A method for responding to nuclear power plant failures

Abstract

The present invention relates to a nuclear power plant fault response method, wherein the method comprises the steps of obtaining operation data related to the power of a nuclear power unit; performing fault diagnosis on the operation data according to a preset diagnostic logic to determine the fault diagnosis result; and in response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to adjust the actual power of the nuclear power unit. The present invention realizes accurate identification and rapid response to transient faults of nuclear power plant units by introducing an intelligent fault diagnosis and power regulation mechanism, thereby effectively reducing the risk of human error and improving the safety and stability of the unit.

Description

Technical Field

[0001] The present invention relates to the field of energy and nuclear energy technology, and in particular to a nuclear power plant fault response method. Background Art

[0002] At present, the transient control of nuclear power plant units requires operators to make judgments based on procedures. Some typical important transients also require operators to intervene manually to ensure the safe and stable operation of the units. In order to make quick and accurate judgments within a limited time and avoid the deterioration of accident consequences, nuclear power plants have compiled unit transient control guidelines and conducted simulator training for operating personnel to enable the operating team to master the content of the unit transient control guidelines and conduct effective control. At the same time, there are other types of transient faults outside the transient control guidelines. At this time, the operating team needs to make judgments based on procedures, skills and knowledge. This requires a high level of skill for the operating team. If the judgment is inaccurate, human errors are very likely to occur. Summary of the invention

[0003] The technical problem to be solved by the present invention is that in the transient control process of the existing nuclear power plant, if the judgment is inaccurate, it is very easy to cause human error, thereby affecting the safe and stable operation of the unit. A nuclear power plant fault response method is provided.

[0004] The technical solution adopted by the present invention to solve the technical problem is: a nuclear power plant fault response method, the method comprising the following steps:

[0005] Obtaining operational data related to nuclear power unit power;

[0006] Performing fault diagnosis on the operating data according to a preset diagnostic logic to determine a fault diagnosis result;

[0007] In response to the fault diagnosis result, the corresponding target power and power regulation rate are obtained to regulate the actual power of the nuclear power unit.

[0008] In one embodiment, the operation data includes: the actual power, the first opening data of the first valve of the deaerator, the second opening data of the first valve of the deaerator, and the first upstream and downstream pipeline data of the pipeline where the first valve of the deaerator is located; wherein the first valve of the deaerator controls the operation state of the deaerator;

[0009] The performing fault diagnosis on the operating data according to the preset diagnostic logic to determine the fault diagnosis result comprises:

[0010] Determining whether the first opening data or the second opening data satisfies a first preset opening range, the first upstream and downstream pipeline data is not abnormal, and the actual power exceeds a first preset power;

[0011] If yes, it is determined that a deaerator valve failure has occurred;

[0012] In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes:

[0013] Obtaining a first target power and a first power adjustment rate corresponding to the deaerator valve failure;

[0014] The actual power is adjusted to the first target power according to the first power adjustment rate.

[0015] In one embodiment, the operation data includes: the actual power, analog data of the condenser emergency drain valve or digital data of the condenser emergency drain valve, and second upstream and downstream pipeline data of the condenser emergency drain valve; wherein the condenser emergency drain valve controls the operation state of the condenser; and the fault diagnosis of the operation data according to the preset diagnostic logic to determine the fault diagnosis result includes:

[0016] Determine whether the analog data or the digital data meets a second preset variation range, whether the second upstream and downstream pipeline data is not abnormal, and whether the actual power exceeds a second preset power;

[0017] If so, it is determined that the condenser emergency drain valve is faulty;

[0018] In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes:

[0019] Obtaining a second target power and a second power adjustment rate corresponding to the condenser emergency drain valve failure;

[0020] The actual power is adjusted to the second target power according to the second power adjustment rate.

[0021] In one embodiment, the operation data includes: the actual power, the third opening data of the first cooling water pump of the conventional island; the fourth opening data of the second cooling water pump of the conventional island; the fifth opening data of the third cooling water pump of the conventional island;

[0022] The performing fault diagnosis on the operating data according to the preset diagnostic logic to determine the fault diagnosis result comprises:

[0023] Determining whether one of the third opening data, the fourth opening data and the fifth opening data satisfies a second preset opening range;

[0024] If yes, it is determined that a cooling water pump failure has occurred;

[0025] In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes:

[0026] Obtaining a third target power and a third power adjustment rate corresponding to the cooling water pump failure;

[0027] The actual power is adjusted to the third target power according to the third power adjustment rate.

[0028] In one embodiment, the operation data includes: the actual power, the first required speed data and the first actual speed data of the first main feed water pump of the steam power system, the second required speed data and the second actual speed data of the second main feed water pump of the steam power system, and the third required speed data and the third actual speed data of the third main feed water pump of the steam power system; wherein, the first main feed water pump, the second main feed water pump and the third main feed water pump jointly control the operation state of the steam power system;

[0029] The performing fault diagnosis on the operating data according to the preset diagnostic logic to determine the fault diagnosis result comprises:

[0030] Determine whether one of the first demand speed data, the second demand speed data and the third demand speed data satisfies preset demand speed data, and whether one of the first actual speed data, the second actual speed data and the third actual speed data satisfies preset actual speed data;

[0031] If so, it is determined that a main feedwater pump failure of the steam power system has occurred;

[0032] In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes:

[0033] Obtaining a fourth target power and a fourth power adjustment rate corresponding to a main feedwater pump failure of a steam power system;

[0034] The actual power is adjusted to the fourth target power according to the fourth power adjustment rate.

[0035] In one embodiment, the operation data includes: the actual power, the oil level signal data of the oil tank of the steam turbine regulating oil system oil station; wherein the oil tank of the steam turbine regulating oil system oil station controls the operation state of the steam turbine regulating oil system oil station;

[0036] The performing fault diagnosis on the operating data according to the preset diagnostic logic to determine the fault diagnosis result comprises:

[0037] Determining whether the oil level signal data satisfies a preset oil level signal;

[0038] If so, it is determined that a fuel tank failure has occurred;

[0039] In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes:

[0040] Obtaining a fifth target power and a fifth power adjustment rate corresponding to the fuel tank fault;

[0041] The actual power is adjusted to the fifth target power according to the fifth power adjustment rate.

[0042] In one embodiment, the operation data includes: the actual power, and the first switch signal data of the regulating valve of the stator cooling water system of the generator; wherein the regulating valve of the stator cooling water system of the generator is used to control the flow rate of the stator cooling water according to the temperature and current of the generator;

[0043] The performing fault diagnosis on the operating data according to the preset diagnostic logic to determine the fault diagnosis result comprises:

[0044] Determining whether the first switch signal data satisfies preset first switch signal data;

[0045] If yes, it is determined that a regulating valve failure of the generator stator cooling water system occurs;

[0046] In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes:

[0047] Obtaining a fifth target power and a fifth power regulation rate corresponding to a fault in a regulating valve of a stator cooling water system of the generator;

[0048] The actual power is adjusted to the fifth target power according to the fifth power adjustment rate.

[0049] In one embodiment, the operation data includes: the actual power, the second switch signal data of the high-pressure heater system valve, and the third upstream and downstream pipeline data where the high-pressure heater system valve is located;

[0050] The performing fault diagnosis on the operating data according to the preset diagnostic logic to determine the fault diagnosis result comprises:

[0051] Determine whether the second switch signal data satisfies the preset second switch signal data, the third upstream and downstream pipeline data is not abnormal, and the actual power exceeds the third preset power;

[0052] If so, it is determined that a high pressure heater system valve failure has occurred;

[0053] In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes:

[0054] Obtaining a seventh target power and a seventh power adjustment rate corresponding to the high-pressure heater system valve failure;

[0055] The actual power is adjusted to the seventh target power according to the seventh power adjustment rate.

[0056] In one embodiment, the operating data includes: the actual power, the closing feedback value of the steam inlet isolation valve of the heater, and the fourth upstream and downstream pipeline data of the pipeline where the steam inlet isolation valve is located; wherein the steam inlet isolation valve of the heater controls the operating state of the heater;

[0057] The performing fault diagnosis on the operating data according to the preset diagnostic logic to determine the fault diagnosis result comprises:

[0058] Determine whether the shutdown feedback value meets the preset shutdown feedback value, the fourth upstream and downstream pipeline data is not abnormal, and the actual power exceeds the fourth preset power;

[0059] If so, it is determined that the steam inlet isolation valve of the heater is faulty;

[0060] In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes:

[0061] Obtaining an eighth target power and an eighth power adjustment rate corresponding to the steam inlet isolation valve failure;

[0062] The actual power is adjusted to the first target power according to the first power adjustment rate.

[0063] In one embodiment, the operating data includes: the actual power, the simulated state signal of the steam valve in the high-pressure cylinder steam turbine protection system, and the fifth upstream and downstream pipeline data of the pipeline where the steam valve is located; wherein the steam valve controls the operating state of the high-pressure cylinder steam turbine protection system;

[0064] The performing fault diagnosis on the operating data according to the preset diagnostic logic to determine the fault diagnosis result comprises:

[0065] Determine whether the simulation state signal satisfies a preset simulation state signal, the fifth upstream and downstream pipeline data is not abnormal, and the actual power exceeds the fifth preset power;

[0066] If so, it is determined that a steam valve failure has occurred;

[0067] In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes:

[0068] Obtaining a ninth target power and a ninth power adjustment rate corresponding to the steam valve failure;

[0069] The actual power is adjusted to the ninth target power according to the ninth power adjustment rate.

[0070] The present invention relates to a nuclear power plant fault response method, wherein the method comprises the steps of obtaining operation data related to the power of a nuclear power unit; performing fault diagnosis on the operation data according to a preset diagnostic logic to determine the fault diagnosis result; and in response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to adjust the actual power of the nuclear power unit. The present invention realizes accurate identification and rapid response to transient faults of nuclear power plant units by introducing an intelligent fault diagnosis and power regulation mechanism, thereby effectively reducing the risk of human error and improving the safety and stability of the unit. BRIEF DESCRIPTION OF THE DRAWINGS

[0071] The present invention will be further described below with reference to the accompanying drawings and embodiments, in which:

[0072] Figure 1 It is a flow chart of the nuclear power plant fault response method of the present invention. DETAILED DESCRIPTION

[0073] In order to make the purpose, features and advantages of the present invention more obvious and easy to understand, the present invention is further described in detail below in conjunction with the accompanying drawings and specific embodiments. Obviously, the described embodiments are part of the embodiments of the present invention, rather than all the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of the present invention.

[0074] In view of the technical problems existing in the background technology: namely, the problems of inaccurate judgment during the transient control process of nuclear power plant units and the easy human error caused by manual power adjustment, the present invention provides a nuclear power plant fault response method, which effectively reduces the risk of human error and improves the safety and stability of the unit.

[0075] like Figure 1 As shown, in order to solve the above problems, the present application provides a nuclear power plant fault response method, the method comprising the following steps:

[0076] S1: Obtaining operation data related to the power of nuclear power units;

[0077] It should be noted that the operating data includes the temperature, pressure, flow information of different system components in the nuclear power plant, the actual output power data of the generator set, and the opening data of the valves of each system, etc. These detailed data are collected and summarized in real time by the monitoring system of the nuclear power plant, laying a solid foundation for subsequent accurate fault diagnosis.

[0078] S2: Perform fault diagnosis on the operating data according to the preset diagnostic logic to determine the fault diagnosis result;

[0079] It should be noted that the preset diagnostic logic is built based on the rich operating experience and profound professional knowledge of nuclear power plants. It can use advanced algorithms for calculations and can also perform in-depth analysis based on historical data. This logic mechanism can keenly capture any abnormal fluctuations in operating data, accurately identify the type, specific location and severity of potential faults, and automatically generate detailed fault diagnosis reports. The entire diagnostic process is highly intelligent, greatly improving the accuracy and processing efficiency of fault diagnosis.

[0080] S3: In response to the fault diagnosis result, the corresponding target power and power regulation rate are obtained to adjust the actual power of the nuclear power unit.

[0081] It should be noted that once the fault diagnosis result is obtained, the target power and the corresponding power adjustment rate are automatically and quickly calculated according to the preset emergency response strategy. These parameters are designed to ensure that the actual power of the nuclear power unit can be quickly and smoothly adjusted to a safe and stable range, thereby effectively curbing the further spread of the fault. Then, the power adjustment command is automatically triggered, and the actual power of the nuclear power unit is accurately controlled through a series of delicate operations, such as adjusting the position of the reactor control rods, adjusting the feed water flow of the steam generator, and adjusting the system power. This series of operations can be done without the manual intervention of the operator, thereby greatly reducing the risk of errors caused by human factors.

[0082] In some embodiments, the nuclear power plant fault response method of the present application can be used to diagnose 16 typical faults of nuclear power plant power changes. Once the system parameters or equipment status change abnormally and meet these preset logical conditions, three automatic response mechanisms will be triggered:

[0083] First, the system can automatically respond to power control and quickly adjust the power of the reactor according to the fault diagnosis results to ensure that it operates within a safe and stable range. This mechanism can achieve intelligent adjustment of the actual power of the nuclear power unit by accurately calculating the target power and power adjustment rate, without the need for manual intervention by the operator, greatly reducing the risk of human error.

[0084] Secondly, it issues an alarm reminder and provides guidance for subsequent response control. This function not only notifies the operation team of the fault situation in a timely manner, but also provides them with detailed response steps and measures, which helps to handle the fault quickly and accurately.

[0085] Finally, a specific description of the fault and response control guidance are given to help the operation team understand the fault more comprehensively. For a long time, although the operation team has worked hard to improve the success rate of intervention under typical fault conditions by formulating procedures, theoretical learning and simulation training, it still faces practical problems such as long identification time and difficulty. The nuclear power plant fault response method of the present invention provides the operation team with a fast and accurate typical fault type identification service through a computer system, and further provides automatic alarm and procedure guidance services. At the same time, for faults that may cause overpower of the unit, respond in advance to ensure that the reactor power meets the technical specifications and achieves power control to the system target value.

[0086] In addition, the system is also scalable and can sort out other typical faults in nuclear power plants, and complete the automatic diagnosis and intelligent response functions of faults according to the operation mode of the system. In addition to realizing the three preset functions of the design, the system can also transmit alarm reminders, fault information and response instructions to the duty station of the nuclear power plant main control room, the duty room, the intermediate control room, the remote command center and the office locations related to the unit operation, to assist relevant personnel to make correct judgments on unit faults and respond in time.

[0087] The present invention determines the typical fault list and typical fault characteristic parameter group that cause the unit to overpower, presets the diagnostic logic, collects data from the unit, and sends it to the system in real time. The system data analysis and diagnosis module runs automatically. When the fault data parameters match the system preset diagnostic logic, it will trigger the above three automatic response mechanisms to achieve rapid and accurate identification, alarm, guidance and intelligent power response of typical faults in nuclear power plants. This process not only reduces the identification time of the operation team, realizes automatic identification and system automatic response control, but also improves the intervention success rate, effectively avoids the unit power exceeding the limit due to faults, and ensures nuclear safety.

[0088] It should be noted that to determine whether this method is applicable to a new fault, the first step is to analyze the comparability of the characteristic parameters of the new fault with the preset logic in the system. If there is similarity, the diagnostic logic can be adjusted and optimized to cover the new fault. Secondly, evaluate the impact of the new fault on the power of the nuclear power plant and the safety risk. If the impact is small and the risk is low, manual monitoring can be adopted; otherwise, the new fault needs to be included in the system diagnosis, and research and development should be strengthened to improve the system capabilities. Finally, the system needs to be expandable and upgradeable to flexibly respond to new fault types that may appear in the future and continuously optimize the fault diagnosis and response mechanism.

[0089] In order to extend the existing fault diagnosis and intelligent response scheme to the regulation of other key parameters of nuclear power plants (such as temperature, pressure, flow, etc.), it is necessary to first clarify the specific regulation targets, sort out the typical faults that may cause abnormalities for these targets, and establish the corresponding fault characteristic parameter groups. Then, based on these fault lists and characteristic parameters, design the corresponding diagnostic logic, and preset response strategies such as automatic adjustment, alarm and post-response control for different faults. At the same time, the data related to the target parameters are collected from the unit in real time and sent to the system for automatic analysis. When the system detects that the fault data parameters related to the target parameters match the preset logic, the corresponding response mechanism will be automatically triggered. In addition, with the accumulation of operating experience and the development of technology, it is necessary to continuously optimize and upgrade the system to adapt to new fault types and regulation requirements. Through these adjustments and expansions, the system will be able to realize intelligent adjustment and fault response for other key parameters of nuclear power plants, thereby further improving the safety and operation efficiency of nuclear power plants.

[0090] Further, the operation data includes: actual power, first opening data of the first valve of the deaerator, second opening data of the first valve of the deaerator, and first upstream and downstream pipeline data of the pipeline where the first valve of the deaerator is located; wherein the first valve of the deaerator controls the operation state of the deaerator;

[0091] Perform fault diagnosis on the operating data according to the preset diagnostic logic and determine the fault diagnosis results including:

[0092] Determine whether the first opening data or the second opening data meets the first preset opening range, the first upstream and downstream pipeline data is not abnormal, and the actual power exceeds the first preset power;

[0093] If yes, it is determined that a deaerator valve failure has occurred;

[0094] In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes:

[0095] Obtaining a first target power and a first power adjustment rate corresponding to a deaerator valve failure;

[0096] The actual power is adjusted to the first target power according to the first power adjustment rate.

[0097] In one embodiment;

[0098] Fault Power reduction rate Target power The deaerator steam inlet valve is accidentally closed 20MW / min 1000MW

[0099] Specifically, the system first collects the status feedback signals (GPV5051MM value and ADG002VVOP value) of the GPV5051 valve / ADG002VV valve in real time, and checks whether one of the two signals changes from 0 to 1 to confirm whether the valve changes from the open state to the closed state. At the same time, the data of the upstream and downstream pipelines and other relevant information of the valve status are monitored. It should be noted that the upstream pipeline is the part that provides steam or fluid to the deaerator, which is located before the valve (GPV5051VV or ADG002VV). Its data includes parameters such as pressure, temperature and flow; while the downstream pipeline is the part where steam or fluid continues to be transmitted after passing through the valve. Its data also includes these key parameters, which is crucial for evaluating the system status after the valve is closed. Verify whether the current actual power is greater than the preset target power of 1000MW. If all conditions are met, the system determines that the deaerator steam inlet valve is accidentally closed according to the preset diagnostic logic and records the event. Subsequently, the new target power is set to 1000MW, and the power adjustment rate is set to 20MW / min, and the actual power of the nuclear power unit is gradually reduced to the target value. During this process, the valve status, upstream and downstream pipeline data and actual power changes are continuously monitored to ensure smooth and safe regulation. Once the target power is reached, the system maintains this level and continues to monitor the status of the deaerator and related systems, while recording the data of the entire fault response process for subsequent analysis and improvement. If other abnormalities or faults are detected, measures are taken according to the preset emergency response procedures.

[0100] In another embodiment:

[0101] Fault Power reduction rate Target power Deaerator water level regulating valve failure fully open Recommended 20MW / min 1000MW

[0102] Specifically, the opening feedback signal of the parallel deaerator water level regulating valve CEX025 / 026VL regulating valve is collected in real time, and its opening data is continuously monitored to detect abnormal conditions. Once it is detected that the opening value of any valve suddenly changes to 100%, that is, the valve is accidentally fully opened, the fault diagnosis process is entered, not only to confirm the valve opening, but also to monitor the upstream and downstream pipeline data and other related information of the valve status, and verify whether the current actual power is greater than the preset target power of 1000MW. If all conditions are met, the system determines that the deaerator water level regulating valve is fully open according to the preset diagnostic logic, and records the fault event. Subsequently, the target power is set to 1000MW, the power regulation rate is set to 20MW / min, and the actual power of the nuclear power unit is gradually reduced until the target is reached. In this process, the valve status, upstream and downstream pipeline data and actual power changes are continuously monitored to ensure smooth and safe regulation. If other abnormalities are detected during regulation or after the target is reached, the system will take measures according to the preset emergency response procedure and record the entire fault response process data for subsequent analysis and improvement.

[0103] In another embodiment:

[0104]

[0105] Specifically, when the opening feedback signal of the parallel deaerator water level control valve CEX025VL control valve / CEX026VL control valve is collected, if it is detected that the opening value of any valve suddenly becomes 0, it means that one of the valves may have been accidentally closed. At this time, a comprehensive fault diagnosis process will be immediately started, not only checking the opening data of the two valves, but also synchronously monitoring the data of the upstream and downstream pipelines and other relevant information of the valve status to ensure the accuracy of the diagnosis and not be interfered by other potential abnormalities. When it is confirmed that the valve is indeed closed, and there are no other abnormalities in the upstream and downstream pipelines and valve status, and the current actual power is greater than the preset target power of 1000MW, according to the preset diagnostic logic, it is determined that the deaerator water level control valve is closed due to a fault. Once the fault is confirmed, the event is immediately recorded, and the new target power is set to 1000MW. At the same time, the power regulation rate is set to 20MW / min in GRE0111ND (load rate setting module), and then the actual power of the nuclear power unit is gradually reduced at this rate until the target power is reached. During the power regulation process, the valve status, upstream and downstream pipeline data, and actual power changes are continuously monitored to ensure smooth and safe regulation. If the valve status of the unclosed valve in CEX025 / 026VL is normal, it is preferred to fully open it to maintain the water supply flow of the deaerator, and automatically adjust to stabilize the liquid level of ADG (deaerator system). Once the actual power reaches the target power, maintain the power level and continue to monitor the status of the deaerator and its related systems. If other abnormalities or failures are detected during this process or after the target power is reached, the system will take prompt measures according to the preset emergency response procedures. In addition, the data of the entire fault response process is recorded in detail for subsequent analysis and improvement. Through the above process, the system can quickly and effectively respond to the fault closure of the deaerator water level regulating valve, ensure the safe and stable operation of the nuclear power unit, and minimize the impact on the deaerator and its related systems.

[0106] Further, the operation data includes: actual power, analog data of the condenser emergency steam trap or digital data of the condenser emergency steam trap, and second upstream and downstream pipeline data of the condenser emergency steam trap; wherein the emergency steam trap controls the operation status of the condenser;

[0107] Perform fault diagnosis on the operating data according to the preset diagnostic logic and determine the fault diagnosis results including:

[0108] Determine whether the analog data or the digital data meets the second preset variation range, whether the second upstream and downstream pipeline data is not abnormal, and whether the actual power exceeds the second preset power;

[0109] If so, it is determined that the condenser emergency drain valve is faulty;

[0110] In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes:

[0111] Obtaining a second target power and a second power adjustment rate corresponding to a condenser emergency drain valve failure;

[0112] The actual power is adjusted to the second target power according to the second power adjustment rate.

[0113] In one embodiment:

[0114]

[0115] Specifically: When the system collects the valve position analog values ​​of emergency drain regulating valves including ABP412 / 512VLP, AHP120 / 220 / 118 / 218VLP, and ABP413 / 513VLOP / CP, ABP415 / 425 / 445 / 465 / 515 / 525 / 545 / 565VVOP / CP,

[0116] When the digital values ​​of emergency steam traps and steam isolation valves such as AHP117 / 217 / 316 / 317 / 112 / 122 / 222 / 322VVOP / CP are detected, these data are analyzed in real time. If the analog value is detected to be abnormally increased to ≥5%, or the OP (open position) in the digital value changes from 0 to 1 and CP changes from 1 to 0, these changes may indicate that the emergency steam trap is accidentally opened. At this time, immediately check the upstream and downstream pipeline data and other valve status information to ensure that there is no other abnormal interference, and verify whether the current thermal power exceeds the preset second preset power of 2875MW. If all conditions are met, the system determines that the condenser emergency steam trap is faulty according to the preset diagnostic logic. After the fault is confirmed, the event is recorded immediately, the reduced target power is set (such as the current power GRE0003MY minus 10MW), and the power adjustment rate is set to 20MW / min. The actual power of the nuclear power unit is gradually reduced to the new target at this rate. During the adjustment process, the system continuously monitors the emergency steam trap status, upstream and downstream pipeline data and actual power changes to ensure smooth and safe adjustment, and monitors other related valves and systems to prevent further abnormalities. This process enables the system to respond quickly to condenser emergency steam trap failures, ensure the safe and stable operation of nuclear power units, and record fault response data for subsequent analysis and improvement, continuously optimizing fault handling and emergency response capabilities.

[0117] In another embodiment:

[0118] Fault Power reduction rate Target power Only one condensate (CEX) pump is left in operation 50MW / min 540MW

[0119] Specifically: When the system monitors the operating status of the condensate system (CEX), it pays attention to the operation of the three parallel condensate pumps CEX001PO, CEX002PO and CEX003PO. These three pumps have exactly the same functions, each can provide 50% of the load capacity, and are designed to be connected in parallel to achieve system redundancy and reliability. The status values ​​of CEX001POTP, CEX002POTP and CEX003POTP of these three pumps are continuously collected to reflect the operating status of the pumps. If the system detects that two of the values ​​change from 0 to 1 (assuming 0 is stopped and 1 is running), it may mean that only one condensate pump is left in operation. At this time, immediately check the upstream and downstream pipeline data and the status of other valves and equipment in the condensate system to ensure that there is no interference from other abnormal information, and verify whether the current nuclear power unit power is greater than the preset second preset power of 540MW. If all conditions are met, it is determined that the redundant pump of the condensate system has failed or shut down, and the event is recorded immediately. Subsequently, the target power after the reduction is automatically set to 540MW, and the power adjustment rate is set to 50MW / min, gradually reducing the actual power of the nuclear power unit until the new target is reached. During the adjustment process, the condensate pump status, upstream and downstream pipeline data, and actual power changes are continuously monitored to ensure smooth and safe adjustment, and other related valves and system status are continuously monitored to prevent further abnormalities. This process enables the system to respond quickly to the failure of the redundant pump of the condensate system, ensure that the nuclear power unit operates at a safe and stable power, and record the fault response data for subsequent analysis and improvement.

[0120] In another embodiment:

[0121] Fault Power reduction rate Target power A circulating water (CRF) pump tripped 50MW / min 600MW

[0122] Specifically: When the system monitors the operating status of the circulating water system (CRF), the operating status of the two circulating water pumps CRF001PO and CRF002PO. These two pumps belong to columns A and B respectively, and have the same function. They are mainly responsible for providing pressure head for seawater to cool the exhaust steam in the condenser. The CRF001POTP and CRF002POTP status values ​​of these two pumps are continuously collected to reflect the operating status of the pumps in real time. If the system detects that one of these two values ​​changes from 0 to 1 (assuming that 0 represents normal operation of the pump and 1 represents pump tripping or stopping operation, the specific meaning is based on the system definition), the fault inspection process is immediately triggered. At this time, the upstream and downstream pipeline data and the status of other valves and equipment in the condenser system are comprehensively checked to ensure that there is no other abnormal information interfering with the judgment, and to verify whether the current nuclear power unit power is greater than the preset second preset power of 600MW. If all conditions are met, that is, the state change of a circulating water pump is within the preset range, the upstream and downstream pipeline data is normal, and the actual power exceeds the preset power, then according to the preset diagnostic logic, it is determined that the CRF redundant pump is faulty or tripped, resulting in only one pump remaining in operation. Once the fault is confirmed, the event is recorded immediately and the target power is set to 600MW (to maintain cooling capacity and safe and stable operation under single pump operation), while the power regulation rate is 50MW / min to prepare for rapid power adjustment. Although the target power has not been reduced, the current power stability is continuously monitored, and the operating status of the remaining circulating water pumps and the status of other related valves and systems are closely monitored to prevent further abnormalities or the need for additional emergency response measures. Through this process, the system can respond quickly to CRF redundant pump failures, ensure that the nuclear power unit can still operate safely and stably when only one pump is left, and record fault response data for subsequent analysis and improvement.

[0123] Furthermore, the operation data includes: actual power, third opening data of the first cooling water pump of the conventional island; fourth opening data of the second cooling water pump of the conventional island; fifth opening data of the third cooling water pump of the conventional island;

[0124] Perform fault diagnosis on the operating data according to the preset diagnostic logic and determine the fault diagnosis results including:

[0125] Determining whether one of the third opening data, the fourth opening data and the fifth opening data satisfies a second preset opening range;

[0126] If yes, it is determined that a cooling water pump failure has occurred;

[0127] In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes:

[0128] Obtaining a third target power and a third power adjustment rate corresponding to a cooling water pump failure;

[0129] The actual power is adjusted to the third target power according to the third power adjustment rate.

[0130] In one embodiment:

[0131]

[0132]

[0133] Specifically, in the operation monitoring system of the nuclear power plant, it is crucial to continuously monitor the operating status of the conventional island cooling water pumps (including SRI 101PO, SRI201PO, SRI301PO). The system performs fault diagnosis by collecting the actual power and the opening data of each pump (SRI 101POTP, SRI201POTP, SRI 301POTP). When the system detects that the opening data of any pump exceeds the preset abnormal or fault range, it will immediately start the further diagnosis process. The process will check three key conditions: the opening data of at least two pumps indicate that they may have stopped running or tripped, the upstream and downstream pipelines and valves are in normal condition, and the actual power of the nuclear power unit exceeds 540MW. If these three conditions are met at the same time, the system will determine that a cooling water pump failure has occurred, that is, at least one pump has failed or tripped, resulting in only one pump remaining in operation. Once the fault is confirmed, take immediate action to set the target power to 540MW and the power regulation rate to 50MW / min, and gradually reduce it to 540MW at a rate of 50MW / min. This setup ensures the redundancy of the three conventional island cooling water pumps, improving the reliability and safety of the system. Even if any one or two pumps fail, the remaining pumps can automatically adjust the load to ensure that the nuclear power units can continue to operate safely and stably.

[0134] Further, the operation data includes: actual power, first required speed data and first actual speed data of the first main feed water pump of the steam power system, second required speed data and second actual speed data of the second main feed water pump of the steam power system, third required speed data and third actual speed data of the third main feed water pump of the steam power system; wherein the first main feed water pump, the second main feed water pump and the third main feed water pump jointly control the operation state of the steam power system;

[0135] Perform fault diagnosis on the operating data according to the preset diagnostic logic and determine the fault diagnosis results including:

[0136] Determine whether one of the first demand speed data, the second demand speed data and the third demand speed data satisfies the preset demand speed data, and whether one of the first actual speed data, the second actual speed data and the third actual speed data satisfies the preset actual speed data;

[0137] If so, it is determined that a main feedwater pump failure of the steam power system has occurred;

[0138] In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes:

[0139] Obtaining a fourth target power and a fourth power adjustment rate corresponding to a main feedwater pump failure of a steam power system;

[0140] The actual power is adjusted to a fourth target power according to a fourth power adjustment rate.

[0141] In one embodiment:

[0142] Fault Power reduction rate Target power The main feed water (APA) pump speed drops abnormally 50MW / min 50MW reduction

[0143] Specifically, in the operation monitoring system of the nuclear power plant, the operation status of the steam power system is continuously monitored to ensure its stable operation. The operation data not only includes the actual power, but also records in detail the required speed data and actual speed data of the three main feed water pumps (APA001PO, APA002PO, APA003PO) of the steam power system. These speed data, namely the first required speed data and the first actual speed data of the first main feed water pump, the second required speed data and the second actual speed data of the second main feed water pump, and the third required speed data and the third actual speed data of the third main feed water pump, together constitute the key information for fault diagnosis of the steam power system. The preset diagnostic logic will check these speed data in real time. Once any required speed data or actual speed data is found to meet the preset abnormal conditions, the system will immediately determine that the main feed water pump of the steam power system has a fault. Subsequently, the system will automatically obtain the target power (the fourth target power) and the power regulation rate (the fourth power regulation rate) corresponding to the fault, and start the regulation mechanism to gradually reduce the actual power of the nuclear power unit to the target power (such as the power after reducing 50MW) at the preset power regulation rate (such as 50MW / min). In the specific implementation, if the system detects that the actual speed of the main feedwater pump (APA) suddenly decreases, while the required speed continues to increase, and the current power is greater than 1030MW, it will set a reduced power target and set the power adjustment rate in the load rate setting module. Then the system will automatically run and reduce the actual power at the set rate until the target power is reached. The three main feedwater pumps APA001 / 002 / 003PO have the same function and provide pressure head for the secondary circuit. Under normal circumstances, the actual speed will follow the required speed. If the two are inconsistent, it indicates that the system may be abnormal.

[0144] Furthermore, the operation data includes: actual power, oil level signal data of the oil tank of the steam turbine regulating oil system oil station; wherein the oil tank of the steam turbine regulating oil system oil station controls the operation state of the steam turbine regulating oil system oil station;

[0145] Perform fault diagnosis on the operating data according to the preset diagnostic logic and determine the fault diagnosis results including:

[0146] Determine whether the oil level signal data meets the preset oil level signal;

[0147] If so, it is determined that a fuel tank failure has occurred;

[0148] In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes:

[0149] Obtaining a fifth target power and a fifth power adjustment rate corresponding to a fuel tank failure;

[0150] The actual power is adjusted to a fifth target power according to a fifth power adjustment rate.

[0151] In one embodiment:

[0152]

[0153] Specifically, in the operation monitoring system of a nuclear power plant, real-time monitoring of the steam power system and its auxiliary systems is a key link to ensure the safe and stable operation of the nuclear power plant. In addition to continuously monitoring the speed data of the main feedwater pump, the system also adds monitoring of the oil level signal data of the oil tank of the oil station of the steam turbine regulating oil system, which is crucial for the accurate control of the oil station operation status. The preset diagnostic logic is further expanded to check whether the oil tank oil level signal data meets the preset abnormal conditions, that is, when the oil level signal of a certain oil station changes from a normal state (0) to an abnormal state (1), and the current nuclear power unit power is greater than the preset threshold (1031MW), the system will determine that it is an oil tank fault. Once the fault is confirmed, it responds immediately, automatically obtains the fifth target power (1031MW) and the fifth power regulation rate (25MW / min) corresponding to the oil tank fault, and automatically adjusts the actual power of the nuclear power unit to gradually reduce it to the target power at the set power regulation rate. In specific implementation, if the system detects an abnormal drop in the oil tank level of the steam turbine regulating oil system oil station, and preliminarily determines that the leak may be located on the valve of the steam turbine protection system (GSE) or steam turbine regulating system (GRE), it will collect relevant oil level signal data and perform predetermined actions according to the current power situation: if the conditions are met, an alarm message will pop up to prompt the operator to confirm the location of the leak. Once the operator confirms that the leak is located at the GSE / GRE valve, the system will automatically set the power target and regulation rate, and automatically operate to reduce the actual power to the target value; if the leak is not at the GSE / GRE valve, the automatic power reduction operation will not be performed. This comprehensive monitoring and response mechanism ensures that the steam power system and its auxiliary systems of the nuclear power plant can take countermeasures quickly and accurately in the event of a failure, ensuring the safe and stable operation of the nuclear power plant.

[0154] In another embodiment:

[0155]

[0156] Specifically, in the safe operation of nuclear power plants, the regulating valves of the generator hydrogen cooling system (GRH1101 / 2101VD) are crucial. They regulate the cooling water flow of the A / B column coolers respectively to maintain the normal temperature of the generator hydrogen. When any one of the two regulating valves (or at the same time) is automatically closed, that is, one of the GRH1101 / 2101MM valve switch signals becomes 0, indicating that the corresponding regulating valve has been completely closed, which may lead to a decrease in cooling capacity and an increase in hydrogen temperature. At this time, the operation monitoring of the nuclear power plant immediately intervenes, first checking the upstream and downstream pipelines and valve status to confirm whether there are other abnormalities. If it is confirmed that there are no other abnormalities, it is determined that there is a potential fault in the generator hydrogen cooling system, and then the power regulation rate of 50MW / min is set to gradually reduce the power of the nuclear power unit, and an alarm signal is issued to remind the operator to pay attention to abnormal conditions and manually adjust the power until the hydrogen temperature returns to normal and stable, thereby ensuring the safe and stable operation of the nuclear power plant.

[0157] Furthermore, the operation data includes: actual power, and first switch signal data of a regulating valve of a generator stator cooling water system; wherein the regulating valve of the generator stator cooling water system is used to control the flow of stator cooling water according to the temperature and current of the generator;

[0158] Perform fault diagnosis on the operating data according to the preset diagnostic logic and determine the fault diagnosis results including:

[0159] Determining whether the first switch signal data satisfies the preset first switch signal data;

[0160] If yes, it is determined that a regulating valve failure of the generator stator cooling water system occurs;

[0161] In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes:

[0162] Obtaining a fifth target power and a fifth power regulation rate corresponding to a fault in a regulating valve of a stator cooling water system of a generator;

[0163] The actual power is adjusted to a fifth target power according to a fifth power adjustment rate.

[0164] In one embodiment:

[0165]

[0166] Specifically, the safe operation of the nuclear power plant is highly dependent on the normal operation of the regulating valve (GST0101VD) of the generator stator cooling water system, which dynamically adjusts the flow of stator cooling water according to the real-time temperature and current of the generator to ensure effective cooling of the generator stator. When the operation monitoring system detects that the first switch signal data (GST0101MM) of the regulating valve of the generator stator cooling water system becomes 0, indicating that the regulating valve may be closed or faulty, the fault diagnosis process is immediately started, and the signal data is deeply analyzed to confirm whether the preset abnormal conditions are met. Once the fault is confirmed, it responds quickly, automatically sets the power regulation rate of 50MW / min in the GRE0111ND load rate setting module, and gradually reduces the power of the nuclear power unit to slow down the rise of the generator temperature and the wire rod temperature. At the same time, an alarm signal is issued to remind the operator to pay attention and manually adjust the power until the outlet water temperature of the generator stator cooling water system (GST) is lower than 76℃ and the wire rod temperature of the generator hydrogen cooling system (GRH) is lower than 87℃, thereby ensuring the safe operation of the generator.

[0167] Further, the operation data includes: actual power, second switch signal data of the high-pressure heater system valve, and third upstream and downstream pipeline data where the high-pressure heater system valve is located;

[0168] Perform fault diagnosis on the operating data according to the preset diagnostic logic and determine the fault diagnosis results including:

[0169] Determine whether the second switch signal data satisfies the preset second switch signal data, the third upstream and downstream pipeline data is not abnormal, and the actual power exceeds the third preset power;

[0170] If so, it is determined that a high pressure heater system valve failure has occurred;

[0171] In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes:

[0172] Obtaining a seventh target power and a seventh power adjustment rate corresponding to a high-pressure heater system valve failure;

[0173] The actual power is adjusted to the seventh target power according to the seventh power adjustment rate.

[0174] In one embodiment:

[0175] Fault Power reduction rate Target power A high-voltage heater is out of service 50MW / min 1046MW

[0176] Specifically, the safety and stable operation of the nuclear power plant is highly dependent on the normal operation of the high-pressure heater system valves. These valves serve as the inlet and outlet isolation valves of the high-pressure heaters in columns A and B, and ensure that the water side of the high-pressure heaters in the corresponding columns is put into operation when fully open. In order to ensure the reliability of this key system, the operation monitoring system of the nuclear power plant is designed to be able to collect and monitor key operation data including the actual power of the nuclear power unit, the switch signal of the high-pressure heater system valves and the status of the upstream and downstream pipelines in real time and comprehensively. Once the monitoring system detects that the closing limit signal (AHP101 / 102VLCP or AHP201 / 202VLCP) of the inlet and outlet isolation valves of the high-pressure heaters in columns A or B changes from 0 to 1 at the same time, it indicates that the valve may be closed, and immediately starts an in-depth fault diagnosis process to analyze the switch signal, the status of the upstream and downstream pipelines and the actual power data to determine whether the preset fault conditions are met - that is, the valve is in the closed limit state, there is no abnormality in the upstream and downstream pipelines, and the actual power exceeds the preset threshold of 1046MW. If these conditions are met, it is quickly determined that there is a valve failure in the high-pressure heater system and countermeasures are automatically taken, including setting a power target of 1046MW and a power regulation rate of 50MW / min to gradually adjust the actual power to the target value to ensure the stable operation of the nuclear power plant.

[0177] In another embodiment:

[0178] Fault Power reduction rate Target power Two-row low-pressure heater exit Recommended 20MW / min Reduced to factory power

[0179] Specifically, the safe and stable operation of a nuclear power plant is inseparable from the precise control of the low-pressure heater system valves and their bypass valves. To ensure the reliability of this key system, the nuclear power plant is equipped with an advanced operation monitoring system that can collect and monitor the actual power of the nuclear power unit, the switch signals of the low-pressure heater system valves, and the status data of the upstream and downstream pipelines in real time. When the monitoring system detects that the closing limit signal of the inlet and outlet isolation valves of the A-column or B-column low-pressure heaters changes, and the bypass valve limit signal also changes, and the upstream and downstream pipeline status and valve status do not show abnormalities, and the current actual power exceeds the preset threshold, the fault diagnosis process is immediately started. Once it is determined that the low-pressure heater system valve is faulty, a power target of 250MW is set, and a power adjustment rate of 20MW / min is set. The system then automatically adjusts the actual power to the target value, and gives the operator enough time to perform other necessary operations to ensure the stable and safe operation of the nuclear power plant. The rapid response and accurate judgment of this mechanism rely on the comprehensive collection, real-time monitoring, in-depth analysis of operation data, and the accuracy of the preset diagnostic logic, providing strong support for the safety and stability of nuclear power plants.

[0180] Further, the operation data includes: actual power, the closing feedback value of the steam inlet isolation valve of the heater, and the fourth upstream and downstream pipeline data of the pipeline where the steam inlet isolation valve is located; wherein the steam inlet isolation valve of the heater controls the operation state of the heater;

[0181] Perform fault diagnosis on the operating data according to the preset diagnostic logic and determine the fault diagnosis results including:

[0182] Determine whether the off-feedback value meets the preset off-feedback value, the fourth upstream and downstream pipeline data are not abnormal, and the actual power exceeds the fourth preset power;

[0183] If so, it is determined that the steam inlet isolation valve of the heater is faulty;

[0184] In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes:

[0185] Obtaining an eighth target power and an eighth power regulation rate corresponding to a steam inlet isolation valve failure;

[0186] The actual power is adjusted to the first target power according to the first power adjustment rate.

[0187] In one embodiment:

[0188]

[0189] Specifically, in the safe operation of nuclear power plants, the status monitoring and fault handling of the steam inlet isolation valve (GSS1302VV, GSS2301VV) of the secondary heater of the reheat steam system (GSS) plays a vital role. To ensure the stable operation of the nuclear power plant, the operation monitoring system collects and monitors the actual power of the nuclear power unit, the closing feedback value of the steam inlet isolation valve, and the upstream and downstream status data of the pipeline where the valve is located in real time. When the monitoring system detects that the closing feedback value of the steam inlet isolation valve of the secondary heater of the reheat steam system of column A and column B changes from 0 to 1 at the same time, that is, both valves are closed, resulting in the loss of reheating function, and there is no abnormal information in the upstream and downstream pipeline status and valve status, and the current actual power is greater than the preset power threshold of 1056MW, the fault diagnosis process is immediately started and it is determined to be a steam inlet isolation valve failure. Subsequently, a power target of 1056MW is set, and a power adjustment rate of 1.5MW / min is set. The actual power is gradually adjusted to the target power at the set rate to ensure the stable and safe operation of the nuclear power plant.

[0190] In another embodiment;

[0191]

[0192] Specifically, in the safe operation of nuclear power plants, the status monitoring and fault handling of the steam inlet isolation valve (GSS1201VV, GSS2201VV) of the first-stage heater of the reheat steam system (GSS) plays a vital role. To ensure the stable operation of the nuclear power plant, the operation monitoring system collects and monitors the actual power of the nuclear power unit, the open limit value of the steam inlet isolation valve, and the upstream and downstream status data of the pipeline where the valve is located in real time. When the monitoring system detects that one of the open limit values ​​of the steam inlet isolation valve of the first-stage heater of the reheat steam system of column A or column B changes from 1 to 0, that is, at least one valve is closed and the reheat function may be lost, and there is no abnormal information in the upstream and downstream pipeline status and valve status, and the current actual power is greater than the preset power threshold of 1074MW, the fault diagnosis process is immediately started and it is determined to be a steam inlet isolation valve failure. Subsequently, a power target of 1074MW is set, and a power adjustment rate of 1.5MW / min is set. The actual power is gradually adjusted to the target power at the set rate to ensure the stable and safe operation of the nuclear power plant.

[0193] Furthermore, the operation data includes: actual power, simulated state signal of the steam valve in the high-pressure cylinder steam turbine protection system, and fifth upstream and downstream pipeline data of the pipeline where the steam valve is located; wherein the steam valve controls the operation state of the high-pressure cylinder steam turbine protection system;

[0194] Perform fault diagnosis on the operating data according to the preset diagnostic logic and determine the fault diagnosis results including:

[0195] Determine whether the simulation state signal satisfies the preset simulation state signal, the fifth upstream and downstream pipeline data are not abnormal, and the actual power exceeds the fifth preset power;

[0196] If so, it is determined that a steam valve failure has occurred;

[0197] In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes:

[0198] Obtaining a ninth target power and a ninth power regulation rate corresponding to a steam valve failure;

[0199] The actual power is adjusted to a ninth target power according to a ninth power adjustment rate.

[0200] In one embodiment:

[0201]

[0202]

[0203] Specifically, in the safe operation of nuclear power plants, the status monitoring and fault handling of steam valves (GSE0151 / 0251 / 0351 / 0451VV) in the high-pressure cylinder turbine protection system are crucial. In order to ensure the stable operation of nuclear power plants, the operation monitoring system collects and monitors the actual power of nuclear power units, the switch limit signal and simulated opening signal of the steam valve, and the upstream and downstream status data of the pipeline where the valve is located in real time. When the monitoring system detects that any steam valve changes from an open state to a closed state, and its closing limit signal changes at the same time, the simulated opening signal also changes accordingly, and the upstream and downstream pipelines and valves are in normal state, and the actual power exceeds the preset 1031MW threshold, the fault diagnosis process is immediately started and it is determined to be a steam valve failure. Subsequently, the power target of 1031MW is automatically set, and the power adjustment rate of 2MW / min is set. The actual power is gradually adjusted to the target power at the set rate to ensure the stability and safety of the nuclear power plant.

[0204] The present invention relates to a nuclear power plant fault response method, wherein the method comprises the steps of obtaining operation data related to the power of a nuclear power unit; performing fault diagnosis on the operation data according to a preset diagnostic logic to determine the fault diagnosis result; and in response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to adjust the actual power of the nuclear power unit. The present invention realizes accurate identification and rapid response to transient faults of nuclear power plant units by introducing an intelligent fault diagnosis and power regulation mechanism, thereby effectively reducing the risk of human error and improving the safety and stability of the unit.

[0205] It can be understood that the above embodiments only express the preferred implementation modes of the present invention, and the descriptions thereof are relatively specific and detailed, but they cannot be understood as limiting the patent scope of the present invention. It should be pointed out that, for ordinary technicians in this field, the above technical features can be freely combined without departing from the concept of the present invention, and several deformations and improvements can be made, which all belong to the protection scope of the present invention. Therefore, all equivalent changes and modifications made to the scope of the claims of the present invention should belong to the coverage of the claims of the present invention.

Claims

1. A method for responding to a nuclear power plant failure, characterized in that: The method comprises the following steps: Obtaining operational data related to nuclear power unit power; Performing fault diagnosis on the operating data according to a preset diagnostic logic to determine a fault diagnosis result; In response to the fault diagnosis result, the corresponding target power and power regulation rate are obtained to regulate the actual power of the nuclear power unit.

2. The nuclear power plant fault response method according to claim 1, characterized in that: The operation data includes: the actual power, the first opening data of the first valve of the deaerator, the second opening data of the first valve of the deaerator, and the first upstream and downstream pipeline data of the pipeline where the first valve of the deaerator is located; wherein the first valve of the deaerator controls the operation state of the deaerator; The performing fault diagnosis on the operating data according to the preset diagnostic logic and determining the fault diagnosis result comprises: Determining whether the first opening data or the second opening data satisfies a first preset opening range, the first upstream and downstream pipeline data is not abnormal, and the actual power exceeds a first preset power; If yes, it is determined that a deaerator valve failure has occurred; In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes: Obtaining a first target power and a first power adjustment rate corresponding to the deaerator valve failure; The actual power is adjusted to the first target power according to the first power adjustment rate.

3. The nuclear power plant fault response method according to claim 1, characterized in that: The operation data includes: the actual power, analog data of the condenser emergency drain valve or digital data of the condenser emergency drain valve, and second upstream and downstream pipeline data of the condenser emergency drain valve; wherein the condenser emergency drain valve controls the operation state of the condenser; and the fault diagnosis of the operation data according to the preset diagnostic logic to determine the fault diagnosis result includes: Determine whether the analog data or the digital data meets a second preset variation range, whether the second upstream and downstream pipeline data is not abnormal, and whether the actual power exceeds a second preset power; If so, it is determined that the condenser emergency drain valve is faulty; In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes: Obtaining a second target power and a second power adjustment rate corresponding to the condenser emergency drain valve failure; The actual power is adjusted to the second target power according to the second power adjustment rate.

4. The nuclear power plant fault response method according to claim 1, characterized in that: The operation data includes: the actual power, the third opening data of the first cooling water pump of the conventional island; the fourth opening data of the second cooling water pump of the conventional island; the fifth opening data of the third cooling water pump of the conventional island; The performing fault diagnosis on the operating data according to the preset diagnostic logic and determining the fault diagnosis result comprises: Determining whether one of the third opening data, the fourth opening data and the fifth opening data satisfies a second preset opening range; If yes, it is determined that a cooling water pump failure has occurred; In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes: Obtaining a third target power and a third power adjustment rate corresponding to the cooling water pump failure; The actual power is adjusted to the third target power according to the third power adjustment rate.

5. The nuclear power plant fault response method according to claim 1, characterized in that: The operation data includes: the actual power, the first required speed data and the first actual speed data of the first main feed water pump of the steam power system, the second required speed data and the second actual speed data of the second main feed water pump of the steam power system, and the third required speed data and the third actual speed data of the third main feed water pump of the steam power system; wherein the first main feed water pump of the steam power system, the second main feed water pump of the steam power system and the third main feed water pump of the steam power system jointly control the operation state of the steam power system; The performing fault diagnosis on the operating data according to the preset diagnostic logic and determining the fault diagnosis result comprises: Determine whether one of the first demand speed data, the second demand speed data and the third demand speed data satisfies preset demand speed data, and whether one of the first actual speed data, the second actual speed data and the third actual speed data satisfies preset actual speed data; If so, it is determined that a main feedwater pump failure of the steam power system has occurred; In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes: Obtaining a fourth target power and a fourth power adjustment rate corresponding to a main feedwater pump failure of a steam power system; The actual power is adjusted to the fourth target power according to the fourth power adjustment rate.

6. The nuclear power plant fault response method according to claim 1, characterized in that: The operation data includes: the actual power and the oil level signal data of the oil tank of the steam turbine regulating oil system oil station; wherein the oil tank of the steam turbine regulating oil system oil station controls the operation state of the steam turbine regulating oil system oil station; The performing fault diagnosis on the operating data according to the preset diagnostic logic and determining the fault diagnosis result comprises: Determining whether the oil level signal data satisfies a preset oil level signal; If so, it is determined that a fuel tank failure has occurred; In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes: Obtaining a fifth target power and a fifth power adjustment rate corresponding to the fuel tank fault; The actual power is adjusted to the fifth target power according to the fifth power adjustment rate.

7. The nuclear power plant fault response method according to claim 1, characterized in that: The operation data includes: the actual power and the first switch signal data of the regulating valve of the stator cooling water system of the generator; wherein the regulating valve of the stator cooling water system of the generator is used to control the flow rate of the stator cooling water according to the temperature and current of the generator; The performing fault diagnosis on the operating data according to the preset diagnostic logic and determining the fault diagnosis result comprises: Determining whether the first switch signal data satisfies preset first switch signal data; If yes, it is determined that a regulating valve failure of the generator stator cooling water system occurs; In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes: Obtaining a fifth target power and a fifth power regulation rate corresponding to a fault in a regulating valve of a stator cooling water system of the generator; The actual power is adjusted to the fifth target power according to the fifth power adjustment rate.

8. The nuclear power plant fault response method according to claim 1, characterized in that: The operation data includes: the actual power, the second switch signal data of the high-pressure heater system valve, and the third upstream and downstream pipeline data where the high-pressure heater system valve is located; The performing fault diagnosis on the operating data according to the preset diagnostic logic and determining the fault diagnosis result comprises: Determine whether the second switch signal data satisfies the preset second switch signal data, the third upstream and downstream pipeline data is not abnormal, and the actual power exceeds the third preset power; If so, it is determined that a high pressure heater system valve failure has occurred; In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes: Obtaining a seventh target power and a seventh power adjustment rate corresponding to the high-pressure heater system valve failure; The actual power is adjusted to the seventh target power according to the seventh power adjustment rate.

9. The nuclear power plant fault response method according to claim 1, characterized in that: The operation data includes: the actual power, the closing feedback value of the steam inlet isolation valve of the heater, and the fourth upstream and downstream pipeline data of the pipeline where the steam inlet isolation valve is located; wherein the steam inlet isolation valve of the heater controls the operation state of the heater; The performing fault diagnosis on the operating data according to the preset diagnostic logic and determining the fault diagnosis result comprises: Determine whether the shutdown feedback value meets the preset shutdown feedback value, the fourth upstream and downstream pipeline data is not abnormal, and the actual power exceeds the fourth preset power; If so, it is determined that the steam inlet isolation valve of the heater is faulty; In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes: Obtaining an eighth target power and an eighth power adjustment rate corresponding to the steam inlet isolation valve failure; The actual power is adjusted to the eighth target power according to the eighth power adjustment rate.

10. The nuclear power plant fault response method according to claim 1, characterized in that: The operation data includes: the actual power, the simulated state signal of the steam valve in the high-pressure cylinder steam turbine protection system, and the fifth upstream and downstream pipeline data of the pipeline where the steam valve in the high-pressure cylinder steam turbine protection system is located; wherein the steam valve in the high-pressure cylinder steam turbine protection system controls the operation state of the high-pressure cylinder steam turbine protection system; The performing fault diagnosis on the operating data according to the preset diagnostic logic and determining the fault diagnosis result comprises: Determine whether the simulation state signal satisfies a preset simulation state signal, the fifth upstream and downstream pipeline data is not abnormal, and the actual power exceeds the fifth preset power; If so, it is determined that a steam valve failure has occurred; In response to the fault diagnosis result, obtaining the corresponding target power and power regulation rate to regulate the actual power of the nuclear power unit includes: Obtaining a ninth target power and a ninth power regulation rate corresponding to the steam valve failure; The actual power is adjusted to the ninth target power according to the ninth power adjustment rate.

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