclear energy mechanism as {0.8, 0.9, 0.75 and 0.6. }; according to the similarity of data information sets among the nuclear power stations, the nuclear power stations are sequenced according to the sequence from high to low of the similarity to obtain {0.95, 0.9, 0.88 and 0.8..degree }, the nuclear power stations with the similarity of 0.95 are selected for marking, the data information sets are recorded as Si ', and a calculation formula of nuclear reactor thermal power is utilized according to the data information sets Si': p=v×u=47 (MW), and the heat generated by each nuclear reaction in the target nuclear power station in unit time can be obtained through calculation;
the method comprises the steps of obtaining the number n=3 of nuclear reactors in a target nuclear power station, and calculating to obtain the total thermal power P=n×p=3×47=141 (MW) generated by the target nuclear power station in unit time.
Acquiring the power generation amount of the core power station in unit time as z=35 according to the data information of the monitoring equipment for real-time monitoring of the target nuclear power station, and according to the formula: η= (z/P) ×100% = 25%, the power generation efficiency of the target nuclear power plant does not belong to a preset power generation efficiency threshold range [30%,35% ], and it is determined that a fault exists in the target nuclear power plant;
When η=25% < a=30%, it is indicated that the thermal power P of the target nuclear power plant predicted by using the similarity of the data information between the nuclear power plants is greatly different from the thermal power of the target nuclear power plant, so that the power generation efficiency of the nuclear power plant is not within the preset power generation efficiency threshold range, so that the predicted thermal power of the target nuclear power plant is determined to be greater than the actual thermal power, and cooling water is provided to the reactor due to the effect of the water intake, so that the normal operation of the reactor is maintained; when the cooling water is not supplied enough, the heat power output of the reactor is affected, namely, the water intake of the nuclear power station is judged to be abnormal, and warning and reminding are carried out.
It is noted that relational terms such as first and second, and the like are used solely to distinguish one entity or action from another entity or action without necessarily requiring or implying any actual such relationship or order between such entities or actions. Moreover, the terms "comprises," "comprising," or any other variation thereof, are intended to cover a non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements does not include only those elements but may include other elements not expressly listed or inherent to such process, method, article, or apparatus.
Finally, it should be noted that: the foregoing description is only a preferred embodiment of the present invention, and the present invention is not limited thereto, but it is to be understood that modifications and equivalents of some of the technical features described in the foregoing embodiments may be made by those skilled in the art, although the present invention has been described in detail with reference to the foregoing embodiments. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present invention should be included in the protection scope of the present invention.
Claims (10)
1. A nuclear power station water intake safety management method based on multi-source data is characterized by comprising the following steps: the nuclear power station water intake safety management method specifically comprises the following steps:
S100, acquiring data information of a nuclear power station according to a database provided by a nuclear energy mechanism, and analyzing and obtaining heat energy generated by a target nuclear power station based on the data information of the nuclear power station;
S200, acquiring electric energy generated by a target nuclear power station in unit time based on real-time data information of monitoring equipment, analyzing and judging the power generation efficiency of the target nuclear power station according to the electric energy generated by the target nuclear power station in unit time and the generated heat energy, and judging whether the target nuclear power station has a fault or not according to the power generation efficiency to determine a fault reason;
S300, constructing an abnormal grade evaluation model according to the fault cause of the nuclear power station, and evaluating the abnormal grade of the nuclear power station based on the abnormal grade evaluation model;
S400, determining an abnormal grade of the nuclear power station, and starting corresponding safety measures according to the abnormal grade.
2. The nuclear power station water intake safety management method based on multi-source data according to claim 1, wherein the method comprises the following steps: the specific method for analyzing the heat energy generated by the target nuclear power station in the S100 is as follows:
S101, acquiring data information of the nuclear power station according to a data report provided by a nuclear energy mechanism, a nuclear power plant data information set Si is generated, si= { Si1, si2, si 3..sij.. SiJ }, i=1, 2, 3..i., I represents the total number of nuclear plants in the data report provided for the nuclear power institution, j=1, 2, 3..j, J being the number of acquired nuclear power plant data information; si is represented as the data information set of the i-th nuclear power plant, and Sij is represented as the j-th data information of the i-th nuclear power plant; according to the formula:
J(Si，Sa)＝|Si∩Sa|/|Si∪Sa|
Calculating to obtain the similarity of the data information set of the target nuclear power plant and the data information set of the nuclear power plant in a data report provided by a nuclear energy mechanism, wherein J (Si, sa) is represented as the similarity of the data information set Sa of the target nuclear power plant and the data information set of the ith nuclear power plant, |Si n Sa|is represented as the number of subsets of intersection sets of the data information set of the ith nuclear power plant and the target nuclear power plant, |Si n Sa is represented as the number of subsets of union sets of the data sets of the ith nuclear power plant and the target nuclear power plant, and Sa is represented as the data information set of the target nuclear power plant;
S102, sorting the nuclear power stations according to the sequence from high to low of the similarity of the data information sets among the nuclear power stations, selecting the nuclear power station with the highest similarity for marking, and marking the data information set as Si ', I' epsilon {1, 2, 3.. I }; a calculation formula for utilizing nuclear reactor thermal power according to the data information set Si': p=v×u, and the heat generated by each nuclear reaction in the unit time can be obtained through calculation; where p is the thermal power of the nuclear reactor in the nuclear power plant, v is the rate of nuclear reactions produced by the fuel, and u is the average energy released by each nuclear reaction;
S103, obtaining the number of nuclear reactors in the target nuclear power station, and calculating to obtain the total thermal power P=n×p generated by the target nuclear power station in unit time, wherein n is the total number of the nuclear reactors in the target nuclear power station.
3. The nuclear power station water intake safety management method based on multi-source data according to claim 2, wherein the method comprises the following steps: the specific method for analyzing and judging the power generation efficiency of the target nuclear power plant and judging the fault of the target nuclear power plant and determining the cause of the fault in S200 is as follows:
S201, acquiring the generated energy of the core power station in unit time as z according to the data information of the monitoring equipment for real-time monitoring of the target nuclear power station, and according to the formula: η= (z/P) ×100% and calculating to obtain the power generation efficiency η of the target nuclear power plant; when the power generation efficiency of the target nuclear power plant does not belong to a preset power generation efficiency threshold value range [ A, B ], judging that the target nuclear power plant has faults, wherein A is represented as a lower limit of the preset power generation efficiency threshold value, and B is represented as an upper limit of the preset power generation efficiency threshold value;
S202, when eta is more than or equal to B, judging that the nuclear power station data information set Si ' has no timeliness, and identifying the nuclear power station data information set Si ' in a data report provided by a nuclear energy mechanism and removing the nuclear power station data information set Si ' from a database;
When eta is less than or equal to A, judging that the predicted thermal power of the target nuclear power plant is greater than the actual thermal power, namely judging that the water intake of the nuclear power plant is abnormal, and carrying out alarm reminding.
4. A nuclear power station water intake safety management method based on multi-source data according to claim 3, wherein: in the S300: the specific method for evaluating the abnormal grade of the nuclear power station based on the abnormal grade evaluation model comprises the following steps:
S301, extracting water flow of a water intake through real-time monitoring data uploaded to a platform by a sensor in a target nuclear power station, wherein r=1, 2 and 3. Accumulating the number of the sensors with the ratio of (vr/V) to V 'to obtain M [ (vr/V) to V' ]; according to the formula:
f＝F-k1/v-k2/{M[(vr/V)≤v’]/R}
Calculating to obtain the safety score of the water intake of the target nuclear power station; wherein F is expressed as a safety score of the water intake of the target nuclear power station, F is expressed as a safety initial score of the water intake of the nuclear power station, V is expressed as a maximum water flow allowed by the water intake of the target nuclear power station, V' is expressed as a preset threshold value of a water flow ratio of the water intake of the target nuclear power station, and k1 and k2 are respectively expressed as weight values;
S302, constructing an abnormal grade evaluation model:
Calculating to obtain the abnormal grade of the water intake of the target nuclear power station, and judging that the abnormal grade of the water intake of the target nuclear power station is high when Q=3; when q=2, determining that the abnormal grade of the water intake of the target nuclear power station is medium; when q=1, determining that the abnormality level of the water intake of the target nuclear power station is low; wherein Q is represented as a target nuclear power station water intake anomaly level, alpha is represented as an upper limit of a water intake safety score when the target nuclear power station water intake anomaly level is highest, beta is represented as an upper limit of a water intake safety score when the target nuclear power station water intake anomaly level is middle, and gamma is represented as an error value of the target nuclear power station water intake safety score.
5. The nuclear power station water intake safety management method based on multi-source data according to claim 4, wherein the method comprises the following steps: the specific method for starting the corresponding security measures according to the abnormal level in S400 is as follows: when the abnormal level Q=3 of the water intake of the target nuclear power station, emergency warning is carried out to stop the operation of the nuclear power station and the staff is arranged to carry out comprehensive maintenance and overhaul on the water intake of the nuclear power station immediately; when the abnormal level Q=2 of the water intake of the target nuclear power station, carrying out alarm reminding and reducing the operation load of the nuclear power station; when the abnormal level Q=1 of the water intake of the target nuclear power station, reminding is carried out, and the abnormal condition is recorded and the personnel to be maintained.
6. A nuclear power station water intake safety management system based on multi-source data is characterized in that: the nuclear power station water intake safety management system and method comprise a data acquisition module, a data analysis module, a safety supervision module and an alarm reminding module; the output end of the data acquisition module is connected with the input end of the data analysis module, the output end of the data analysis module is connected with the input end of the safety supervision module, and the output end of the safety supervision module is connected with the input end of the alarm reminding module; the data acquisition module is used for acquiring data information of the nuclear power station and data information monitored by the sensor in real time; the data analysis module is used for analyzing the power generation efficiency of the nuclear power station and the fault reason of the nuclear power station; the safety supervision module is used for analyzing the safety score of the water intake of the nuclear power station and determining the abnormal grade of the water intake of the nuclear power station; the alarm reminding module carries out alarm reminding based on the abnormal grade of the water intake of the nuclear power station and takes safety measures corresponding to the abnormal grade of the water intake.
7. The nuclear power station water intake safety management system based on multi-source data of claim 6, wherein: the data acquisition module comprises a nuclear power station data information acquisition unit and a sensor monitoring data acquisition unit; the nuclear power station data information acquisition unit is used for acquiring data information of the nuclear power station; the sensor monitoring data acquisition unit is used for acquiring real-time monitoring data uploaded to the platform by the sensor after determining the fault cause of the nuclear power station.
8. The nuclear power station water intake safety management system based on multi-source data of claim 7, wherein: the data analysis module comprises a nuclear power station power generation efficiency analysis unit and a nuclear power station fault reason analysis unit; the power generation efficiency analysis unit of the nuclear power station analyzes the power generation efficiency of the nuclear power station according to the predicted thermal power of the nuclear power station; the nuclear power station fault cause analysis unit is used for analyzing the fault cause of the nuclear power station according to the efficiency of the nuclear power station.
9. The nuclear power station water intake safety management system based on multi-source data of claim 8, wherein: the safety supervision module comprises a nuclear power station water intake safety score analysis unit and an abnormal grade assessment model construction unit; the safety score analysis unit of the water intake of the nuclear power station analyzes the safety score of the water intake of the nuclear power station according to the real-time monitoring data uploaded to the platform by the sensor; the abnormal grade evaluation model construction unit is used for constructing an abnormal grade evaluation model based on the safety score of the water intake of the nuclear power station.
10. The nuclear power station water intake safety management system based on multi-source data of claim 9, wherein: the alarm reminding module comprises an alarm reminding unit and a safety measure decision unit; the alarm reminding unit carries out alarm reminding of different levels based on abnormal levels of the water intake of the nuclear power station; the security measure decision unit decides the security measure according to the alarm reminding level.
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| CN105527113A (en) * | 2015-12-02 | 2016-04-27 | 中广核工程有限公司 | Nuclear power station thermal energy efficiency monitoring and diagnosing system and method |
| CN110926433A (en) * | 2019-11-28 | 2020-03-27 | 中国船舶重工集团公司第七一九研究所 | Marine disaster early warning system for coastal nuclear power station |
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| CN105527113A (en) * | 2015-12-02 | 2016-04-27 | 中广核工程有限公司 | Nuclear power station thermal energy efficiency monitoring and diagnosing system and method |
| CN110926433A (en) * | 2019-11-28 | 2020-03-27 | 中国船舶重工集团公司第七一九研究所 | Marine disaster early warning system for coastal nuclear power station |
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