CN116994786A - Online diagnosis method for third-generation passive pressurized water reactor nuclear power station accident - Google Patents
Online diagnosis method for third-generation passive pressurized water reactor nuclear power station accident Download PDFInfo
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Abstract
The invention particularly relates to a third-generation advanced passive pressurized water reactor nuclear power station accident online diagnosis method, which comprises the steps of obtaining a standardized third-generation passive pressurized water reactor nuclear power station operation signal; identifying a state interval of a third-generation passive pressurized water reactor nuclear power plant; identifying the accident sign of the third-generation passive pressurized water reactor nuclear power plant; identifying abnormal states of a system of the third-generation passive pressurized water reactor nuclear power plant; and identifying the accident type of the third-generation passive pressurized water reactor nuclear power station according to the accident sign and the system abnormal state of the third-generation passive pressurized water reactor nuclear power station. The invention also relates to an accident online diagnosis system, computer equipment and storage medium of the third-generation advanced passive pressurized water reactor nuclear power station. The invention realizes the rapid, accurate and comprehensive diagnosis of the accident of the third-generation advanced passive pressurized water reactor nuclear power station based on a small amount of the operation signals of the third-generation advanced passive pressurized water reactor nuclear power station.
Description
Technical Field
The invention relates to the technical field of nuclear power simulation, in particular to an on-line diagnosis method for an accident of a third-generation passive pressurized water reactor nuclear power station.
Background
The nuclear power device of the third-generation passive pressurized water reactor nuclear power station has a complex structure, relates to a plurality of devices, and is provided with sensors for real-time monitoring in order to timely and comprehensively grasp the states of the devices, so that when the operation of the nuclear power station is abnormal, especially when the operation of the nuclear power station is developed under the condition of serious accidents, operators and emergency response technicians of the power station need to locate abnormal information from mass monitoring data and alarm signals, and further correct decisions are made. Even in severe accident phases, power loss, large-area damage to meters and large-area failure of meters are often accompanied, and the power plant state monitoring information provided by the nuclear power plant is incomplete and accurate, so that the difficulty of correct decision making is further aggravated. If misoperations are taken by personnel misjudgment or other personnel risks, accidents are extremely likely to be seriously worsened. Thus, the related personnel can have great working pressure and psychological stress under the condition. Under the condition that an accident occurs in a nuclear power plant, the root cause and the current operation state of the accident of the power plant are required to be diagnosed according to limited trusted operation data, and powerful technical support is provided for emergency treatment of the nuclear accident.
Disclosure of Invention
The invention aims to provide an on-line diagnosis method for the accident of a third-generation advanced passive pressurized water reactor nuclear power station, which can rapidly, accurately and comprehensively complete the diagnosis of the accident of the third-generation advanced passive pressurized water reactor nuclear power station according to a small amount of operation signals of the third-generation advanced passive pressurized water reactor nuclear power station.
In order to achieve the above object, the present invention provides the following technical solutions:
an on-line diagnosis method for the accident of the third generation passive pressurized water reactor nuclear power station comprises the following steps:
s101, preprocessing the read operation signal of the third-generation passive pressurized water reactor nuclear power station to obtain a standardized operation signal of the third-generation passive pressurized water reactor nuclear power station;
s102, identifying a state interval of the third-generation passive pressurized water reactor nuclear power station according to a standardized third-generation passive pressurized water reactor nuclear power station operation signal;
s103, identifying the accident symptom of the third-generation passive pressurized water reactor nuclear power station according to the standardized operation signal of the third-generation passive pressurized water reactor nuclear power station;
s104, identifying the abnormal state of the system of the third-generation passive pressurized water reactor nuclear power station according to the standardized operation signal of the third-generation passive pressurized water reactor nuclear power station;
s105, identifying the accident type of the third-generation passive pressurized water reactor nuclear power station according to the accident symptom and the system abnormal state of the third-generation passive pressurized water reactor nuclear power station.
Further, in S101, preprocessing the read third generation passive pressurized water reactor nuclear power plant operation signal, including performing validity check on the read third generation passive pressurized water reactor nuclear power plant operation signal, and identifying and processing an abnormal signal in the read third generation passive pressurized water reactor nuclear power plant operation signal; performing validity check on the read operation signals of the third-generation passive pressurized water reactor nuclear power station, wherein the validity check comprises checking whether the signals are in a design range and checking the consistency of multiple signal channels; identifying and processing abnormal signals in the third-generation passive pressurized water reactor nuclear power station operation signals, including identifying default values, abnormal values and multiple signals in the read third-generation passive pressurized water reactor nuclear power station operation signals, removing the default values and the abnormal values in the third-generation passive pressurized water reactor nuclear power station operation signals, and merging the multiple signals in the read third-generation passive pressurized water reactor nuclear power station operation signals.
Further, S102, including the following steps:
s1021, judging each problem related to the state interval of the third-generation passive pressurized water reactor nuclear power station according to the standardized third-generation passive pressurized water reactor nuclear power station operation signal, and obtaining the judging result of all the problems related to the state interval of the third-generation passive pressurized water reactor nuclear power station;
S1022, associating judgment results of all problems related to the state interval of the third-generation passive pressurized water reactor nuclear power plant with the state relation matrix of the third-generation passive pressurized water reactor nuclear power plant to obtain the state interval of the third-generation passive pressurized water reactor nuclear power plant;
the judging result of each problem related to the state interval of the third-generation passive pressurized water reactor nuclear power station is yes or no; if the judgment result is yes, the column of the state relation matrix corresponding to the third generation passive pressurized water reactor nuclear power station where the problem is located takes a value of 1; if the judging result is negative, the column value of the problem in the state relation matrix corresponding to the third-generation passive pressurized water reactor nuclear power station is 0; the third generation passive pressurized water reactor nuclear power station state relation matrix is a third generation passive pressurized water reactor nuclear power station state section corresponding to the judgment result of all problems related to the third generation passive pressurized water reactor nuclear power station state section.
Further, S103 includes the following steps: and identifying the accident sign of the third-generation passive pressurized water reactor nuclear power plant by comparing the numerical value change of the operation signal of the third-generation passive pressurized water reactor nuclear power plant at the moment with the previous moment or whether the numerical value of the operation signal of the third-generation passive pressurized water reactor nuclear power plant at the moment exceeds a set threshold range.
Further, the third generation passive pressurized water reactor nuclear power plant accident symptoms include low main system pressure, non-failure of the pressure vessel, high containment pressure, high pit water level, high evaporator radioactive dose, high evaporator water level, SGTR observed by operators, suspected main system breach and coolant loss not containment, ac loss, low stabilizer water level, low main system temperature, high main system pressure, high containment temperature, reactor shutdown and reactor power drop.
Further, S104 includes the following steps:
s1041, determining likelihood function variables of each problem related to abnormal state identification of a third-generation passive pressurized water reactor nuclear power station system according to standardized third-generation passive pressurized water reactor nuclear power station operation signals;
s1042, calculating the confidence probability of each problem establishment related to the abnormal state identification of the third generation passive pressurized water reactor nuclear power station system according to the likelihood function;
s1043, calculating the confidence probability of each problem establishment related to the abnormal state of the third-generation passive pressurized water reactor nuclear power station system according to the standardized third-generation passive pressurized water reactor nuclear power station operation signal;
S1044, taking an average value of the confidence probabilities of all problems related to the abnormal state of the system of the third-generation passive pressurized water reactor nuclear power plant to obtain the confidence probability of the abnormal state of the system of the third-generation passive pressurized water reactor nuclear power plant;
s1045, judging whether the calculation results of S1043 and S1044 meet the set confidence probability judgment condition of the abnormal state of the third generation passive pressurized water reactor nuclear power station system, and if so, identifying the abnormal state of the third generation passive pressurized water reactor nuclear power station system;
the confidence probability judging condition of the abnormal state of the third generation passive pressurized water reactor nuclear power station system is as follows: the confidence probability of the abnormal state of the system of the third-generation passive pressurized water reactor nuclear power station is more than 0.5; or the confidence probability of the abnormal state of the system of the third-generation passive pressurized water reactor nuclear power station is larger than 0.5, and the confidence probability of the establishment of one or more problems related to the abnormal state of the system of the third-generation passive pressurized water reactor nuclear power station is larger than 0.5.
Further, the abnormal state of the third generation passive pressurized water reactor nuclear power station system comprises an abnormal charging and discharging state; problems associated with the identification of the abnormal charging and discharging include: an indication of whether a high pressure injection flow rate is present, the high pressure injection flow rate being approximately the desired value; the water level of the voltage stabilizer is high or rises; secondary side heat traps are disabled or lost; no indication of a breach was previously apparent; whether the pressure change of the main system is consistent with the high-pressure injection flow or not, and whether saturated water flows out of the release valve or not is found; the confidence probability judging conditions of the abnormal upper charging and discharging are as follows: the confidence probability of the abnormal upper charge and lower discharge is larger than 0.5, and the confidence probability of the first problem related to the abnormal upper charge and lower discharge is larger than 0.5.
Further, S105 includes the following steps:
the fuzzy expert knowledge base constructs a diagnosis tree of each type of accident of the third generation passive pressurized water reactor nuclear power station according to the diagnosis conditions of each type of accident of the third generation passive pressurized water reactor nuclear power station;
judging whether each diagnosis condition of each type of accident of the third-generation passive pressurized water reactor nuclear power plant is met according to a diagnosis tree of each type of accident of the third-generation passive pressurized water reactor nuclear power plant, and calculating the confidence probability that each diagnosis condition of each type of accident of the third-generation passive pressurized water reactor nuclear power plant is met;
taking an arithmetic average value of the confidence probabilities that all diagnostic conditions of each type of accident of the third-generation passive pressurized water reactor nuclear power station are met, and obtaining the confidence probabilities of each type of accident of the third-generation passive pressurized water reactor nuclear power station;
when the confidence probability of the type of accidents of the third-generation passive pressurized water reactor nuclear power plant is greater than 0.5, judging that the type of accidents exist in the third-generation passive pressurized water reactor nuclear power plant;
the diagnosis conditions of each type of accident of the third-generation passive pressurized water reactor nuclear power plant comprise a plurality of third-generation passive pressurized water reactor nuclear power plant accident symptoms and/or abnormal states of a system of the third-generation passive pressurized water reactor nuclear power plant.
Further, the third generation passive pressurized water reactor nuclear power plant type accidents include a coolant loss type accident, a heat transfer pipe break type accident, a whole plant power loss type accident, a main steam pipe break type accident and an unexpected shutdown type accident.
The invention also provides an accident online diagnosis system of the third-generation passive pressurized water reactor nuclear power station, which comprises the following steps:
the data processing module 201 is configured to pre-process the read third generation passive pressurized water reactor nuclear power station operation signal to obtain a standardized third generation passive pressurized water reactor nuclear power station operation signal;
the first identifying module 202 is configured to identify a state interval of the third generation passive pressurized water reactor nuclear power plant according to the standardized third generation passive pressurized water reactor nuclear power plant operation signal;
the second identifying module 203 is configured to identify, according to the standardized operation signal of the third generation passive pressurized water reactor nuclear power plant, an accident sign of the third generation passive pressurized water reactor nuclear power plant;
the third identifying module 204 is configured to identify an abnormal state of the system of the third generation passive pressurized water reactor nuclear power plant according to the standardized operation signal of the third generation passive pressurized water reactor nuclear power plant;
a fourth identifying module 205, configured to identify an accident type of the third generation passive pressurized water reactor nuclear power plant according to an accident symptom and a system abnormal state of the third generation passive pressurized water reactor nuclear power plant;
The data processing module 201, the first recognition module 202, the second recognition module 203, the third recognition module 204 and the fourth recognition module 205.
The invention also provides computer equipment, which comprises a memory and a processor, wherein the memory is stored with computer readable instructions, and the processor realizes the steps of the third-generation passive pressurized water reactor nuclear power station accident online diagnosis method when executing the computer readable instructions.
The invention also provides a computer readable storage medium, wherein the computer readable storage medium is stored with computer readable instructions, and the computer readable instructions realize the steps of the third generation passive pressurized water reactor nuclear power station accident online diagnosis method when being executed.
The beneficial technical effects of the invention are as follows:
the method, the system, the computer equipment and the storage medium for diagnosing the third-generation advanced passive pressurized water reactor nuclear power station accident online can complete the diagnosis of the state interval, the accident sign, the system abnormal state and the accident type of the third-generation advanced passive pressurized water reactor nuclear power station within 300 seconds based on 120 operation data of the third-generation passive pressurized water reactor nuclear power station, and the accuracy is more than 95%, so that the rapid, accurate and comprehensive accident diagnosis of the third-generation advanced passive pressurized water reactor nuclear power station is realized.
Drawings
FIG. 1 is a flow chart of one embodiment of the third generation advanced passive pressurized water reactor nuclear power plant incident on-line diagnostic method of the present application;
FIG. 2 is a schematic diagram of an embodiment of an accident online diagnostic system for a third generation advanced passive pressurized water reactor nuclear power plant of the present application;
FIG. 3 is a schematic diagram of a computer device according to an embodiment of the present application.
Detailed Description
Unless defined otherwise, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this application belongs; the terminology used in the description of the application herein is for the purpose of describing particular embodiments only and is not intended to be limiting of the application; the terms "comprising" and "having" and any variations thereof, in the description of the application and the claims and the description of the drawings above, are intended to cover a non-exclusive inclusion. The terms first, second and the like in the description and in the claims or in the above-described figures, are used for distinguishing between different objects and not necessarily for describing a sequential or chronological order.
Reference herein to "an embodiment" means that a particular feature, structure, or characteristic described in connection with the embodiment may be included in at least one embodiment of the application. The appearances of such phrases in various places in the specification are not necessarily all referring to the same embodiment, nor are separate or alternative embodiments mutually exclusive of other embodiments. Those of skill in the art will explicitly and implicitly appreciate that the embodiments described herein may be combined with other embodiments.
The technical solutions of the present invention will be clearly and completely described below with reference to the accompanying drawings and specific embodiments.
Referring to fig. 1, the embodiment provides an on-line diagnosis method for an accident of a third generation passive pressurized water reactor nuclear power station, which comprises the following steps:
s101, preprocessing the read operation signal of the third-generation passive pressurized water reactor nuclear power station to obtain a standardized operation signal of the third-generation passive pressurized water reactor nuclear power station shown in the table 1;
s102, identifying a state interval of the third-generation passive pressurized water reactor nuclear power station according to a standardized third-generation passive pressurized water reactor nuclear power station operation signal;
s103, identifying the accident symptom of the third-generation passive pressurized water reactor nuclear power station according to the standardized operation signal of the third-generation passive pressurized water reactor nuclear power station;
s104, identifying the abnormal state of the system of the third-generation passive pressurized water reactor nuclear power station according to the standardized operation signal of the third-generation passive pressurized water reactor nuclear power station;
s105, identifying the accident type of the third-generation passive pressurized water reactor nuclear power station according to the accident symptom and the system abnormal state of the third-generation passive pressurized water reactor nuclear power station.
It should be understood that the various sub-steps or stages in each step are not necessarily performed at the same time, but may be performed at different times, the order of execution of which is not necessarily sequential, but may be performed in rotation or alternatively with other steps or at least a portion of the sub-steps or stages of other steps.
In this embodiment, in S101, preprocessing is performed on the read third generation passive pressurized water reactor nuclear power plant operation signal, including performing validity check on the read third generation passive pressurized water reactor nuclear power plant operation signal, and identifying and processing an abnormal signal in the read third generation passive pressurized water reactor nuclear power plant operation signal; performing validity check on the read operation signals of the third-generation passive pressurized water reactor nuclear power station, wherein the validity check comprises checking whether the signals are in a design range and checking the consistency of multiple signal channels; identifying and processing abnormal signals in the third-generation passive pressurized water reactor nuclear power station operation signals, including identifying default values, abnormal values and multiple signals in the read third-generation passive pressurized water reactor nuclear power station operation signals, removing the default values and the abnormal values in the third-generation passive pressurized water reactor nuclear power station operation signals, and merging the multiple signals in the read third-generation passive pressurized water reactor nuclear power station operation signals.
Table 1 standardized third generation passive pressurized water reactor nuclear power plant operating signals
In this embodiment, S102 includes the following steps:
s1021, judging each problem related to the state interval of the third-generation passive pressurized water reactor nuclear power station according to the standardized third-generation passive pressurized water reactor nuclear power station operation signal, and obtaining the judging result of all the problems related to the state interval of the third-generation passive pressurized water reactor nuclear power station;
S1022, correlating the judging result of all problems related to the state section of the third generation passive pressurized water reactor nuclear power plant with the state relation matrix of the third generation passive pressurized water reactor nuclear power plant shown in the table 2 to obtain the state section of the third generation passive pressurized water reactor nuclear power plant.
In this embodiment, as shown in table 2, the problems related to the state interval of the third generation passive pressurized water reactor nuclear power plant include problem 1, problem 2, problem 3, problem 4, problem 5, problem 6, problem 7 and problem 8, wherein problem 1 is whether the core is bare, problem 2 is whether the core is bare for more than 10 minutes, problem 3 is whether the core outlet temperature is more than 1300K, problem 4 is whether the inside of the containment is a high-activity environment, problem 5 is whether the containment temperature is more than 600K, problem 6 is whether the main system pressure is close to the containment pressure, problem 7 is whether the containment pressure exceeds the design reference and rises, and problem 8 is whether the containment pressure rises for more than 30 minutes; the judging result of each problem related to the state interval of the third-generation passive pressurized water reactor nuclear power station is yes or no; if the judgment result is yes, the column of the state relation matrix corresponding to the third generation passive pressurized water reactor nuclear power station where the problem is located takes a value of 1; if the judging result is negative, the column value of the problem in the state relation matrix corresponding to the third-generation passive pressurized water reactor nuclear power station is 0; the third generation passive pressurized water reactor nuclear power station state relation matrix is a third generation passive pressurized water reactor nuclear power station state section corresponding to the judgment result of all problems related to the third generation passive pressurized water reactor nuclear power station state section.
TABLE 2 third generation passive pressurized water reactor nuclear power plant state relationship matrix
In this embodiment, S103 includes the steps of:
and identifying the accident sign of the third-generation passive pressurized water reactor nuclear power plant by comparing the numerical value change of the operation signal of the third-generation passive pressurized water reactor nuclear power plant at the moment with the previous moment or whether the numerical value of the operation signal of the third-generation passive pressurized water reactor nuclear power plant at the moment is within a set threshold value range.
In this embodiment, the third generation passive pressurized water reactor nuclear power plant accident symptoms include low main system pressure, no failure of the pressure vessel, high containment pressure, high pit water level, high evaporator radioactive agent, high evaporator water level, SGTR observed by operators to have occurred, suspected main system breach and coolant loss not being containment, ac loss, low regulator water level, low main system temperature, high main system pressure, high containment temperature, reactor shutdown and reactor power drop;
if the pressure value of the main system at the current moment is smaller than the opening threshold value of the safety valve of the voltage stabilizer, the main system is identified to be low; if the change rate of the pressure value of the main system at the current moment is smaller than zero at the last moment, the pressure drop of the main system is identified; if the state interval of the third-generation passive pressurized water reactor nuclear power station is before the failure of the pressure vessel, the pressure vessel is identified as not being failed; if the containment pressure value at the current moment is greater than 175% of the atmospheric pressure, identifying that the containment pressure is high; if the change rate of the containment pressure value at the current moment is greater than zero at the last moment, identifying that the containment pressure rises; if the change rate of the pit water level value at the current moment is greater than zero at the last moment, the pit water level is identified to be raised; if the radioactive dose value of the evaporator at the current moment is larger than the radioactive dose average value of other evaporators, identifying that the radioactive dose of the evaporator is high; if the water level value of the evaporator at the current moment is larger than the water level high set value of the evaporator, identifying that the water level of the evaporator is high; if the change rate of the evaporator number water level value at the current moment is larger than zero, identifying that the evaporator number water level rises; if the presence operator observes that the SGTR has occurred, identifying that the operator observed that SGTR has occurred; if the suspected main system is broken and the coolant loss is not a containment signal, identifying that the suspected main system is broken and the coolant loss is not a containment; identifying an ac loss if an ac loss signal is present; if the water level value of the voltage stabilizer at the current moment is smaller than the steady-state operation water level value of the voltage stabilizer, the water level of the voltage stabilizer is identified to be low; if the change rate of the temperature value of the main system at the current moment and the last moment is larger than the maximum rate allowed by the regulations, the temperature of the main system is identified to be reduced; if the pressure value of the main system at the current moment is larger than the pressure value of the damaged evaporator, the main system is identified to be high; if the containment pressure value at the current moment is greater than 175% of the atmospheric pressure, identifying that the containment pressure is high; if the containment temperature value at the current moment is greater than 120% of the steady-state containment operating temperature value, identifying that the containment temperature is high; identifying a reactor trip if a reactor trip signal is present; if the rate of change of reactor power at the current time and at a time immediately above is greater than the decay heat theoretical curve, a reactor power drop is identified.
In this embodiment, S104 includes the following steps:
s1041, determining likelihood function variables of each problem related to abnormal state identification of a third-generation passive pressurized water reactor nuclear power station system according to standardized third-generation passive pressurized water reactor nuclear power station operation signals;
s1042, calculating the confidence probability of each problem establishment related to the abnormal state identification of the third generation passive pressurized water reactor nuclear power station system according to the likelihood function;
s1043, calculating the confidence probability of each problem establishment related to the abnormal state of the third-generation passive pressurized water reactor nuclear power station system according to the standardized third-generation passive pressurized water reactor nuclear power station operation signal;
s1044, taking an average value of the confidence probabilities of all problems related to the abnormal state of the system of the third-generation passive pressurized water reactor nuclear power plant to obtain the confidence probability of the abnormal state of the system of the third-generation passive pressurized water reactor nuclear power plant;
s1045, judging whether the calculation results of S1043 and S1044 meet the set confidence probability judgment condition of the abnormal state of the third generation passive pressurized water reactor nuclear power station system, and if so, identifying the abnormal state of the third generation passive pressurized water reactor nuclear power station system;
The confidence probability judging condition of the abnormal state of the third generation passive pressurized water reactor nuclear power station system is as follows: the confidence probability of the abnormal state of the system of the third-generation passive pressurized water reactor nuclear power station is more than 0.5; or the confidence probability of the abnormal state of the system of the third-generation passive pressurized water reactor nuclear power station is larger than 0.5, and the confidence probability of the establishment of one or more problems related to the abnormal state of the system of the third-generation passive pressurized water reactor nuclear power station is larger than 0.5.
In the embodiment, the abnormal state of the system of the third-generation passive pressurized water reactor nuclear power station comprises an abnormal state of filling and discharging; problems associated with the identification of the abnormal charging and discharging include: an indication of whether a high pressure injection flow rate is present, the high pressure injection flow rate being approximately the desired value; the water level of the voltage stabilizer is high or rises; secondary side heat traps are disabled or lost; no indication of a breach was previously apparent; whether the pressure change of the main system is consistent with the high-pressure injection flow or not, and whether saturated water flows out of the release valve or not is found;
determining the difference between the third generation passive pressurized water reactor nuclear power station and the upper charging and the lower discharging according to the standardized operation signal of the third generation passive pressurized water reactor nuclear power stationLikelihood function variables of each question associated with constant identification, e.g. likelihood function variable x of first question associated with the identification of a charging and discharging anomaly 1 =5 (2 x (high-pressure injection flow rate value/high-pressure injection flow rate expected value at the present time) -1); likelihood function variable x of second problem related to upper charge and lower discharge abnormality identification 2 =5 (2×1 (regulator water level value/regulator water level expected value at the present moment); likelihood function variable x of third problem related to upper charge and lower discharge abnormality recognition 3 =5 (2 x (secondary side hot-well value/secondary side hot-well expected value at the current time) -1); likelihood function variable x of fourth problem related to upper charge and lower discharge abnormality recognition 4 =5 (2 x (break value/break expected value at current time) -1); likelihood function variable x of fifth problem related to upper charge and lower discharge abnormality recognition 5 =5 (2 x (main system pressure value/main system pressure expected value at the current time) -1);
calculating confidence probability of establishment of each problem related to the up-down-charging abnormality identification by likelihood function, confidence probability f (x 1 )＝1/(1+e -x1 ) Confidence probability f (x) that the second problem related to the upper-charge-lower-discharge abnormality recognition is established 2 )＝1/(1+e -x2 ) Confidence probability f (x) that third problem related to the abnormal recognition of the charging and discharging is established 3 )＝1/(1+e -x3 ) Confidence probability f (x) that the fourth problem related to the upper-charge-lower-discharge abnormality recognition is established 4 )＝1/(1+e -x4 ) Confidence probability f (x) that fifth problem related to the identification of the abnormal charge/discharge is established 5 )＝1/(1+e -x5 ) The method comprises the steps of carrying out a first treatment on the surface of the The likelihood function is: f (x) =1/(1+e -x ) The method comprises the steps of carrying out a first treatment on the surface of the x is a likelihood function variable, and f (x) is a confidence probability;
the confidence probabilities that all the problems related to the upper-charge-lower-discharge abnormality recognition are satisfied are averaged to obtain a confidence probability= (f (x) 1 )+f(x 2 )+f(x 3 )+f(x 4 )+f(x 5 ))/5；
If the confidence probability calculation result of the upper charging and lower discharging abnormality meets the set confidence probability judgment condition of the upper charging and lower discharging abnormality, the upper charging and lower discharging abnormality is identified;
the confidence probability judging conditions of the abnormal upper charging and discharging are as follows: the confidence probability of the abnormal upper charge and lower discharge is larger than 0.5, and the confidence probability of the first problem related to the abnormal upper charge and lower discharge identification is larger than 0.5.
In the present embodiment, S105 includes the steps of:
the fuzzy expert knowledge base constructs a diagnosis tree of each type of accident of the third generation passive pressurized water reactor nuclear power station according to the diagnosis conditions of each type of accident of the third generation passive pressurized water reactor nuclear power station;
judging whether each diagnosis condition of each type of accident of the third-generation passive pressurized water reactor nuclear power plant is met according to a diagnosis tree of each type of accident of the third-generation passive pressurized water reactor nuclear power plant, and calculating the confidence probability that each diagnosis condition of each type of accident of the third-generation passive pressurized water reactor nuclear power plant is met;
Taking an arithmetic average value of the confidence probabilities that all diagnostic conditions of each type of accident of the third-generation passive pressurized water reactor nuclear power station are met, and obtaining the confidence probabilities of each type of accident of the third-generation passive pressurized water reactor nuclear power station;
and when the confidence probability of the type of accidents of the third-generation passive pressurized water reactor nuclear power plant is larger than 0.5, judging that the type of accidents exist in the third-generation passive pressurized water reactor nuclear power plant.
In this embodiment, the third generation passive pressurized water reactor nuclear power plant type accidents include a coolant loss type accident, a heat transfer pipe break type accident, a whole plant power loss type accident, a main steam pipe break type accident, and an unexpected shutdown type accident.
In this embodiment, the diagnosis conditions for the loss of coolant accident are: first diagnostic conditions: the main system pressure is low; second diagnostic conditions: the main system pressure drops; third diagnostic conditions: the pressure vessel did not fail; fourth diagnostic conditions: the containment pressure is high; fifth diagnostic conditions: the containment pressure rises; sixth diagnostic condition: the pit water level rises; seventh diagnostic condition: abnormal upper-charging and lower-discharging; the fuzzy expert knowledge base constructs a diagnosis tree of the coolant loss accident according to the diagnosis conditions of the coolant loss accident;
Judging that the third generation passive pressurized water reactor nuclear power station has a coolant loss accident, comprising the following steps:
judging whether each diagnosis condition of the coolant loss accident is met according to the diagnosis tree of the coolant loss accident;
calculating the confidence probability that each diagnosis condition of the coolant loss accident is met according to the diagnosis tree of the coolant loss accident;
the confidence probabilities that the first diagnosis condition, the second diagnosis condition, the fourth diagnosis condition, the fifth diagnosis condition and the sixth diagnosis condition are met are all calculated through likelihood functions, and the confidence probabilities that the third diagnosis condition, the seventh diagnosis condition and the eighth diagnosis condition are met are all 100%;
confidence probability of coolant loss accident= (confidence probability of first diagnosis condition being established + confidence probability of second diagnosis condition being established + confidence probability of third diagnosis condition being established + confidence probability of fourth diagnosis condition being established + confidence probability of fifth diagnosis condition being established + confidence probability of sixth diagnosis condition being established + confidence probability of seventh diagnosis condition being established + confidence probability of eighth diagnosis condition being established)/8;
and when the confidence probability of the coolant loss accident is larger than 0.5, judging that the coolant loss accident exists in the third-generation passive pressurized water reactor nuclear power station.
In this embodiment, the diagnosis conditions for the heat transfer tube break type accident are: first diagnostic conditions: the radioactive dose of the evaporator is high; second diagnostic conditions: the water level of the evaporator is high; third diagnostic conditions: the water level of the evaporator rises; fourth diagnostic conditions: the operator observes that SGTR has occurred; fifth diagnostic conditions: suspected main system breach and coolant loss is not containment; the fuzzy expert knowledge base constructs a diagnosis tree of the heat transfer pipe break type accident according to the diagnosis conditions of the heat transfer pipe break type accident;
judging that the third generation passive pressurized water reactor nuclear power station has a heat transfer pipe break accident, comprising the following steps:
judging whether each diagnosis condition of the coolant loss accident is met according to the diagnosis tree of the coolant loss accident;
calculating the confidence probability that each diagnosis condition of the heat transfer pipe break accident is met according to the diagnosis tree of the heat transfer pipe break accident;
the confidence probabilities that the first diagnosis condition, the second diagnosis condition, the third diagnosis condition and the fifth diagnosis condition are met are all calculated through likelihood functions, and the confidence probabilities that the fourth diagnosis condition is met are all 100%;
confidence probability of heat transfer tube break accident= (confidence probability of first diagnosis condition being established + confidence probability of second diagnosis condition being established + confidence probability of third diagnosis condition being established + confidence probability of fourth diagnosis condition being established + confidence probability of fifth diagnosis condition being established)/5;
And when the confidence probability of the heat transfer pipe break accident is more than 0.5, judging that the heat transfer pipe break accident exists in the third-generation passive pressurized water reactor nuclear power station.
In this embodiment, the diagnosis conditions of the power failure accident of the whole plant are: first diagnostic conditions: loss of ac signal; the fuzzy expert knowledge base constructs a diagnosis tree of the whole-plant power-losing accidents according to the diagnosis conditions of the whole-plant power-losing accidents;
judging that the third generation passive pressurized water reactor nuclear power station has a whole-plant power failure accident, comprising the following steps:
judging whether each diagnosis condition of the whole-plant power-losing accident is met or not according to the diagnosis tree of the whole-plant power-losing accident;
calculating the confidence probability that each diagnosis condition of the whole-plant power-loss accident is met according to the diagnosis tree of the whole-plant power-loss accident;
wherein, the confidence probabilities of the first diagnosis condition are 100%;
confidence probability of the whole plant power loss accident = confidence probability that the first diagnostic condition is true;
and when the confidence probability of the whole-plant power failure accident is larger than 0.5, judging that the whole-plant power failure accident exists in the third-generation passive pressurized water reactor nuclear power station.
In this embodiment, the diagnosis conditions of the main steam pipe break type accident are: first diagnostic conditions: the water level of the voltage stabilizer is low; second diagnostic conditions: the temperature of the main system is reduced; third diagnostic conditions: the main system pressure is high; fourth diagnostic conditions: the containment pressure is high; fifth diagnostic conditions: the containment temperature is high; the fuzzy expert knowledge base constructs a diagnosis tree of the main steam pipeline fracture accident according to the diagnosis conditions of the main steam pipeline fracture accident;
Judging that the third generation passive pressurized water reactor nuclear power station has a main steam pipeline fracture accident, comprising the following steps:
judging whether each diagnosis condition of the main steam pipeline fracture accident is met according to the diagnosis tree of the main steam pipeline fracture accident;
calculating the confidence probability that each diagnosis condition of the main steam pipeline fracture accident is met according to the diagnosis tree of the main steam pipeline fracture accident;
confidence probabilities that the first diagnosis condition, the second diagnosis condition, the third diagnosis condition, the fourth diagnosis condition and the fifth diagnosis condition are met are all calculated through likelihood functions;
confidence probability of main steam pipe break accident= (confidence probability of first diagnosis condition being met + confidence probability of second diagnosis condition being met + confidence probability of third diagnosis condition being met + confidence probability of fourth diagnosis condition being met + confidence probability of fifth diagnosis condition being met)/5;
and when the confidence probability of the main steam pipeline break accident is greater than 0.5, judging that the main steam pipeline break accident exists in the third-generation passive pressurized water reactor nuclear power station.
In this embodiment, the diagnosis conditions for unexpected shutdown type accidents are: first diagnostic conditions: shutdown of the reactor; second diagnostic conditions: reactor power drops; the fuzzy expert knowledge base constructs a diagnosis tree of unexpected shutdown accidents according to diagnosis conditions of unexpected shutdown accidents;
Judging that unexpected stop-reactor accidents exist in the third-generation passive pressurized water reactor nuclear power station, comprising the following steps of:
judging whether each diagnosis condition of the unexpected shutdown accident is met according to the diagnosis tree of the unexpected shutdown accident;
calculating the confidence probability that each diagnosis condition of the unexpected shutdown event is satisfied according to the diagnosis tree of the unexpected shutdown event;
wherein the confidence probability that the first diagnostic condition is established is 100%; the confidence probability that the second diagnosis condition is satisfied is calculated through a likelihood function;
confidence probability of unexpected shutdown class accident= (confidence probability of first diagnostic condition being established+confidence probability of second diagnostic condition being established)/2;
and when the confidence probability of the unexpected shutdown event is greater than 0.5, judging that the unexpected shutdown event exists in the third-generation passive pressurized water reactor nuclear power plant.
The method for diagnosing the accident of the third-generation advanced passive pressurized water reactor nuclear power station on line can complete the diagnosis of the state interval, the accident sign, the system abnormal state and the accident type of the third-generation advanced passive pressurized water reactor nuclear power station within 300 seconds based on 120 operation data of the third-generation passive pressurized water reactor nuclear power station, and the accuracy is over 95 percent, so that the rapid, accurate and comprehensive accident diagnosis of the third-generation advanced passive pressurized water reactor nuclear power station is realized.
Referring to fig. 2, as an implementation of the above method, the present invention provides an embodiment of an accident online diagnosis system for a third generation advanced passive pressurized water reactor nuclear power plant, which corresponds to the embodiment of the above method, and the system is particularly applicable to various electronic devices.
The third generation passive pressurized water reactor nuclear power station accident online diagnosis system according to the embodiment comprises:
the data processing module 201 is configured to pre-process the read third generation passive pressurized water reactor nuclear power station operation signal to obtain a standardized third generation passive pressurized water reactor nuclear power station operation signal;
the first identifying module 202 is configured to identify a state interval of the third generation passive pressurized water reactor nuclear power plant according to the standardized third generation passive pressurized water reactor nuclear power plant operation signal;
the second identifying module 203 is configured to identify, according to the standardized operation signal of the third generation passive pressurized water reactor nuclear power plant, an accident sign of the third generation passive pressurized water reactor nuclear power plant;
the third identifying module 204 is configured to identify an abnormal state of the system of the third generation passive pressurized water reactor nuclear power plant according to the standardized operation signal of the third generation passive pressurized water reactor nuclear power plant;
a fourth identifying module 205, configured to identify an accident type of the third generation passive pressurized water reactor nuclear power plant according to an accident symptom and a system abnormal state of the third generation passive pressurized water reactor nuclear power plant;
The data processing module 201, the first recognition module 202, the second recognition module 203, the third recognition module 204 and the fourth recognition module 205.
The accident online diagnosis system for the third-generation advanced passive pressurized water reactor nuclear power station can complete diagnosis of the state interval, the accident sign, the system abnormal state and the accident type of the third-generation advanced passive pressurized water reactor nuclear power station within 300 seconds based on 120 operation data of the third-generation passive pressurized water reactor nuclear power station, and has the accuracy rate of more than 95%, so that the rapid, accurate and comprehensive accident diagnosis of the third-generation advanced passive pressurized water reactor nuclear power station is realized.
Referring to fig. 3, the embodiment further provides a computer device, which includes a memory and a processor, where the memory stores computer readable instructions, and the processor implements the steps of the above-mentioned method for online diagnosis of an accident in a third generation passive pressurized water reactor nuclear power plant when executing the computer readable instructions.
The computer device of the present embodiment includes a memory 301, a processor 302, and a network interface 303 that are communicatively connected to each other through a system bus. It should be noted that only computer devices having components 301-303 are shown in the figures, but it should be understood that not all of the illustrated components are required to be implemented and that more or fewer components may be implemented instead. It will be appreciated by those skilled in the art that the computer device herein is a device capable of automatically performing numerical calculations and/or information processing according to predetermined or stored instructions, and the hardware thereof includes, but is not limited to, microprocessors, application specific integrated circuits, programmable gate arrays, digital processors, embedded devices, and the like.
The computer equipment can be a desktop computer, a notebook computer, a palm computer, a cloud server and other computing equipment. The computer equipment can perform man-machine interaction with a user through a keyboard, a mouse, a remote controller, a touch pad or voice control equipment and the like.
The memory 301 comprises at least one type of readable storage medium including flash memory, hard disk, multimedia card, card memory, random access memory, static random access memory, read only memory, electrically erasable programmable read only memory, magnetic disk, optical disk, and the like. In some embodiments, the memory 301 may be an internal storage unit of the computer device, such as a hard disk or a memory of the computer device. In other embodiments, the memory 301 may also be an external storage device of the computer device, such as a plug-in hard disk, a smart memory card, a secure digital card, a flash memory card, etc. that is provided on the computer device. Of course, the memory 301 may also include both an internal memory unit of the computer device and an external memory device. In this embodiment, the memory 301 is generally used to store an operating system and various application software installed on the computer device, for example, the computer readable instructions of the above-mentioned third generation passive pressurized water reactor nuclear power plant accident online diagnosis method. In addition, the memory 301 may be used to temporarily store various types of data that have been output or are to be output.
The processor 302 may be a central processing unit, controller, microcontroller, microprocessor, or other data processing chip in some embodiments. The processor 302 is typically used to control the overall operation of the computer device. In this embodiment, the processor 302 is configured to execute computer readable instructions stored in the memory 301 or process data, for example, computer readable instructions for executing the above-mentioned method for on-line diagnosis of an accident in a third generation passive pressurized water reactor nuclear power plant.
The network interface 303 may include a wireless network interface or a wired network interface, which network interface 303 is typically used to establish communication connections between the computer device and other electronic devices.
The computer equipment of the embodiment can complete diagnosis of the state interval, the accident sign, the system abnormal state and the accident type of the third-generation advanced passive pressurized water reactor nuclear power station within 300 seconds based on 120 operation data of the third-generation passive pressurized water reactor nuclear power station, and the accuracy is over 95 percent, so that the rapid, accurate and comprehensive accident diagnosis of the third-generation advanced passive pressurized water reactor nuclear power station is realized.
The embodiment also provides a computer readable storage medium, wherein computer readable instructions are stored on the computer readable storage medium, and the computer readable instructions realize the steps of the third generation passive pressurized water reactor nuclear power station accident online diagnosis method when being executed.
The computer readable storage medium of the embodiment can complete diagnosis of the state interval, the accident sign, the system abnormal state and the accident type of the third-generation advanced passive pressurized water reactor nuclear power station within 300 seconds based on 120 operation data of the third-generation passive pressurized water reactor nuclear power station, and the accuracy is over 95 percent, so that the rapid, accurate and comprehensive accident diagnosis of the third-generation advanced passive pressurized water reactor nuclear power station is realized.
The foregoing examples illustrate only a few embodiments of the invention and are described in detail herein without thereby limiting the scope of the invention. It should be noted that it will be apparent to those skilled in the art that several variations and modifications can be made without departing from the spirit of the invention, which are all within the scope of the invention. Accordingly, the scope of protection of the present invention is to be determined by the appended claims.
Claims (12)
1. An on-line diagnosis method for an accident of a third-generation passive pressurized water reactor nuclear power station is characterized by comprising the following steps:
s101, preprocessing the read operation signal of the third-generation passive pressurized water reactor nuclear power station to obtain a standardized operation signal of the third-generation passive pressurized water reactor nuclear power station;
S102, identifying a state interval of the third-generation passive pressurized water reactor nuclear power station according to a standardized third-generation passive pressurized water reactor nuclear power station operation signal;
s103, identifying the accident symptom of the third-generation passive pressurized water reactor nuclear power station according to the standardized operation signal of the third-generation passive pressurized water reactor nuclear power station;
s104, identifying the abnormal state of the system of the third-generation passive pressurized water reactor nuclear power station according to the standardized operation signal of the third-generation passive pressurized water reactor nuclear power station;
s105, identifying the accident type of the third-generation passive pressurized water reactor nuclear power station according to the accident symptom and the system abnormal state of the third-generation passive pressurized water reactor nuclear power station.
2. The method for on-line diagnosis of an accident in a third generation passive pressurized water reactor nuclear power plant according to claim 1, wherein in S101, preprocessing the read third generation passive pressurized water reactor nuclear power plant operation signal includes validity checking the read third generation passive pressurized water reactor nuclear power plant operation signal, and identifying and processing an abnormal signal in the read third generation passive pressurized water reactor nuclear power plant operation signal; performing validity check on the read operation signals of the third-generation passive pressurized water reactor nuclear power station, wherein the validity check comprises checking whether the signals are in a design range and checking the consistency of multiple signal channels; identifying and processing abnormal signals in the third-generation passive pressurized water reactor nuclear power station operation signals, including identifying default values, abnormal values and multiple signals in the read third-generation passive pressurized water reactor nuclear power station operation signals, removing the default values and the abnormal values in the third-generation passive pressurized water reactor nuclear power station operation signals, and merging the multiple signals in the read third-generation passive pressurized water reactor nuclear power station operation signals.
3. The method for on-line diagnosis of an accident in a third generation passive pressurized water reactor nuclear power plant according to claim 1, wherein S102 comprises the steps of:
s1021, judging each problem related to the state interval of the third-generation passive pressurized water reactor nuclear power station according to the standardized third-generation passive pressurized water reactor nuclear power station operation signal, and obtaining the judging result of all the problems related to the state interval of the third-generation passive pressurized water reactor nuclear power station;
s1022, associating judgment results of all problems related to the state interval of the third-generation passive pressurized water reactor nuclear power plant with the state relation matrix of the third-generation passive pressurized water reactor nuclear power plant to obtain the state interval of the third-generation passive pressurized water reactor nuclear power plant;
the judging result of each problem related to the state interval of the third-generation passive pressurized water reactor nuclear power station is yes or no; if the judgment result is yes, the column of the state relation matrix corresponding to the third generation passive pressurized water reactor nuclear power station where the problem is located takes a value of 1; if the judging result is negative, the column value of the problem in the state relation matrix corresponding to the third-generation passive pressurized water reactor nuclear power station is 0; the third generation passive pressurized water reactor nuclear power station state relation matrix is a third generation passive pressurized water reactor nuclear power station state section corresponding to the judgment result of all problems related to the third generation passive pressurized water reactor nuclear power station state section.
4. The method for on-line diagnosis of an accident in a third generation passive pressurized water reactor nuclear power plant according to claim 1, wherein S103 comprises the steps of: and identifying the accident sign of the third-generation passive pressurized water reactor nuclear power plant by comparing the numerical value change of the operation signal of the third-generation passive pressurized water reactor nuclear power plant at the moment with the previous moment or whether the numerical value of the operation signal of the third-generation passive pressurized water reactor nuclear power plant at the moment exceeds a set threshold range.
5. The method of on-line diagnosis of a third generation passive pressurized water reactor nuclear power plant incident of claim 4, wherein the third generation passive pressurized water reactor nuclear power plant incident sign includes a low main system pressure, a pressure vessel not failing, a high containment pressure, a pit water level, a high evaporator radioactive agent, a high evaporator water level, an operator observing that SGTR has occurred, a suspected main system breach and a coolant loss is not containment, an ac loss, a low regulator water level, a low main system temperature, a high main system pressure, a high containment temperature, a reactor shutdown, and a reactor power drop.
6. The method for on-line diagnosis of an accident in a third generation passive pressurized water reactor nuclear power plant according to claim 1, wherein S104 comprises the steps of:
s1041, determining likelihood function variables of each problem related to abnormal state identification of a third-generation passive pressurized water reactor nuclear power station system according to standardized third-generation passive pressurized water reactor nuclear power station operation signals;
s1042, calculating the confidence probability of each problem establishment related to the abnormal state identification of the third generation passive pressurized water reactor nuclear power station system according to the likelihood function;
s1043, calculating the confidence probability of each problem establishment related to the abnormal state of the third-generation passive pressurized water reactor nuclear power station system according to the standardized third-generation passive pressurized water reactor nuclear power station operation signal;
s1044, taking an average value of the confidence probabilities of all problems related to the abnormal state of the system of the third-generation passive pressurized water reactor nuclear power plant to obtain the confidence probability of the abnormal state of the system of the third-generation passive pressurized water reactor nuclear power plant;
s1045, judging whether the calculation results of S1043 and S1044 meet the set confidence probability judgment condition of the abnormal state of the third generation passive pressurized water reactor nuclear power station system, and if so, identifying the abnormal state of the third generation passive pressurized water reactor nuclear power station system;
The confidence probability judging condition of the abnormal state of the third generation passive pressurized water reactor nuclear power station system is as follows: the confidence probability of the abnormal state of the system of the third-generation passive pressurized water reactor nuclear power station is more than 0.5; or the confidence probability of the abnormal state of the system of the third-generation passive pressurized water reactor nuclear power station is larger than 0.5, and the confidence probability of the establishment of one or more problems related to the abnormal state of the system of the third-generation passive pressurized water reactor nuclear power station is larger than 0.5.
7. The method for on-line diagnosis of an accident in a third generation passive pressurized water reactor nuclear power plant according to claim 6, wherein the abnormal state of the system in the third generation passive pressurized water reactor nuclear power plant comprises an abnormal state of up-charging and down-discharging; problems associated with the identification of the abnormal charging and discharging include: an indication of whether a high pressure injection flow rate is present, the high pressure injection flow rate being approximately the desired value; the water level of the voltage stabilizer is high or rises; secondary side heat traps are disabled or lost; no indication of a breach was previously apparent; whether the pressure change of the main system is consistent with the high-pressure injection flow or not, and whether saturated water flows out of the release valve or not is found; the confidence probability judging conditions of the abnormal upper charging and discharging are as follows: the confidence probability of the abnormal upper charge and lower discharge is larger than 0.5, and the confidence probability of the first problem related to the abnormal upper charge and lower discharge is larger than 0.5.
8. The method for on-line diagnosis of an accident in a third generation passive pressurized water reactor nuclear power plant according to claim 1, wherein S105 comprises the steps of:
the fuzzy expert knowledge base constructs a diagnosis tree of each type of accident of the third generation passive pressurized water reactor nuclear power station according to the diagnosis conditions of each type of accident of the third generation passive pressurized water reactor nuclear power station;
judging whether each diagnosis condition of each type of accident of the third-generation passive pressurized water reactor nuclear power plant is met according to a diagnosis tree of each type of accident of the third-generation passive pressurized water reactor nuclear power plant, and calculating the confidence probability that each diagnosis condition of each type of accident of the third-generation passive pressurized water reactor nuclear power plant is met;
taking an arithmetic average value of the confidence probabilities that all diagnostic conditions of each type of accident of the third-generation passive pressurized water reactor nuclear power station are met, and obtaining the confidence probabilities of each type of accident of the third-generation passive pressurized water reactor nuclear power station;
when the confidence probability of the type of accidents of the third-generation passive pressurized water reactor nuclear power plant is greater than 0.5, judging that the type of accidents exist in the third-generation passive pressurized water reactor nuclear power plant;
the diagnosis conditions of each type of accident of the third-generation passive pressurized water reactor nuclear power plant comprise a plurality of third-generation passive pressurized water reactor nuclear power plant accident symptoms and/or abnormal states of a system of the third-generation passive pressurized water reactor nuclear power plant.
9. The method for on-line diagnosis of a third generation passive pressurized water reactor nuclear power plant accident according to claim 8, wherein the third generation passive pressurized water reactor nuclear power plant type accident includes a coolant loss accident, a heat transfer pipe break accident, a whole plant power loss accident, a main steam pipe break accident, and an unexpected shutdown accident.
10. An on-line diagnostic system for an accident of a third generation passive pressurized water reactor nuclear power station, which is characterized by comprising:
the data processing module 201 is configured to pre-process the read third generation passive pressurized water reactor nuclear power station operation signal to obtain a standardized third generation passive pressurized water reactor nuclear power station operation signal;
the first identifying module 202 is configured to identify a state interval of the third generation passive pressurized water reactor nuclear power plant according to the standardized third generation passive pressurized water reactor nuclear power plant operation signal;
the second identifying module 203 is configured to identify, according to the standardized operation signal of the third generation passive pressurized water reactor nuclear power plant, an accident sign of the third generation passive pressurized water reactor nuclear power plant;
the third identifying module 204 is configured to identify an abnormal state of the system of the third generation passive pressurized water reactor nuclear power plant according to the standardized operation signal of the third generation passive pressurized water reactor nuclear power plant;
A fourth identifying module 205, configured to identify an accident type of the third generation passive pressurized water reactor nuclear power plant according to an accident symptom and a system abnormal state of the third generation passive pressurized water reactor nuclear power plant;
the data processing module 201, the first recognition module 202, the second recognition module 203, the third recognition module 204 and the fourth recognition module 205.
11. A computer device comprising a memory and a processor, the memory having stored thereon computer readable instructions, wherein the processor, when executing the computer readable instructions, performs the steps of the method for on-line diagnosis of an accident in a third generation passive pressurized water reactor nuclear power plant as defined in any one of claims 1 to 9.
12. A computer readable storage medium having computer readable instructions stored thereon, wherein the computer readable instructions when executed implement the steps of the third generation passive pressurized water reactor nuclear power plant incident on-line diagnostic method of any of claims 1-9.
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