Method, device and computer equipment for evaluating emergency state of nuclear power plant
By acquiring real-time monitoring data from nuclear power plants, analyzing the degree of data loss, and combining it with weighted factor calculations, the problem of inaccurate emergency state assessment in existing technologies has been solved, enabling more accurate emergency state judgment and improving the reliability of safe operation of nuclear power plants.
Patent Information
- Application Number
- CN202111526713.8
- Authority / Receiving Office
- CN · China
- Patent Type
- Patents(China)
- Current Assignee / Owner
- Filing Date
- 2021-12-14
- Publication Date
- 2026-02-06
- Estimated Expiration
- 2041-12-14
AI Technical Summary
Existing technologies lack quantitative standards for assessing the emergency status of nuclear power plants, resulting in overly selective data and significant data loss, making it impossible to accurately assess the emergency status.
By acquiring real-time monitoring data during unit operation, analyzing the degree of data loss, and combining the unit's operating status, a weighted factor is used to calculate the degree of loss of alarm data and parameter data, thereby determining the emergency status of the nuclear power plant.
This improves the accuracy of emergency status assessment, ensuring accurate judgment of the nuclear power plant's emergency status in the event of data loss, and enhancing the reliability of safe operation.
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Figure CN114186872B_ABST
Abstract
Description
TECHNICAL FIELD
[0001] The present application relates to the technical field of nuclear power, and in particular to an emergency state evaluation method and device for a nuclear power plant, a computer device, a storage medium, and a computer program product. BACKGROUND
[0002] With the development of nuclear power technology, after a nuclear accident occurs, it is necessary to quickly and effectively control the nuclear accident and mitigate its consequences. Therefore, a nuclear power plant must have a detailed nuclear accident emergency plan and sufficient emergency preparation.
[0003] In the traditional technology, a large number of alarms and parameter indications are generally used to prompt the staff, and the staff classifies the emergency state according to the alarms and parameter indications, thereby ensuring the safe operation of the nuclear power plant.
[0004] However, considering conditions such as partial software common cause failure of a digital control system (DCS), when using existing technology to evaluate the emergency state, there are inevitably problems such as no executable quantitative standard, too one-sided data selection, and large-area data loss, which result in the inability to accurately evaluate the emergency state. SUMMARY
[0005] Therefore, it is necessary to provide an emergency state evaluation method and device for a nuclear power plant, a computer device, a computer readable storage medium, and a computer program product, which can improve the accuracy of emergency state evaluation of a nuclear power plant.
[0006] In a first aspect, the present application provides an emergency state evaluation method for a nuclear power plant, the method comprising:
[0007] obtaining real-time monitoring data during unit operation, the real-time monitoring data being data related to the safety function of the nuclear power plant system;
[0008] analyzing the data loss degree of the real-time monitoring data to obtain a data loss degree analysis result;
[0009] if the data loss degree analysis result meets a preset data loss degree condition, determining the emergency state of the nuclear power plant in combination with the operating state of the unit.
[0010] In one embodiment, the real-time monitoring data includes alarm data; and the step of analyzing the data loss degree of the real-time monitoring data to obtain a data loss degree analysis result comprises:
[0011] extracting each safety important alarm data in the alarm data; counting each of the safety important alarm data to obtain an alarm data quantity of each safety important alarm level; analyzing an alarm data loss degree of the safety important alarm data based on the alarm data quantity of each safety important alarm level and a corresponding alarm weight factor, wherein the data loss degree analysis result comprises the alarm data loss degree.
[0012] In one of the embodiments, the real-time monitoring data comprises parameter data; the analyzing of the data loss degree of the real-time monitoring data to obtain a data loss degree analysis result comprises:
[0013] extracting safety important parameter data in the parameter data; counting each of the safety important parameter data to obtain a parameter data quantity of each safety important parameter level; analyzing a parameter data loss degree of the safety important parameter data based on the parameter data quantity of each safety important parameter level and a corresponding parameter weight factor, wherein the data loss degree analysis result comprises the parameter data loss degree.
[0014] In one of the embodiments, the safety important alarm data carries an alarm data state.
[0015] The method further comprises: counting an invalid alarm data quantity of each of the safety important alarm levels in which the alarm data state is invalid in each of the safety important alarm data.
[0016] The analyzing of the alarm data loss degree of the safety important alarm data based on the alarm data quantity of each safety important alarm level and a corresponding alarm weight factor comprises:
[0017] multiplying the alarm data quantity of each of the safety important alarm levels and the corresponding alarm weight factor to obtain each initial weighted alarm quantity.
[0018] multiplying the invalid alarm data quantity of each of the safety important alarm levels and the corresponding alarm weight factor to obtain each initial weighted invalid alarm quantity.
[0019] analyzing and obtaining the alarm data loss degree of the safety important alarm data based on each of the initial weighted alarm quantity and each of the initial weighted invalid alarm quantity.
[0020] In one of the embodiments, the analyzing and obtaining of the alarm data loss degree of the safety important alarm data based on each of the initial weighted alarm quantity and each of the initial weighted invalid alarm quantity comprises:
[0021] A ratio of a target weighted invalid alarm quantity to the target weighted alarm quantity is taken as the alarm data loss degree, the target weighted invalid alarm quantity being a sum of the initial weighted alarm quantities, and the target weighted alarm quantity being a sum of the initial weighted invalid alarm quantities.
[0022] In one of the embodiments, the security important parameter data carries a parameter data state.
[0023] The method further includes: counting an invalid parameter data quantity of each security important parameter level in which the parameter data state is invalid in each security important parameter data.
[0024] The parameter data loss degree of the security important parameter data is analyzed based on the parameter data quantity of each security important parameter level and the corresponding parameter weight factor, including:
[0025] The parameter data quantity of each security important parameter level is multiplied by the corresponding parameter weight factor to obtain an initial weighted parameter quantity.
[0026] The invalid parameter data quantity of each security important parameter level is multiplied by the corresponding parameter weight factor to obtain an initial weighted invalid parameter quantity.
[0027] The parameter data loss degree of the security important parameter data is analyzed based on the initial weighted parameter quantity and the initial weighted invalid parameter quantity.
[0028] In one of the embodiments, the parameter data loss degree of the security important parameter data is analyzed based on the initial weighted parameter quantity and the initial weighted invalid parameter quantity, including:
[0029] A ratio of a target weighted invalid parameter quantity to a target weighted parameter quantity is taken as the parameter data loss degree, the target weighted invalid parameter quantity being a sum of the initial weighted parameter quantities, and the target weighted parameter quantity being a sum of the initial weighted invalid parameter quantities.
[0030] In one of the embodiments, if the ratio of the target weighted invalid alarm quantity to the target weighted alarm quantity is greater than a first preset ratio, it is determined that the data loss degree analysis result meets a preset data loss degree condition.
[0031] In one of the embodiments, if the ratio of the target weighted invalid parameter quantity to the target weighted parameter quantity is greater than a second preset ratio, it is determined that the data loss degree analysis result meets a preset data loss degree condition.
[0032] In one of the embodiments, if the data loss degree analysis result meets the preset data loss degree condition, and in combination with the operation state of the unit, the emergency state of the nuclear power plant is determined, including:
[0033] If the data loss degree analysis result meets the preset data loss degree condition, and the operation state of the unit is the steady state, the emergency state of the nuclear power plant is determined as the emergency standby state.
[0034] In one of the embodiments, if the data loss degree analysis result meets the preset data loss degree condition, and in combination with the operation state of the unit, the emergency state of the nuclear power plant is determined, including:
[0035] If the data loss degree analysis result meets the preset data loss degree condition, and the operation state of the unit is the transient state, if within a preset time period, the operation state of the unit changes from the transient state to the steady state, the emergency state of the nuclear power plant is determined as the plant emergency state.
[0036] In one of the embodiments, if the data loss degree analysis result meets the preset data loss degree condition, and in combination with the operation state of the unit, the emergency state of the nuclear power plant is determined, including:
[0037] If the data loss degree analysis result meets the preset data loss degree condition, and the operation state of the unit is the transient state, if within a preset time period, the operation state of the unit still remains the transient state, the emergency state of the nuclear power plant is determined as the site emergency state.
[0038] In one of the embodiments, the operation state of the unit is determined as the transient state, including: if a shutdown signal is received, the operation state of the unit is determined as the transient state.
[0039] In one of the embodiments, the operation state of the unit is determined as the transient state, including: if a safety injection system trigger signal is received, the operation state of the unit is determined as the transient state.
[0040] In one of the embodiments, the operation state of the unit is determined as the transient state, including: if the steam turbine load data meets a preset steam turbine load data condition, the operation state of the unit is determined as the transient state.
[0041] In one of the embodiments, the operation state of the unit is determined as the transient state, including: if the reactor load data meets a preset reactor load condition, the operation state of the unit is determined as the transient state.
[0042] In a second aspect, the application further provides an emergency state evaluation device of a nuclear power plant, the device comprising:
[0043] a data acquisition module configured to acquire real-time monitoring data of the unit operation, the real-time monitoring data being data related to the safety function of the nuclear power plant system;
[0044] a data analysis module configured to analyze a data loss degree of the real-time monitoring data and obtain a data loss degree analysis result;
[0045] an emergency state evaluation module configured to determine an emergency state of the nuclear power plant based on the data loss degree analysis result and the operation state of the unit if the data loss degree analysis result meets a preset data loss degree condition.
[0046] In a third aspect, the present application provides a computer device, comprising a memory and a processor, wherein the memory stores a computer program, and the processor implements the steps of the method described above when executing the computer program.
[0047] In a fourth aspect, the present application provides a computer readable storage medium, which stores a computer program, and the computer program implements the steps of the method described above when executed by a processor.
[0048] In a fifth aspect, the present application provides a computer program product, which comprises a computer program, and the computer program implements the steps of the method described above when executed by a processor.
[0049] The method, device, computer device, storage medium and computer program product for evaluating the emergency state of the nuclear power plant described above can acquire real-time monitoring data of the unit operation, analyze the data loss degree of the real-time monitoring data and obtain a data loss degree analysis result, so that the emergency state of the nuclear power plant can be determined based on the data loss degree analysis result and the operation state of the unit if the data loss degree analysis result meets a preset data loss degree condition. The above method can improve the evaluation accuracy of the emergency state. BRIEF DESCRIPTION OF DRAWINGS
[0050] Figure 1 FIG. 1 is a diagram of an application environment of the method for evaluating the emergency state of the nuclear power plant in one embodiment;
[0051] Figure 2 FIG. 2 is a flowchart of the method for evaluating the emergency state of the nuclear power plant in one embodiment;
[0052] Figure 3 FIG. 3 is a flowchart of the method for evaluating the emergency state of the nuclear power plant in one embodiment;
[0053] Figure 4 FIG. 4 is a flowchart of the method for evaluating the emergency state of the nuclear power plant in another embodiment;
[0054] Figure 5A flowchart of an emergency state evaluation method of a nuclear power plant in another embodiment;
[0055] Figure 6 A structural block diagram of an emergency state evaluation device of a nuclear power plant in an embodiment;
[0056] Figure 7 An internal structure diagram of a computer device in an embodiment;
[0057] Figure 8 An internal structure diagram of a computer device in an embodiment. DETAILED DESCRIPTION
[0058] In order to make the purposes, technical solutions and advantages of the present application clearer, the present application is further described in detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are only used to explain the present application and not intended to limit the present application.
[0059] The emergency state evaluation method of a nuclear power plant provided by the embodiments of the present application can be applied in an application environment as shown in Figure 1 , which involves various data monitoring devices such as instrument 1, instrument 2, sensor 1 and sensor N. The various data monitoring devices can be used to monitor various types of data when each unit in the nuclear power plant is running, such as reactor state information (reactor nuclear power, core thermal power, electric power, etc.), alarm data (reactor coolant loop flow low alarm, steam generator leakage rate high alarm, steam generator gamma radioactivity high alarm, etc.), parameter data (stabilizer liquid level, core coolant outlet temperature, high-pressure safety injection system flow, steam generator secondary side pressure, etc.), and equipment operation state feedback information (pump operation state feedback information, valve opening and closing position state feedback information, etc.). Various types of real-time monitoring data can be transmitted to the plant-level management device 102 through a network, and the plant-level management device 102 analyzes the data loss degree of the real-time monitoring data to obtain a data loss degree analysis result. If the data loss degree analysis result meets a preset data loss degree condition, the emergency state of the nuclear power plant is determined in combination with the operation state of the unit. The plant-level management device 102 can be, but is not limited to, various personal computers, notebook computers, smart phones, tablet computers, Internet of Things devices and portable wearable devices. The plant-level management device 102 can also be a server, which can be implemented by an independent server or a server cluster composed of multiple servers.
[0060] In an embodiment, as shown in Figure 2 , an emergency state evaluation method of a nuclear power plant is provided. The method is described below by taking the plant-level management device 102 in Figure 1 as an example, which includes the following steps:
[0061] In step S202, real-time monitoring data of the unit operation is acquired, wherein the real-time monitoring data is data related to the safety function of the nuclear power plant system.
[0062] The real-time monitoring data refers to data related to the safety function of the nuclear power plant system during the operation of the unit. Specifically, the real-time monitoring data can include reactor state information (reactor nuclear power, reactor core thermal power, electric power, etc.), alarm data (reactor coolant loop flow low alarm, steam generator leakage rate high alarm, steam generator gamma radioactivity high alarm, etc.), parameter information (stabilizer liquid level, reactor coolant outlet temperature, high-pressure safety injection system flow, steam generator secondary side pressure, etc.), and device operation state feedback information (pump operation state feedback information, valve opening and closing position state feedback information, etc.).
[0063] In step S204, the data loss degree of the real-time monitoring data is analyzed to obtain a data loss degree analysis result.
[0064] The data loss degree can be used to indicate how much the real-time monitoring data is lost. By analyzing the real-time monitoring data, the data loss degree analysis result can be obtained.
[0065] In step S206, if the data loss degree analysis result meets a preset data loss degree condition, the emergency state of the nuclear power plant is determined in combination with the operation state of the unit.
[0066] The preset data loss degree condition refers to a condition for judging the data loss degree of the data loss degree analysis result. The operation state of the unit refers to the actual operation of the unit, which can include a steady state and a transient state. The emergency state of the nuclear power plant refers to an emergency mode determined according to the data loss degree analysis result and the operation state of the unit.
[0067] The steady state of the unit refers to a steady and normal operation of the unit. The transient state of the unit refers to a transient state deviating from the normal operation, which can be caused by a unit fault.
[0068] In one embodiment, the operation state of the unit is determined as the transient state, including: if a shutdown signal is received, the operation state of the unit is determined as the transient state.
[0069] The trip signal triggering can represent automatic action of the reactor protection system caused by failure of some systems and devices in the nuclear power plant (such as power distribution panel power failure, containment control system failure, main feedwater system failure, etc.), and the trip signal can be obtained from a trip breaker opening signal of the reactor protection system (such as for a certain pressurized water reactor nuclear power plant: the trip breaker is configured as "4-to-2", and one pair of trip breakers is opened to generate the trip signal), and the trip signal can be directly obtained by the plant-level management device.
[0070] In one of the embodiments, determining the operation state of the unit as a transient operation state comprises: if the safety injection system triggering signal is received, determining the operation state of the unit as a transient operation state.
[0071] The safety injection system triggering signal triggering can represent automatic action of the safety injection system caused by failure of systems or devices of the nuclear power plant (such as reactor coolant system pipe rupture, main steam pipe rupture, steam generator U-tube rupture, etc.) threatening the core cooling, and the safety injection system triggering signal can be obtained from a safety injection system automatic triggering signal of the reactor protection system (in the reactor protection system, a plurality of safety injection system automatic triggering logics are generally set to cover all possible accident conditions. For example: stable pressure "3-to-2" logic, containment pressure "4-to-2" logic, etc., which can all generate the safety injection system triggering signal), and the safety injection system triggering signal can be directly obtained by the plant-level management device.
[0072] In one of the embodiments, determining the operation state of the unit as a transient operation state comprises: if the steam turbine load data meets a preset steam turbine load data condition, determining the operation state of the unit as a transient operation state.
[0073] The preset steam turbine load data condition refers to a condition for judging whether the steam turbine load data is qualified, and during normal operation of the unit, the steam turbine can be operated at 100% full load. For example, if the steam turbine load reduction amplitude exceeds 25% (reduced to below 75%), it can be considered that the steam turbine load data meets the preset steam turbine load data condition, i.e., a transient operation state occurs, and the steam turbine load data can be directly obtained by the plant-level management device.
[0074] In one of the embodiments, determining the operation state of the unit as a transient operation state comprises: if the reactor load data meets a preset reactor load condition, determining the operation state of the unit as a transient operation state.
[0075] The preset reactor load condition refers to a condition for judging whether the reactor load data is qualified. During normal operation of the unit, the reactor is operated at 100% full load. For example, if the reactor load is reduced by more than 25% (to less than 75%), it can be considered that the reactor load data meets the preset reactor load condition, that is, an operating transient occurs, and the reactor load data can be directly obtained by the plant-level management device.
[0076] In one embodiment, the preset data loss degree condition can be a set data loss percentage, which can be adjusted according to actual conditions. By comparing the data loss degree analysis result with the data loss percentage, it can be determined whether the data loss degree analysis result meets the preset data loss degree condition.
[0077] In the above method for evaluating the emergency state of the nuclear power plant, real-time monitoring data during operation of the unit is obtained, and the data loss degree of the real-time monitoring data is analyzed to obtain a data loss degree analysis result. Therefore, when the data loss degree analysis result meets the preset data loss degree condition, the emergency state of the nuclear power plant can be determined according to the data loss degree analysis result and the operating state of the unit. The above method can improve the evaluation accuracy of the emergency state.
[0078] In one embodiment, the real-time monitoring data includes alarm data. The analysis of the data loss degree of the real-time monitoring data to obtain a data loss degree analysis result includes:
[0079] Each safety important alarm data in the alarm data is extracted. The number of alarm data of each safety important alarm level is obtained by counting each safety important alarm data. Based on the number of alarm data of each safety important alarm level and the corresponding alarm weight factor, the alarm data loss degree of the safety important alarm data is analyzed. The data loss degree analysis result includes the alarm data loss degree.
[0080] In one embodiment, the alarm data refers to data used to prompt when various units of the nuclear power plant and the like have operating abnormalities or operating accidents. Through the alarm data, the staff can intervene in various accidents. The alarm data can include safety important alarm data and non-safety important alarm data. In this embodiment, the safety important alarm data is extracted and analyzed considering the impact on the safe operation of the unit.
[0081] In one of the embodiments, the safety important alarm data refers to alarm data required for a nuclear power plant system to perform its safety functions, the three safety functions of a nuclear power plant include: safe shutdown and maintenance of a safe shutdown state (reactivity control), residual heat removal after shutdown (residual heat removal), and prevention of radioactive material from entering the environment (radioactive containment), the safety function performed by the safety important alarm data is to prevent the three safety functions from failing in principle, and typical safety important alarm data can include: an entry alarm indicating an accident operation, an alarm indicating a serious degradation of the reactor core cooling state, an alarm indicating a steam generator U-tube break, an alarm indicating a loss of dedicated safety system, etc. Non-safety important alarm data does not perform safety functions, and is generally used to indicate operation abnormalities of non-safety level equipment that maintains normal operation of the nuclear power plant.
[0082] In one of the embodiments, the safety important alarm level refers to a level divided for each safety important alarm data, wherein, when dividing the level, the safety important alarm data can be divided according to the emergency degree, and colors can be used to identify the safety important alarm data of each emergency degree, and for the safety important alarm data of each emergency degree, a corresponding alarm weight factor is given, specifically, the alarm weight factor of the safety important alarm data with a higher emergency degree can be greater than the alarm weight factor of the safety important alarm data with a lower emergency degree.
[0083] In one of the embodiments, according to the emergency degree from heavy to light, the safety important alarm data can be respectively given a corresponding red identification, orange identification, yellow identification and green identification, and different alarm weight factors are respectively given according to the emergency degree, specifically, the alarm weight factor corresponding to the red identification can be 1.0, the alarm weight factor corresponding to the orange identification can be 0.7, the alarm weight factor corresponding to the yellow identification can be 0.3, and the alarm weight factor corresponding to the green identification can be 0.1.
[0084] Among them, by extracting only each safety important alarm data in the alarm data, the probability of safe operation of the unit can be improved, and each safety important alarm data is counted to obtain the number of alarm data of each safety important alarm level, based on the number of alarm data of each safety important alarm level and the corresponding alarm weight factor, the alarm data loss degree of the safety important alarm data is analyzed, since the number of safety important alarm data and the corresponding alarm weight factor are considered, the analysis accuracy of the alarm data loss degree can be improved by the above method.
[0085] In one of the embodiments, the real-time monitoring data includes parameter data; the analysis of the data loss degree of the real-time monitoring data to obtain the data loss degree analysis result includes:
[0086] extracting security important parameter data in the parameter data; counting each security important parameter data to obtain parameter data quantity of each security important parameter level; analyzing parameter data loss degree of the security important parameter data based on the parameter data quantity of each security important parameter level and corresponding parameter weight factor, wherein the data loss degree analysis result comprises the parameter data loss degree.
[0087] In one of the embodiments, the parameter data refers to state parameter information and operation state information during operation of the unit. The parameter data can comprise security important parameter data and non-security important parameter data. In this embodiment, the security important parameter data is extracted for analysis in view of the influence on safe operation of the unit.
[0088] In one of the embodiments, the security important parameter data refers to parameter data required by a nuclear power plant system to perform its safety function. The three safety functions of the nuclear power plant include: safe shutdown and maintenance of safe shutdown state (reactivity control), residual heat removal after shutdown (residual heat removal), and prevention of radioactive substances from entering the environment (radioactive containment). The safety function performed by the security important parameter data is to prevent the three safety functions from failing in principle. Typical security important parameter data includes: reactor pressure vessel water level, core outlet coolant subcooling degree, core subcriticality, steam generator radioactivity, containment pressure, etc. The non-security important parameter data does not perform safety function, and is generally used to indicate the operation state of non-safety level equipment for maintaining normal operation of the nuclear power plant, such as normal operation feedwater flow and normal operation feedwater temperature.
[0089] In one of the embodiments, the security important parameter level refers to a level divided for each security important parameter data. When dividing the level, the security important parameter data can be divided according to the importance degree, and numbers, letters, and feature codes can be used to identify the security important parameter data of each importance degree. In addition, for the security important parameter data of each importance degree, a corresponding parameter weight factor is assigned. Specifically, the parameter weight factor of the security important parameter data with higher importance degree can be greater than the parameter weight factor of the security important parameter data with lower importance degree.
[0090] In one of the embodiments, according to the importance degree from high to low, the security important parameter data can be divided into first type parameter PAMS1, second type parameter PAMS2, etc. Different parameter weight factors are assigned according to the importance degree. Specifically, the parameter weight factor corresponding to PAMS1 can be 1.0, and the alarm weight factor corresponding to PAMS2 can be 0.5.
[0091] The safety important parameter data is extracted from the parameter data, so that the probability of safe operation of the unit is improved, and the safety important parameter data is counted to obtain the parameter data quantity of each safety important parameter level. Based on the parameter data quantity of each safety important parameter level and the corresponding parameter weight factor, the parameter data loss degree of the safety important parameter data is analyzed. Since the number of safety important parameter data and the corresponding parameter weight factor are considered, the analysis accuracy of the parameter data loss degree can be improved by the above method.
[0092] In one of the embodiments, the safety important alarm data carries alarm data state; the method further comprises: counting the invalid alarm data quantity of each safety important alarm level in which the alarm data state of each safety important alarm data is invalid.
[0093] The alarm data state is information indicating the state of the alarm data, and the state of the alarm data can include a valid state and an invalid state. The valid state can mean that the alarm data is normal, and the invalid state can mean that the alarm data is abnormal.
[0094] Therefore, the analysis of the alarm data loss degree of the safety important alarm data based on the alarm data quantity of each safety important alarm level and the corresponding alarm weight factor comprises:
[0095] In step S302, the alarm data quantity of each safety important alarm level and the corresponding alarm weight factor are multiplied to obtain each initial weighted alarm quantity.
[0096] Each safety important alarm level corresponds to a corresponding alarm data quantity.
[0097] In step S304, the invalid alarm data quantity of each safety important alarm level and the corresponding alarm weight factor are multiplied to obtain each initial weighted invalid alarm quantity.
[0098] The safety important alarm data can be determined to be invalid safety important alarm data or valid safety important alarm data according to the alarm data state.
[0099] In step S306, the alarm data loss degree of the safety important alarm data is analyzed based on each initial weighted alarm quantity and each initial weighted invalid alarm quantity.
[0100] In one embodiment, the initial weighted alarm quantity is obtained by multiplying the alarm data quantity of each security important alarm level by the corresponding alarm weight factor, and the initial weighted invalid alarm quantity is obtained by multiplying the invalid alarm data quantity of each security important alarm level by the corresponding alarm weight factor. By comprehensively considering the two factors of weight and quantity, the accuracy of the obtained alarm data loss degree can be improved.
[0101] In one embodiment, the analysis of the alarm data loss degree of the security important alarm data based on the initial weighted alarm quantity and the initial weighted invalid alarm quantity comprises:
[0102] The ratio of the target weighted invalid alarm quantity to the target weighted alarm quantity is taken as the alarm data loss degree, the target weighted invalid alarm quantity is the sum of the initial weighted alarm quantities, and the target weighted alarm quantity is the sum of the initial weighted invalid alarm quantities.
[0103] In one embodiment, reference is made to formula 1:
[0104] S A = K R × A R + K O × A O + K Y × A Y + K G × A G
[0105] wherein S A represents the target weighted alarm quantity, K R may represent the alarm weight factor corresponding to one security important alarm level, A R represents the alarm data quantity of the security important alarm level, K O may represent the alarm weight factor corresponding to another security important alarm level, A O represents the alarm data quantity of the security important alarm level, K Y may represent the alarm weight factor corresponding to another security important alarm level, and A Y represents the alarm data quantity of the security important alarm level. Thus, the target weighted alarm quantity can be determined.
[0106] In one embodiment, reference is made to formula 2:
[0107] IS A = K R × LA R + K O × LA O + K YX LA Y + K G X LA G
[0108] wherein, IS A represents the target weighted invalid alarm quantity, K R may represent an alarm weight factor corresponding to a safety important alarm level, LA R represents the invalid alarm data quantity of the safety important alarm level, K O may represent an alarm weight factor corresponding to another safety important alarm level, LA O represents the invalid alarm data quantity of the safety important alarm level, LA Y may represent an alarm weight factor corresponding to another safety important alarm level, LA G represents the invalid alarm data quantity of the safety important alarm level. Thus, the target weighted invalid alarm quantity can be determined.
[0109] In one of the embodiments, after the target weighted alarm quantity and the target weighted invalid alarm data are determined, the ratio of the target weighted invalid alarm quantity to the target weighted alarm quantity can be taken as the alarm data loss degree. If the ratio of the target weighted invalid alarm quantity to the target weighted alarm quantity is greater than a first preset ratio, it is determined that the data loss degree analysis result meets the preset data loss degree condition, wherein the first preset ratio is a condition for judging the data loss degree, and the first preset ratio can be adjusted according to actual conditions.
[0110] In one of the embodiments, the safety important parameter data carries parameter data states; the method further comprises: counting the invalid parameter data quantity of each safety important parameter level in which the parameter data state is invalid.
[0111] wherein, the parameter data state refers to information indicating the state of the parameter data, and the state of the parameter data can include a valid state and an invalid state, wherein the valid state can mean that the parameter data is normal, and the invalid state can mean that the parameter data is abnormal.
[0112] Therefore, the analysis of the parameter data loss degree of the safety important parameter data based on the parameter data quantity of each safety important parameter level and the corresponding parameter weight factor comprises:
[0113] In step S402, the parameter data quantity of each safety important parameter level and the corresponding parameter weight factor are multiplied to obtain each initial weighted parameter quantity.
[0114] wherein, each safety important parameter level corresponds to a corresponding parameter data quantity.
[0115] Step S404, multiplying the invalid parameter data quantity of each security important parameter level and the corresponding parameter weight factor to obtain each initial weighted invalid parameter quantity.
[0116] Wherein, the security important parameter data can be determined according to the parameter data state whether it is invalid security important parameter data or valid security important parameter data.
[0117] Step S406, based on each initial weighted parameter quantity and each initial weighted invalid parameter quantity, analyzing to obtain the parameter data loss degree of the security important parameter data.
[0118] In one embodiment, by multiplying the parameter data quantity of each security important level and the corresponding parameter weight factor, the initial weighted parameter quantity can be obtained, multiplying the invalid parameter data quantity of each security important parameter level and the corresponding parameter weight factor to obtain each initial weighted invalid parameter quantity, by comprehensively considering the two factors of weight and quantity, the accuracy of the finally obtained parameter data loss degree can be improved.
[0119] In one embodiment, the security important parameter data based on each initial weighted parameter quantity and each initial weighted invalid parameter quantity, analyzing to obtain the parameter data loss degree, includes:
[0120] The ratio of the target weighted invalid parameter quantity and the target weighted parameter quantity is taken as the parameter data loss degree, the target weighted invalid parameter quantity is the sum value of each initial weighted parameter quantity, and the target weighted parameter quantity is the sum value of each initial weighted invalid parameter quantity.
[0121] In one embodiment, reference is made to formula 3 as shown:
[0122] S PAMS = K PAMS1 × T PAMSI + K PAMS2 × T PAMS2
[0123] Wherein, S PAMS represents the target weighted parameter quantity, K PAMS1 may represent a parameter weight factor corresponding to a security important parameter level, T PAMSI represents the parameter data quantity of the security important parameter level, K PAMS2 may represent a parameter weight factor corresponding to another security important parameter level, T PAMS2 represents the parameter data quantity of the security important parameter level.
[0124] In one embodiment, reference is made to formula 4 as shown:
[0125] IS PAMS =K PAMS1 ×IT PAMSI +K PAMS2 ×IT PAMS2
[0126] Among them, IS PAMS K represents the number of weighted invalid parameters in the target. PAMS1 This can represent a parameter weighting factor corresponding to a security importance parameter level, IT PAMSI K represents the number of invalid parameter data at this level of safety importance. PAMS2 This can represent a parameter weighting factor corresponding to another level of security importance, IT PAMS2 This indicates the number of invalid parameter data at this level of safety importance.
[0127] In one embodiment, after determining the target number of weighted parameters and the target number of invalid parameters, the ratio of the target number of invalid parameters to the target number of weighted parameters can be used as the alarm data loss degree. If the ratio of the target number of invalid parameters to the target number of weighted parameters is greater than a second preset ratio, the data loss degree analysis result is determined to meet the preset data loss degree condition. The second preset ratio is a pre-set condition for judging the data loss degree, and the second preset ratio can be adjusted according to the actual situation.
[0128] In one embodiment, if the data loss level analysis result meets a preset data loss level condition, and the emergency status of the nuclear power plant is determined in conjunction with the unit's operating status, the process includes:
[0129] If the data loss level analysis results meet the preset data loss level conditions, and the unit's operating state is in steady state, then the nuclear power plant's emergency status is determined to be an emergency standby state.
[0130] In one embodiment, the emergency status of the nuclear power plant is determined to be an emergency standby state when the data loss level analysis results meet the preset data loss level conditions and the unit's operating state is in a steady state.
[0131] In one embodiment, if the data loss level analysis result meets a preset data loss level condition, and the emergency status of the nuclear power plant is determined in conjunction with the unit's operating status, the process includes:
[0132] If the data loss level analysis results meet the preset data loss level conditions, the unit's operating state is a transient operating state. If the unit's operating state changes from a transient operating state to a steady operating state within a preset time period, the nuclear power plant's emergency state is determined to be a plant emergency state.
[0133] In one of the embodiments, taking the operation transient triggered by the trip signal as an example, if the control rod drive mechanism power supply has been disconnected, the auxiliary feedwater pump is in good condition, the feedwater regulating valve is open, the atmospheric release valve is field adjustable, the auxiliary feedwater tank has sufficient water storage, and the loop pressure boundary remains intact (no coolant leakage), etc. within a predetermined time period, it is considered that the operation state is changed from the operation transient to the operation steady state. When the data loss degree analysis result meets the preset data loss degree condition, it is determined that the emergency state of the nuclear power plant is the plant emergency state.
[0134] In one of the embodiments, when the data loss degree analysis result meets the preset data loss degree condition, the emergency state of the nuclear power plant is determined in combination with the operation state of the unit, which includes:
[0135] If the data loss degree analysis result meets the preset data loss degree condition, and the operation state of the unit is the operation transient, if the operation state of the unit remains the operation transient within a predetermined time period, it is determined that the emergency state of the nuclear power plant is the site emergency state.
[0136] In one of the embodiments, if the operation transient of the unit cannot be effectively controlled within a predetermined time period, the emergency state classification needs to be further upgraded, that is, it is determined that the emergency state of the nuclear power plant is the site emergency state.
[0137] In one of the embodiments, as shown in the flowchart of the emergency state evaluation method of the nuclear power plant in one specific embodiment: Figure 5
[0138] First, real-time monitoring data during unit operation is obtained, wherein the real-time monitoring data includes alarm data and parameter data. The alarm data refers to data used for prompting when various devices in the nuclear power plant appear operation abnormities or operation accidents occur. Through the alarm data, the staff can intervene in various accidents. The parameter data refers to state parameter information and operation state information during unit operation, etc.
[0139] After obtaining the alarm data and the parameter data, the alarm data and the parameter can be analyzed to obtain a data loss degree analysis result. Specifically, in processing the alarm data, each safety important alarm data in the alarm data can be extracted. The number of alarm data of each safety important alarm level is obtained by counting each safety important alarm data. Based on the number of alarm data of each safety important alarm level and the corresponding alarm weight factor, the alarm data loss degree of the safety important alarm data is analyzed. The data loss degree analysis result includes the alarm data loss degree.
[0140] The alarm data quantity of each security importance level is multiplied by the corresponding alarm weight factor to obtain an initial weighted alarm quantity, and the invalid alarm data quantity of each security importance alarm level is multiplied by the corresponding alarm weight factor to obtain an initial weighted invalid alarm quantity. By comprehensively considering the two factors of weight and quantity, the accuracy of the finally obtained alarm data loss degree can be improved.
[0141] The ratio of the target weighted invalid alarm quantity to the target weighted alarm quantity is taken as the alarm data loss degree. The target weighted invalid alarm quantity is the sum of the initial weighted alarm quantities, and the target weighted alarm quantity is the sum of the initial weighted invalid alarm quantities. If the ratio of the target weighted invalid alarm quantity to the target weighted alarm quantity is greater than a first preset ratio, it is determined that the data loss degree analysis result meets the preset data loss degree condition. The first preset ratio is a condition for judging the data loss degree, and the first preset ratio can be adjusted according to actual conditions.
[0142] In processing the parameter data, the security important parameter data in the parameter data can be extracted. Each security important parameter data is counted to obtain the parameter data quantity of each security important parameter level. Based on the parameter data quantity of each security important parameter level and the corresponding parameter weight factor, the parameter data loss degree of the security important parameter data is analyzed. The data loss degree analysis result includes the parameter data loss degree. By multiplying the parameter data quantity of each security important level by the corresponding parameter weight factor, the initial weighted parameter quantity can be obtained. By multiplying the invalid parameter data quantity of each security important parameter level by the corresponding parameter weight factor, the initial weighted invalid parameter quantity can be obtained. By comprehensively considering the two factors of weight and quantity, the accuracy of the finally obtained parameter data loss degree can be improved.
[0143] After the target weighted parameter quantity and the target weighted invalid parameter quantity are determined, the ratio of the target weighted invalid parameter quantity to the target weighted parameter quantity can be taken as the alarm data loss degree. If the ratio of the target weighted invalid parameter quantity to the target weighted parameter quantity is greater than a second preset ratio, it is determined that the data loss degree analysis result meets the preset data loss degree condition. The second preset ratio is a condition for judging the data loss degree, and the second preset ratio can be adjusted according to actual conditions.
[0144] Finally, if the data loss degree analysis result meets the preset data loss degree condition and the operation state of the unit is a steady state, the emergency state of the nuclear power plant is determined to be an emergency standby state. If the data loss degree analysis result meets the preset data loss degree condition and the operation state of the unit is a transient state, if the operation state of the unit changes from the transient state to the steady state within a preset time period, the emergency state of the nuclear power plant is determined to be a plant emergency state. If the data loss degree analysis result meets the preset data loss degree condition and the operation state of the unit is a transient state, if the operation state of the unit remains in the transient state within a preset time period, the emergency state of the nuclear power plant is determined to be a site emergency state.
[0145] It should be understood that, although each step in the flowchart involved in each embodiment as described above is displayed in sequence according to the direction of the arrow, these steps are not necessarily executed in sequence according to the direction of the arrow. Unless otherwise specified herein, there is no strict order limitation for the execution of these steps, and these steps can be executed in other orders. Moreover, at least part of the steps in the flowchart involved in each embodiment as described above can include multiple steps or stages, which are not necessarily executed at the same time, but can be executed at different times, and the execution order of these steps or stages is not necessarily sequential, but can be executed in rotation or alternation with at least part of other steps or stages in other steps.
[0146] Based on the same inventive concept, the embodiments of the present application also provide a nuclear power plant emergency state evaluation device for implementing the above-mentioned nuclear power plant emergency state evaluation method. The implementation scheme for solving the problem provided by the device is similar to the implementation scheme described in the above method, so the specific limitations in one or more nuclear power plant emergency state evaluation device embodiments provided below can refer to the limitations of the nuclear power plant emergency state evaluation method in the above text, which will not be repeated here.
[0147] In one embodiment, as shown in Figure 6 a nuclear power plant emergency state evaluation device is provided, comprising: a data acquisition module 602, a data analysis module 604 and an emergency state evaluation module 606, wherein:
[0148] The data acquisition module 602 is configured to acquire real-time monitoring data during unit operation, and the real-time monitoring data is data related to the safety function of the nuclear power plant system.
[0149] The data analysis module 604 is configured to analyze a data loss degree of the real-time monitoring data, and obtain a data loss degree analysis result.
[0150] The emergency state evaluation module 606 is configured to determine an emergency state of the nuclear power plant in combination with an operation state of the unit if the data loss degree analysis result satisfies a preset data loss degree condition.
[0151] In one of the embodiments, the data analysis module comprises an alarm data analysis module.
[0152] The alarm data analysis module is configured to extract each safety important alarm data in the alarm data, count each safety important alarm data, and obtain an alarm data quantity of each safety important alarm level; and analyze an alarm data loss degree of the safety important alarm data based on the alarm data quantity of each safety important alarm level and a corresponding alarm weight factor, wherein the data loss degree analysis result comprises the alarm data loss degree, and the real-time monitoring data comprises alarm data.
[0153] In one of the embodiments, the alarm data analysis module is configured to count an invalid alarm data quantity of each safety important alarm level in which the alarm data state is invalid in each safety important alarm data, and multiply the alarm data quantity of each safety important alarm level and the corresponding alarm weight factor to obtain each initial weighted alarm quantity; multiply the invalid alarm data quantity of each safety important alarm level and the corresponding alarm weight factor to obtain each initial weighted invalid alarm quantity; and analyze the alarm data loss degree of the safety important alarm data based on each initial weighted alarm quantity and each initial weighted invalid alarm quantity, wherein the safety important alarm data carries an alarm data state.
[0154] In one of the embodiments, the alarm data analysis module is configured to take a ratio of a target weighted invalid alarm quantity to the target weighted alarm quantity as the alarm data loss degree, wherein the target weighted invalid alarm quantity is a sum of each initial weighted alarm quantity, and the target weighted alarm quantity is a sum of each initial weighted invalid alarm quantity.
[0155] In one of the embodiments, the data analysis module comprises a parameter data analysis module.
[0156] The parameter data analysis module is configured to extract security important parameter data from the parameter data, count the parameter data quantity of each security important parameter level based on each security important parameter level, and analyze the parameter data loss degree of the security important parameter data based on the parameter data quantity of each security important parameter level and the corresponding parameter weight factor. The data loss degree analysis result includes the parameter data loss degree.
[0157] In one of the embodiments, the parameter data analysis module is configured to count the invalid parameter data quantity of each security important parameter level in which the parameter data state is invalid in each security important parameter data, multiply the parameter data quantity of each security important parameter level and the corresponding parameter weight factor to obtain each initial weighted parameter quantity, multiply the invalid parameter data quantity of each security important parameter level and the corresponding parameter weight factor to obtain each initial weighted invalid parameter quantity, and analyze the parameter data loss degree of the security important parameter data based on each initial weighted parameter quantity and each initial weighted invalid parameter quantity. The security important parameter data carries a parameter data state.
[0158] In one of the embodiments, the emergency state evaluation module includes a data loss degree analysis result processing module.
[0159] The data loss degree analysis result processing module is configured to determine that the data loss degree analysis result meets a preset data loss degree condition if the ratio of the target weighted invalid alarm quantity to the target weighted alarm quantity is greater than a first preset ratio.
[0160] In one of the embodiments, the data loss degree analysis result processing module is configured to determine that the data loss degree analysis result meets a preset data loss degree condition if the ratio of the target weighted invalid parameter quantity to the target weighted parameter quantity is greater than a second preset ratio.
[0161] In one of the embodiments, the emergency state evaluation module is configured to determine that the emergency state of the nuclear power plant is an emergency standby state if the data loss degree analysis result meets a preset data loss degree condition and the operation state of the unit is a steady state.
[0162] In one of the embodiments, the emergency state evaluation module is configured to determine that the emergency state of the nuclear power plant is a plant emergency state if the data loss degree analysis result meets a preset data loss degree condition, the operation state of the unit is a transient state, and the operation state of the unit is changed from the transient state to the steady state within a preset time period.
[0163] In one of the embodiments, the emergency state evaluation module is configured to determine the emergency state of the nuclear power plant as a site emergency state if the data loss degree analysis result satisfies a preset data loss degree condition and the operation state of the unit is a transient state, and if the operation state of the unit remains the transient state within a preset time period.
[0164] In one of the embodiments, the emergency state evaluation module comprises a transient state judgment module.
[0165] The transient state judgment module is configured to determine that the operation state of the unit is the transient state if a trip signal is received.
[0166] In one of the embodiments, the transient state judgment module is configured to determine that the operation state of the unit is the transient state if a safety injection system trigger signal is received.
[0167] In one of the embodiments, the transient state judgment module is configured to determine that the operation state of the unit is the transient state if steam turbine load data satisfies a preset steam turbine load data condition.
[0168] In one of the embodiments, the transient state judgment module is configured to determine that the operation state of the unit is the transient state if reactor load data satisfies a preset reactor load condition.
[0169] The above-mentioned modules in the emergency state evaluation device for the nuclear power plant can be realized by software, hardware, or a combination thereof. The above-mentioned modules can be embedded in or independent of the processor in the computer device in hardware form, or can be stored in the memory in the computer device in software form, so as to be called and executed by the processor to perform the operations corresponding to the above-mentioned modules.
[0170] In one embodiment, a computer device, which can be a server, is provided. An internal structure diagram of the computer device can be as shown in Figure 7 The computer device comprises a processor, a memory, and a network interface connected through a system bus. The processor of the computer device is configured to provide computing and control capabilities. The memory of the computer device comprises a non-volatile 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 operating system and the computer program in the non-volatile storage medium to run. The database of the computer device is configured to store real-time monitoring data of a unit operation. The network interface of the computer device is configured to communicate with an external terminal through a network connection. The computer program is executed by the processor to implement an emergency state evaluation method for a nuclear power plant.
[0171] In one embodiment, a computer device is provided, which may be a terminal, and its internal structure diagram may be as follows: Figure 8 As shown, the computer device includes a processor, memory, communication interface, display screen, and input devices connected via a system bus. The processor provides computational and control capabilities. The memory includes non-volatile storage media and internal memory. The non-volatile storage media stores the operating system and computer programs. The internal memory provides an environment for the operation of the operating system and computer programs stored in the non-volatile storage media. The communication interface is used for wired or wireless communication with external terminals; wireless communication can be achieved through Wi-Fi, mobile cellular networks, NFC (Near Field Communication), or other technologies. When executed by the processor, the computer program implements an emergency status assessment method for a nuclear power plant.
[0172] Those skilled in the art will understand that Figure 7 , Figure 8 The structure shown is merely a block diagram of a portion of the structure related to the present application and does not constitute a limitation on the computer device to which the present application is applied. Specific computer devices may include more or fewer components than those shown in the figure, or combine certain components, or have different component arrangements.
[0173] In one embodiment, a computer device is provided, including a memory and a processor, wherein the memory stores a computer program, and the processor executes the computer program to implement the steps of the above-described emergency state assessment method for nuclear power plants.
[0174] In one embodiment, a computer-readable storage medium is provided having a computer program stored thereon, which, when executed by a processor, implements the steps of the above-described emergency status assessment method for nuclear power plants.
[0175] In one embodiment, a computer program product is provided, including a computer program that, when executed by a processor, implements the steps of the above-described emergency status assessment method for nuclear power plants.
[0176] Those skilled in the art can understand that all or part of the processes in the above-mentioned embodiment methods can be completed by instructing the relevant hardware through a computer program. The computer program can be stored in a non-volatile computer readable storage medium, and when the computer program is executed, the processes of the above-mentioned embodiments of the methods can be included. Any reference to memory, database or other medium used in the embodiments provided in the present application can include at least one of non-volatile and volatile memory. Non-volatile memory can include read-only memory (Read-Only Memory, ROM), magnetic tape, floppy disk, flash memory, optical storage, high-density embedded non-volatile memory, resistive memory (ReRAM), magnetoresistive random access memory (Magnetoresistive Random Access Memory, MRAM), ferroelectric memory (Ferroelectric Random Access Memory, FRAM), phase change memory (Phase Change Memory, PCM), graphene memory, etc. Volatile memory can include random access memory (Random Access Memory, RAM) or external cache memory, etc. As an illustration but not limitation, RAM can be in various forms, such as static random access memory (Static Random Access Memory, SRAM) or dynamic random access memory (Dynamic Random Access Memory, DRAM), etc. The database involved in the embodiments provided in the present application can include at least one of a relational database and a non-relational database. The non-relational database can include a distributed database based on a block chain, etc., without being limited thereto. The processor involved in the embodiments provided in the present application can be a general-purpose processor, a central processing unit, a graphics processing unit, a digital signal processor, a programmable logic device, a data processing logic device based on quantum computing, etc., without being limited thereto.
[0177] Any combination of the technical features of the above embodiments can be made. In order to make the description simple, all possible combinations of the technical features in the above embodiments are not described, however, as long as the combination of the technical features does not exist contradictory, it should be considered as the scope of the present application.
[0178] The above embodiments only express several implementation manners of the present application, and the description is more specific and detailed, but it should not be understood as a limitation on the scope of the patent of the present application. It should be noted that for ordinary skilled in the art, without departing from the concept of the present application, a number of modifications and improvements can be made, which are within the scope of protection of the present application. Therefore, the scope of protection of the present application should be subject to the appended claims.
Claims
1. A method for assessing the emergency status of a nuclear power plant, characterized in that, The method includes: Acquire real-time monitoring data during unit operation, wherein the real-time monitoring data is data related to the implementation of safety functions of the nuclear power plant system; the real-time monitoring data includes alarm data and parameter data; Analyze the degree of data loss in the real-time monitoring data to obtain the data loss degree analysis results; The analysis of the degree of data loss in the real-time monitoring data, and the resulting data loss analysis results, include: Extract each important safety alarm data from the alarm data; statistically analyze each important safety alarm data to obtain the number of alarm data at each important safety alarm level; based on the number of alarm data at each important safety alarm level and the corresponding alarm weight factor, analyze the degree of alarm data loss of the important safety alarm data, and the data loss degree analysis result includes the degree of alarm data loss; Extract safety-critical parameter data from the parameter data; statistically analyze each safety-critical parameter data to obtain the number of parameter data at each safety-critical parameter level; based on the number of parameter data at each safety-critical parameter level and the corresponding parameter weight factor, analyze the degree of parameter data loss of the safety-critical parameter data, and the data loss analysis result includes the degree of parameter data loss. If the data loss level analysis results meet the preset data loss level conditions, the emergency status of the nuclear power plant is determined in conjunction with the operating status of the unit. Determining the emergency status of a nuclear power plant based on the operating status of the units includes: If the unit is in a steady operating state, the emergency status of the nuclear power plant is determined to be an emergency standby state. If the operating state of the unit changes from transient to steady state within a preset time period, the emergency state of the nuclear power plant is determined to be the plant emergency state. If the unit's operating state remains in transient state within a preset time period, the emergency state of the nuclear power plant is determined to be the site emergency state.
2. The method according to claim 1, characterized in that, The critical safety alarm data carries the alarm data status; The method further includes: counting the number of invalid alarm data of each of the security-critical alarm levels in which the alarm data status is invalid; The analysis of the degree of alarm data loss of the important safety alarm data based on the number of alarm data for each of the aforementioned safety-critical alarm levels and the corresponding alarm weight factors includes: Multiply the number of alarm data for each of the aforementioned safety importance alarm levels by the corresponding alarm weight factor to obtain the initial weighted alarm count; Multiply the number of invalid alarm data for each of the aforementioned security importance alarm levels by the corresponding alarm weight factor to obtain the initial weighted number of invalid alarms; Based on the number of initial weighted alarms and the number of initial weighted invalid alarms, the degree of alarm data loss for obtaining the security-critical alarm data is analyzed.
3. The method according to claim 2, characterized in that, The analysis of the degree of alarm data loss based on the initial weighted alarm count and the initial weighted invalid alarm count includes: The ratio of the target weighted invalid alarm count to the target weighted alarm count is used as the degree of alarm data loss. The target weighted invalid alarm count is the sum of the initial weighted alarm counts.
4. The method according to claim 1, characterized in that, The safety-critical parameter data carries the parameter data status; The method further includes: counting the number of invalid parameter data at each of the security-important parameter levels in which the parameter data status is invalid; The analysis of the degree of parameter data loss of the safety-important parameter data based on the number of parameter data at each of the aforementioned safety-important parameter levels and the corresponding parameter weighting factors includes: Multiply the number of parameter data for each of the aforementioned safety-important parameter levels by the corresponding parameter weight factor to obtain the number of initial weighted parameters; Multiply the number of invalid parameter data for each of the aforementioned safety-critical parameter levels by the corresponding parameter weight factor to obtain the initial weighted number of invalid parameters; Based on the number of initial weighted parameters and the number of invalid initial weighted parameters, the degree of parameter data loss in obtaining the safety-critical parameter data is analyzed.
5. The method according to claim 4, characterized in that, The analysis of the degree of parameter data loss in obtaining the safety-critical parameter data based on the number of each initial weighted parameter and the number of each initial weighted invalid parameter includes: The ratio of the target number of invalid weighted parameters to the target number of weighted parameters is used as the degree of parameter data loss. The target number of invalid weighted parameters is the sum of the initial number of weighted parameters.
6. The method according to claim 3, characterized in that, If the ratio of the target weighted invalid alarm count to the target weighted alarm count is greater than a first preset ratio, the data loss degree analysis result is determined to meet the preset data loss degree condition.
7. The method according to claim 5, characterized in that, If the ratio of the number of target weighted invalid parameters to the number of target weighted parameters is greater than the second preset ratio, the data loss degree analysis result is determined to meet the preset data loss degree condition.
8. The method according to claim 1, characterized in that, The operating state of the unit is determined to be transient, including at least one of the following: First item: If a shutdown signal is received, the operating state of the unit is determined to be transient. Second item: If a safety injection system trigger signal is received, the operating state of the unit is determined to be transient. Third item: If the turbine load data meets the preset turbine load data conditions, the operating state of the unit is determined to be transient. Fourth item: If the reactor load data meets the preset reactor load conditions, the operating state of the unit is determined to be transient.
9. An emergency status assessment device for a nuclear power plant, characterized in that, The device includes: The data acquisition module is used to acquire real-time monitoring data during unit operation, wherein the real-time monitoring data is data related to the implementation of safety functions of the nuclear power plant system; The data analysis module is used to analyze the degree of data loss of the real-time monitoring data and obtain the data loss degree analysis results; The alarm data analysis module is used to analyze the degree of data loss of the real-time monitoring data and obtain the data loss degree analysis result, including: extracting each safety-important alarm data from the alarm data; statistically analyzing each safety-important alarm data to obtain the number of alarm data at each safety-important alarm level; and analyzing the degree of alarm data loss of the safety-important alarm data based on the number of alarm data at each safety-important alarm level and the corresponding alarm weight factor, wherein the data loss degree analysis result includes the degree of alarm data loss. The parameter data analysis module is also used to extract safety-important parameter data from the parameter data; to statistically analyze each of the safety-important parameter data to obtain the number of parameter data at each safety-important parameter level; and to analyze the degree of parameter data loss of the safety-important parameter data based on the number of parameter data at each safety-important parameter level and the corresponding parameter weight factor, wherein the result of the data loss analysis includes the degree of parameter data loss. The emergency status assessment module is used to determine the emergency status of the nuclear power plant if the data loss degree analysis results meet preset data loss degree conditions, in conjunction with the unit's operating status. Determining the emergency status of the nuclear power plant in conjunction with the unit's operating status includes: if the unit's operating status is in a steady-state operation, determining the nuclear power plant's emergency status as an emergency standby state; if, within a preset time period, the unit's operating status changes from a transient operating state to a steady-state operation, determining the nuclear power plant's emergency status as a plant emergency state; if, within a preset time period, the unit's operating status remains in a transient operating state, determining the nuclear power plant's emergency status as a site emergency state.
10. A computer device comprising a memory and a processor, wherein the memory stores a computer program, characterized in that, When the processor executes the computer program, it implements the steps of the method according to any one of claims 1 to 8.
11. A computer-readable storage medium having a computer program stored thereon, characterized in that, When the computer program is executed by a processor, it implements the steps of the method according to any one of claims 1 to 8.
12. A computer program product, comprising a computer program, characterized in that, When the computer program is executed by a processor, it implements the steps of the method according to any one of claims 1 to 8.
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