Instrument control monitoring method for automatic diagnosis and prompt of accident regulations of nuclear power station

Abstract

The invention relates to the technical field of power plant instrument control monitoring, and aims to solve the problems that an existing instrument control monitoring method is long in consumed time and large in personnel burden, and the optimal accident processing opportunity may be missed under the condition that the accident progress rapidly develops, and the accident processing time is prolonged. According to the instrument control monitoring method for automatic diagnosis and prompt of the accident regulations of the nuclear power station, the diagnostic logic is established according to the initial type of the event, and hierarchical arrangement judgment is introduced into the corresponding accident regulations; according to the method, step-by-step judgment is carried out according to a power loss type, a nuclear island equipment cooling water loss type, an earthquake type, a leakage type from a primary loop to a secondary loop, a secondary loop break type and a primary loop break type, corresponding accident regulations can be quickly and automatically diagnosed, and the diagnosed accident regulations are prompted to an operator, so that the diagnosis efficiency and accuracy of the accident regulations are improved, and the safety of a unit is ensured.

Description

Technical Field

[0001] The invention relates to the technical field of power plant instrumentation and control monitoring, and in particular to an instrumentation and control monitoring method for automatic diagnosis and prompting of nuclear power plant accident procedures. Background Art

[0002] The nuclear power plant has formulated accident procedures for initiating events and considered response measures and steps according to the progress of the accident, so as to provide guidance to the nuclear power plant operators when these initiating events occur and ensure the safety of the nuclear power plant.

[0003] The events that trigger the reactor shutdown are included in the post-shutdown accident procedures. For transients that can diagnose the causes of operational deviations and the initial causes of accidents, such procedures can be used to achieve rapid response and basically cover the scope of design basis accidents during the operation of the reactor unit.

[0004] The post-outage accident procedures have the following components:

[0005] 1) Accident handling procedures after shutdown (Type A);

[0006] 2) Post-shutdown diagnostic procedures (A0).

[0007] The post-shutdown accident procedure is applicable to the operation of the reactor power to the hot state, heating and cooling conditions. When a shutdown occurs, the A0 shutdown diagnostic procedure will be entered. For the conditions where the accident type can be diagnosed based on the power plant information, the operator will be guided to restore the nuclear power plant to the final safe shutdown state according to the post-shutdown accident handling procedure (Class A), that is, the post-shutdown accident handling procedure that can bring the nuclear power plant into the optimal radioactive material release and equipment component damage to the minimum termination state.

[0008] This type of regulations is mainly divided into secondary circuit rupture, leakage from primary circuit to secondary circuit, electrical failure, other system failure, etc. according to the type of accident. The corresponding disposal strategy is determined according to the accident conditions and the system equipment configuration of the power plant.

[0009] After the reactor is shut down, the steps for handling the accident procedure are that the operator first performs event-oriented diagnosis through the post-shutdown diagnostic procedure (A0), diagnoses a specific procedure based on the procedure, and then handles the accident according to this specific accident procedure.

[0010] At present, the post-shutdown diagnostic procedure (A0) paper operation document is used for accident procedure diagnosis. The operators in the main control room execute and confirm step by step, which leads to slow execution and low efficiency. In the event of an accident, the accident progresses quickly, with many alarm messages and multiple parameters to be monitored, which puts a lot of mental burden and pressure on the personnel.

[0011] It can be seen that the current diagnosis when an accident occurs uses a paper version of the accident procedure diagnostic procedure. The accident procedure diagnostic procedure has many diagnostic steps and is executed step by step. The diagnostic conditions are the equipment protection action or shutdown alarm signals appearing in the nuclear power plant operation system. The operator needs to confirm and judge step by step according to the paper documents, which is time-consuming and burdensome to personnel. In the case of a rapid development of the accident, the best time to handle the accident may be missed, which prolongs the time to handle the accident.

[0012] Therefore, there is a problem that the cause of the accident needs to be determined quickly and measures taken as soon as possible, while the current accident procedures are slow in the gradual diagnosis process. Summary of the invention

[0013] The purpose of the present invention is to overcome the defects of the prior art and provide an instrumentation and control monitoring method for automatic diagnosis and prompting of nuclear power plant accident procedures, which improves the efficiency and accuracy of diagnosis.

[0014] In order to achieve the above object, the present invention provides the following technical solutions:

[0015] An instrumentation and control monitoring method for automatic diagnosis and prompting of accident procedures in a nuclear power plant establishes a diagnosis logic according to the initial type of the event, makes a hierarchical arrangement judgment and introduces it into the corresponding accident procedures, and makes a step-by-step judgment according to the power failure type, the nuclear island equipment cooling water loss type, the earthquake type, the leakage from the primary circuit to the secondary circuit type, the secondary circuit rupture type, and the primary circuit rupture type. After the judgment, the accident handling procedures to be executed are displayed on the instrumentation and control screen, and the operator can directly extract the corresponding accident handling procedures to control the unit status according to the instructions, thereby reducing the burden of manual diagnosis based on paper procedures and improving the diagnosis speed and accuracy.

[0016] In some embodiments, a monitoring screen for automatic diagnosis of accident procedures is established, integrating and summarizing the alarm information of the diagnosis process.

[0017] In some embodiments, the power failure accident judgment includes the following steps:

[0018] Step 1.1: Triggering by a shutdown signal: the first judgment module is triggered by any shutdown signal, the YES unit of the first judgment module is triggered and enters the second judgment module through a connecting line;

[0019] Step 1.2: Determine whether the load section busbar of the factory power supply is de-energized during normal operation through the second judgment module. If de-energized, enter the third judgment module;

[0020] Step 1.3: Use the third judgment module to determine whether the bus voltage of the emergency load section of the power supply to the plant is lost. If so, enter the first judgment result block and instruct to execute the accident handling procedures for the loss of all power supplies in the plant. Otherwise, enter the second judgment result block and instruct to execute the accident handling procedures for the power failure of the normal operating load section, and remind the operator to execute the corresponding accident procedures.

[0021] In some embodiments, determining a nuclear island equipment cooling water loss accident includes the following steps:

[0022] Step 2.1: Triggering of a shutdown signal: triggering a first judgment module through any shutdown signal;

[0023] Step 2.2: Determine whether the load section busbar of the factory power supply is deenergized during normal operation by the second determination module. If not, enter the fourth determination module.

[0024] Step 2.3: Determine whether the cooling water system of the nuclear island system equipment is lost through the fourth judgment module. If lost, enter the third judgment result block and instruct to execute the nuclear island equipment cooling water loss accident handling procedures.

[0025] In some embodiments, determining a nuclear island equipment cooling water loss accident includes the following steps:

[0026] Step 2.1: Triggering of a shutdown signal: triggering a first judgment module through any shutdown signal;

[0027] Step 2.2: Determine whether the load section busbar of the factory power supply is deenergized during normal operation by the second determination module. If not, enter the fourth determination module.

[0028] Step 2.3: Determine whether the cooling water system of the nuclear island system equipment is lost through the fourth judgment module. If lost, enter the third judgment result block and instruct to execute the nuclear island equipment cooling water loss accident handling procedures.

[0029] In some embodiments, earthquake accident determination includes the following steps:

[0030] Step 3.1: Triggering a shutdown signal: triggering a first judgment module through any shutdown signal;

[0031] Step 3.2: Determine whether the load section busbar of the factory power supply is deenergized during normal operation through the second judgment module. If not, enter the fourth judgment module;

[0032] Step 3.3: Determine whether the cooling water system of the nuclear island system equipment is lost through the fourth judgment module. If not, enter the fifth judgment module;

[0033] Step 3.4: Determine whether an earthquake has occurred through the fifth judgment module. If an earthquake has occurred, enter the fourth judgment result block to instruct the execution of earthquake accident procedures.

[0034] In some embodiments, the judgment of a leakage accident from the primary circuit to the secondary circuit includes the following steps:

[0035] Step 4.1: Triggering of a shutdown signal: triggering a first judgment module through any shutdown signal;

[0036] Step 4.2: Determine whether the load section busbar of the factory power supply is deenergized during normal operation through the second judgment module. If not, enter the fourth judgment module;

[0037] Step 4.3: Determine whether the cooling water system of the nuclear island system equipment is lost through the fourth judgment module. If not, enter the fifth judgment module;

[0038] Step 4.4: Determine whether an earthquake has occurred through the fifth determination module, and if not, enter the sixth determination module;

[0039] Step 4.5: The sixth judgment module is used to determine whether the leakage signal from the primary circuit to the secondary circuit is triggered. If triggered, the seventh judgment module is used to determine whether the pressure in the containment increases. If increased, the fifth judgment result block is entered to instruct the execution of the accident procedures for the leakage from the primary circuit to the secondary circuit superimposed on the steam breach in the containment.

[0040] In some embodiments, if the pressure inside the containment shell does not increase, the eighth judgment module is passed; if the pressure of the secondary circuit outside the containment shell increases, the sixth judgment result block is entered, instructing the execution of the accident procedure of leakage from the first circuit to the second circuit superimposed on the steam rupture outside the containment shell; if the pressure of the secondary circuit outside the containment shell does not increase, the seventh judgment result block is entered, instructing the execution of the accident procedure of leakage from the first circuit to the second circuit.

[0041] In some embodiments, the secondary circuit breach accident determination includes the following steps:

[0042] Step 5.1: Triggering a shutdown signal: triggering a first judgment module through any shutdown signal;

[0043] Step 5.2: Determine whether the load section busbar of the factory power supply is deenergized during normal operation through the second judgment module. If not, enter the fourth judgment module;

[0044] Step 5.3: Determine whether the cooling water system of the nuclear island system equipment is lost through the fourth judgment module. If not, enter the fifth judgment module;

[0045] Step 5.4: Determine whether an earthquake has occurred through the fifth determination module, and if not, enter the sixth determination module;

[0046] Step 5.5: Determine whether the leakage signal from the first circuit to the second circuit is triggered by the sixth judgment module. If not, enter the ninth judgment module;

[0047] Step 5.6: If it is determined through the ninth judgment module that a breach and leakage of the secondary circuit occurs, the eighth judgment result block is entered to instruct the execution of the secondary circuit breach accident handling procedure.

[0048] In some embodiments, the judgment of a circuit breach accident includes the following steps:

[0049] Step 6.1: Triggering a shutdown signal: triggering a first judgment module through any shutdown signal;

[0050] Step 6.2: Determine whether the load section busbar of the factory power supply is deenergized during normal operation through the second judgment module. If not, enter the fourth judgment module;

[0051] Step 6.3: Determine whether the cooling water system of the nuclear island system equipment is lost through the fourth judgment module. If not, enter the fifth judgment module;

[0052] Step 6.4: Determine whether an earthquake has occurred through the fifth determination module, and if not, enter the sixth determination module;

[0053] Step 6.5: Determine whether the leakage signal from the first circuit to the second circuit is triggered by the sixth judgment module. If not, enter the ninth judgment module;

[0054] Step 6.6: Determine whether there is a rupture or leakage in the secondary circuit through the ninth judgment module. If not, enter the tenth judgment module;

[0055] Step 6.7: Determine whether a circuit has a breach through the tenth judgment module. If so, enter the ninth judgment result block to instruct the execution of the circuit breach fault handling procedure.

[0056] Compared with the prior art, the instrumentation and control monitoring method for automatic diagnosis and prompting of nuclear power plant accident procedures provided by the present invention has the following beneficial effects:

[0057] When various types of accidents occur, the present invention can quickly and automatically diagnose the corresponding accident procedures, and prompt the diagnosed accident procedures to the operator, thereby improving the diagnostic efficiency and accuracy of the accident procedures and ensuring the safety of the unit.

[0058] The present invention can realize automatic diagnosis when an accident occurs, remind the operator to quickly enter the required accident procedures, reduce the burden and time of personnel in executing paper procedures for step-by-step diagnosis, and improve the efficiency and accuracy of diagnosis.

[0059] Furthermore, the invention can comprehensively display the diagnostic process when an accident occurs, and summarize relevant parameters and important alarm information, so that personnel can fully understand the accident situation, analyze the cause of the accident, and intervene in the accident as soon as possible. BRIEF DESCRIPTION OF THE DRAWINGS

[0060] In order to more clearly illustrate the technical solution of the present invention, the following briefly introduces the drawings required for the technical description.

[0061] Figure 1 A logical schematic diagram of the instrumentation and control monitoring method for automatic diagnosis and prompting of nuclear power plant accident procedures provided by the present invention. DETAILED DESCRIPTION

[0062] The following is further explained in detail through specific implementation methods.

[0063] like Figure 1 As shown, the present invention sets 10 judgment modules and 9 judgment result blocks.

[0064] The first judgment module 1 is used to judge whether the shutdown signal is triggered; the second judgment module 2 is used to judge whether the load section bus of the normal operation of the power plant is de-energized, and the voltage of the power plant bus is lower than 4.2kV (normal value 10kV) as the judgment condition in the logic; the third judgment module 3 is used to judge whether the voltage of the emergency load section bus of the power plant is de-energized, and the voltage of the power plant bus is lower than 4.2kV (normal value 10kV) as the judgment condition in the logic; the fourth judgment module 4 is used to judge whether the cooling water system of the nuclear island system equipment is lost, and the signal that all the cooling water pumps of the nuclear island equipment are shut down is used as the judgment condition in the logic; the fifth judgment module 5 is used to judge whether an earthquake occurs, and it is judged by whether the alarm signal of the earthquake acceleration exceeding the limit value appears; the sixth judgment module 6 is used to judge whether the leakage signal from the primary circuit to the secondary circuit is triggered, and it is judged by whether the alarm signal of the radioactivity exceeding the limit value of the secondary circuit appears; the seventh judgment module 7 is used to judge whether the pressure in the containment increases, so as to judge whether there is a leakage of the medium in the primary circuit or the secondary circuit in the containment, and whether the pressure in the containment exceeds the alarm limit to judge; the eighth judgment module 8 is used to judge whether the pressure of the secondary circuit outside the containment increases; the ninth judgment module 9 is used to judge whether there is a rupture and leakage in the secondary circuit; the tenth judgment module 10 is used to judge whether there is a rupture in the primary circuit; the first judgment result block 11 indicates the execution of the "Accident Handling Procedures for the Loss of All Power Sources in the Whole Plant"; the second judgment result block 12 indicates the execution of the "Accident Handling Procedures for Power Loss in the Normal Operation Load Section"; the third judgment result block 13 indicates the execution of the "Accident Handling Procedures for the Loss of Cooling Water for Nuclear Island Equipment"; the fourth judgment result block 14, instructing to execute the "Earthquake Accident Regulations"; the fifth judgment result block 15, instructing to execute the "Primary Circuit to Secondary Circuit Leakage Superimposed Steam Breach Accident Regulations"; the sixth judgment result block 16, instructing to execute the "Primary Circuit to Secondary Circuit Leakage Superimposed Steam Breach Accident Regulations"; the seventh judgment result block 17, instructing to execute the "Primary Circuit to Secondary Circuit Leakage Accident Regulations"; the eighth judgment result block 18, instructing to execute the "Secondary Circuit Breach Accident Handling Regulations"; the ninth judgment result block 19, instructing to execute the "Primary Circuit Breach Accident Handling Regulations"; Figure 1 The connection line 20 with an arrow in the figure indicates connection to each module, and the purpose is to establish a friendly human-machine interface to facilitate personnel to understand and judge.

[0065] The function of the judgment module is to determine the type of accident and the technical procedures for accident procedures that need to be executed by setting the judgment logic for key parameters or alarms. There are mainly two types:

[0066] (1) By extracting the analog value in the instrumentation and control system, the limit value is set in the logic, and the logic is triggered when the limit value is exceeded. For example, a certain temperature A is monitored, and the temperature limit is set to 300℃. When the temperature A exceeds 300℃, the logic judgment is to trigger the YES unit. Among them, the YES unit is a judgment logic based on the main instrumentation and control DCS system. The shutdown signal is introduced into this logic judgment. If the shutdown signal from the instrumentation and control system is received, the "yes" logic is triggered, that is, YES. If the shutdown signal is not received, it is not, that is, NO. For example, the judgment condition for the start of the equipment in the instrumentation and control system, if the start condition is met, the start option of the equipment on the screen is green and operable, and if the condition is not met, it is gray and cannot be operated.

[0067] (2) Extract the switch alarm. When there is an alarm, the YES unit is triggered. For example, when the earthquake alarm B is triggered, the YES unit of the logic is triggered.

[0068] The function of the judgment result block is: due to the technical procedure that guides the operator in the main control room to execute a certain accident procedure, such as the "Accident Handling Procedure for Loss of All Power Sources in the Plant", this technical procedure is used to control and stabilize the unit status and mitigate the consequences of the accident when all power sources in the plant are lost. The content of the technical procedure contains specific operating steps and operating purposes.

[0069] like Figure 1 As shown, the present invention provides an instrumentation and control monitoring method for automatic diagnosis and prompting of nuclear power plant accident procedures, comprising:

[0070] According to the initial type of the event, a diagnostic logic is established (a logic for selecting a certain accident procedure. For example, if there is an earthquake signal, it is diagnosed that the accident procedure using earthquake needs to be executed. If there is a low voltage of the electrical busbar, the logic diagnoses that the accident procedure related to power failure needs to be executed). Considering the reasonable logical order, the hierarchical layout judgment is introduced into the corresponding accident procedure. According to the six major levels of power failure, nuclear island equipment cooling water loss, earthquake, leakage from the primary circuit to the secondary circuit, secondary circuit breach, and primary circuit breach, a hierarchical judgment structure is established. The role of step-by-step diagnosis is to use the elimination method to determine the specific cause of the accident and thus derive the accident procedure that needs to be selected. Due to the different causes of various accidents, for example, leakage from the primary circuit may leak to the secondary circuit or to the air. Only when leakage to the secondary circuit is excluded can it be determined that it is leaking to the air. After the judgment is completed, it can be concluded that the accident handling procedure needs to be executed. These six major levels have a certain order. They are judged and eliminated one by one in the order of these six levels. This has the advantage of clear levels and conforms to the logic of accident analysis and judgment.

[0071] A monitoring screen for automatic diagnosis of accident procedures is established, and the alarm information of the diagnosis process is integrated and summarized; personnel can quickly grasp all the information of the accident by viewing the diagnosis monitoring screen, and analyze the cause of the accident based on this information, without having to flip through multiple monitoring screens to obtain this information.

[0072] In the monitoring screen of the accident procedure automatic diagnosis, a tree-like diagnostic flowchart is drawn with clear logic. Three types of logic blocks are set in the diagnostic logic diagram of the instrumentation monitoring screen: judgment module, diagnosis result block and connection line. Each logic block will automatically judge according to the alarm signal and parameters. The diagnosis result module is the display of the accident procedure diagnosis result obtained according to the diagnostic logic. The connection line is the connection line between the judgment modules or between the judgment module and the judgment result module. When the conditions are met, the corresponding module and line will change color, which is convenient for personnel to obtain the diagnosis process.

[0073] Exemplarily, the present invention is divided into six levels according to the type of accident, namely, power failure, nuclear island equipment cooling water loss, earthquake, primary circuit to secondary circuit leakage, secondary circuit breach, and primary circuit breach. The following lists and describes the monitoring methods of the six levels respectively.

[0074] The judgment of power failure accidents includes the following steps:

[0075] Step 1.1: Triggering by a shutdown signal: the first judgment module is triggered by any shutdown signal, the YES unit of the first judgment module is triggered and enters the second judgment module through a connecting line;

[0076] Step 1.2: Determine whether the load section busbar of the factory power supply is de-energized during normal operation through the second judgment module. If de-energized, enter the third judgment module;

[0077] Step 1.3: Use the third judgment module to determine whether the bus voltage of the emergency load section of the power supply to the plant is lost. If so, enter the first judgment result block and instruct to execute the "Accident Handling Procedures for Loss of All Power Sources in the Plant". Otherwise, enter the second judgment result block and instruct to execute the "Accident Handling Procedures for Power Loss in Normal Operation Load Sections" to remind the operator to execute the corresponding accident procedures.

[0078] The judgment of the loss of cooling water accident of nuclear island equipment includes the following steps:

[0079] Step 2.1: Triggering of a shutdown signal: triggering a first judgment module through any shutdown signal;

[0080] Step 2.2: Determine whether the load section busbar of the factory power supply is deenergized during normal operation by the second determination module. If not, enter the fourth determination module.

[0081] Step 2.3: Determine whether the cooling water system of the nuclear island system equipment is lost through the fourth judgment module. If lost, enter the third judgment result block and instruct to execute the "Nuclear Island Equipment Cooling Water Loss Accident Handling Procedures".

[0082] The judgment of earthquake accidents includes the following steps:

[0083] Step 3.1: Triggering a shutdown signal: triggering a first judgment module through any shutdown signal;

[0084] Step 3.2: Determine whether the load section busbar of the factory power supply is deenergized during normal operation through the second judgment module. If not, enter the fourth judgment module;

[0085] Step 3.3: Determine whether the cooling water system of the nuclear island system equipment is lost through the fourth judgment module. If not, enter the fifth judgment module;

[0086] Step 3.4: Determine whether an earthquake has occurred through the fifth judgment module. If an earthquake has occurred, enter the fourth judgment result block to instruct the execution of the "Earthquake Accident Regulations".

[0087] The judgment of leakage accidents from the primary circuit to the secondary circuit includes the following steps:

[0088] Step 4.1: Triggering of a shutdown signal: triggering a first judgment module through any shutdown signal;

[0089] Step 4.2: Determine whether the load section busbar of the factory power supply is deenergized during normal operation through the second judgment module. If not, enter the fourth judgment module;

[0090] Step 4.3: Determine whether the cooling water system of the nuclear island system equipment is lost through the fourth judgment module. If not, enter the fifth judgment module;

[0091] Step 4.4: Determine whether an earthquake has occurred through the fifth determination module, and if not, enter the sixth determination module;

[0092] Step 4.5: The sixth judgment module is used to determine whether the leakage signal from the primary circuit to the secondary circuit is triggered. If triggered, the seventh judgment module is used to determine whether the pressure in the containment increases. If increased, the fifth judgment result block is entered to instruct the execution of the "Procedures for Accidents of Leakage from the Primary Circuit to the Secondary Circuit Superimposed on Steam Breach in the Containment".

[0093] If the pressure inside the containment shell has not increased, the eighth judgment module is used to determine whether the pressure of the secondary circuit outside the containment shell has increased. If the pressure of the secondary circuit outside the containment shell has increased, the sixth judgment result block is entered to instruct the execution of the "Accident Regulations for Leakage from the Primary Circuit to the Secondary Circuit Superimposed on Steam Rupture Outside the Containment Shell". If the pressure of the secondary circuit outside the containment shell has not increased, the seventh judgment result block is entered to instruct the execution of the "Accident Regulations for Leakage from the Primary Circuit to the Secondary Circuit".

[0094] The judgment of secondary circuit breach accidents includes the following steps:

[0095] Step 5.1: Triggering a shutdown signal: triggering a first judgment module through any shutdown signal;

[0096] Step 5.2: Determine whether the load section busbar of the factory power supply is deenergized during normal operation through the second judgment module. If not, enter the fourth judgment module;

[0097] Step 5.3: Determine whether the cooling water system of the nuclear island system equipment is lost through the fourth judgment module. If not, enter the fifth judgment module;

[0098] Step 5.4: Determine whether an earthquake has occurred through the fifth determination module, and if not, enter the sixth determination module;

[0099] Step 5.5: Determine whether the leakage signal from the first circuit to the second circuit is triggered by the sixth judgment module. If not, enter the ninth judgment module;

[0100] Step 5.6: The ninth judgment module is used to judge whether there is a breach and leakage in the secondary circuit. If so, the eighth judgment result block is entered to instruct the execution of the "Second Circuit Breach Accident Handling Procedure".

[0101] The judgment of a circuit rupture accident includes the following steps:

[0102] Step 6.1: Triggering a shutdown signal: triggering a first judgment module through any shutdown signal;

[0103] Step 6.2: Determine whether the load section busbar of the factory power supply is deenergized during normal operation through the second judgment module. If not, enter the fourth judgment module;

[0104] Step 6.3: Determine whether the cooling water system of the nuclear island system equipment is lost through the fourth judgment module. If not, enter the fifth judgment module;

[0105] Step 6.4: Determine whether an earthquake has occurred through the fifth determination module, and if not, enter the sixth determination module;

[0106] Step 6.5: Determine whether the leakage signal from the first circuit to the second circuit is triggered by the sixth judgment module. If not, enter the ninth judgment module;

[0107] Step 6.6: Determine whether there is a rupture or leakage in the secondary circuit through the ninth judgment module. If not, enter the tenth judgment module;

[0108] Step 6.7: Determine whether a circuit has a breach through the tenth judgment module. If so, enter the ninth judgment result block and instruct to execute the "Procedure for Handling a Breach of a Circuit".

[0109] The above is only a specific embodiment of the present invention, but the protection scope of the present invention is not limited thereto. Any changes or substitutions that can be easily thought of by a person skilled in the art within the technical scope disclosed by the present invention should be included in the protection scope of the present invention. Therefore, the protection scope of the present invention should be based on the protection scope of the claims.

Claims

1. An instrumentation and control monitoring method for automatic diagnosis and prompting of nuclear power plant accident procedures, characterized in that: The diagnostic logic is established according to the initial type of event, and the hierarchical layout judgment is introduced into the corresponding accident procedures. The judgment is made step by step according to the power failure type, loss of cooling water for nuclear island equipment, earthquake type, leakage from primary circuit to secondary circuit type, secondary circuit rupture type, and primary circuit rupture type.

2. The instrumentation and control monitoring method for automatic diagnosis and prompting of nuclear power plant accident procedures according to claim 1 is characterized in that: Establish a monitoring screen for automatic diagnosis of accident procedures, and integrate and summarize the alarm information of the diagnosis process.

3. The instrumentation and control monitoring method for automatic diagnosis and prompting of nuclear power plant accident procedures according to claim 1 or 2, characterized in that: The judgment of power failure accidents includes the following steps: Step 1.1: Triggering by a shutdown signal: the first judgment module is triggered by any shutdown signal, the YES unit of the first judgment module is triggered and enters the second judgment module through a connecting line; Step 1.2: Determine whether the load section busbar of the factory power supply is de-energized during normal operation through the second judgment module. If de-energized, enter the third judgment module; Step 1.3: Use the third judgment module to determine whether the bus voltage of the emergency load section of the power supply to the plant is lost. If so, enter the first judgment result block and instruct to execute the accident handling procedures for the loss of all power supplies in the plant. Otherwise, enter the second judgment result block and instruct to execute the accident handling procedures for the power failure of the normal operating load section, and remind the operator to execute the corresponding accident procedures.

4. The instrumentation and control monitoring method for automatic diagnosis and prompting of nuclear power plant accident procedures according to claim 1 or 2, characterized in that: The judgment of the loss of cooling water accident of nuclear island equipment includes the following steps: Step 2.1: Triggering a shutdown signal: triggering a first judgment module through any shutdown signal; Step 2.2: Determine whether the load section busbar of the factory power supply is deenergized during normal operation by the second determination module. If not, enter the fourth determination module. Step 2.3: Determine whether the cooling water system of the nuclear island system equipment is lost through the fourth judgment module. If lost, enter the third judgment result block and instruct to execute the nuclear island equipment cooling water loss accident handling procedures.

5. The instrumentation and control monitoring method for automatic diagnosis and prompting of nuclear power plant accident procedures according to claim 1 or 2, characterized in that: The judgment of the loss of cooling water accident of nuclear island equipment includes the following steps: Step 2.1: Triggering a shutdown signal: triggering a first judgment module through any shutdown signal; Step 2.2: Determine whether the load section busbar of the factory power supply is de-energized during normal operation by the second judgment module. If not, enter the fourth judgment module; Step 2.3: Determine whether the cooling water system of the nuclear island system equipment is lost through the fourth judgment module. If lost, enter the third judgment result block and instruct to execute the nuclear island equipment cooling water loss accident handling procedures.

6. The instrumentation and control monitoring method for automatic diagnosis and prompting of nuclear power plant accident procedures according to claim 1 or 2, characterized in that: The judgment of earthquake accidents includes the following steps: Step 3.1: Triggering a shutdown signal: triggering a first judgment module through any shutdown signal; Step 3.2: Determine whether the load section busbar of the factory power supply is deenergized during normal operation through the second judgment module. If not, enter the fourth judgment module; Step 3.3: Determine whether the cooling water system of the nuclear island system equipment is lost through the fourth judgment module. If not, enter the fifth judgment module; Step 3.4: Determine whether an earthquake has occurred through the fifth judgment module. If an earthquake has occurred, enter the fourth judgment result block to instruct the execution of earthquake accident procedures.

7. The instrumentation and control monitoring method for automatic diagnosis and prompting of nuclear power plant accident procedures according to claim 1 or 2, characterized in that: The judgment of leakage accidents from the primary circuit to the secondary circuit includes the following steps: Step 4.1: Triggering a shutdown signal: triggering a first judgment module through any shutdown signal; Step 4.2: Determine whether the load section busbar of the factory power supply is deenergized during normal operation through the second judgment module. If not, enter the fourth judgment module; Step 4.3: Determine whether the cooling water system of the nuclear island system equipment is lost through the fourth judgment module. If not, enter the fifth judgment module; Step 4.4: Determine whether an earthquake has occurred through the fifth determination module, and if not, enter the sixth determination module; Step 4.5: The sixth judgment module is used to determine whether the leakage signal from the primary circuit to the secondary circuit is triggered. If triggered, the seventh judgment module is used to determine whether the pressure in the containment increases. If increased, the fifth judgment result block is entered to instruct the execution of the accident procedures for the leakage from the primary circuit to the secondary circuit superimposed on the steam breach in the containment.

8. The instrumentation and control monitoring method for automatic diagnosis and prompting of nuclear power plant accident procedures according to claim 7 is characterized in that: If the pressure inside the containment shell does not increase, the eighth judgment module is passed. If the pressure of the secondary circuit outside the containment shell increases, the sixth judgment result block is entered, indicating the execution of the accident procedure of leakage from the first circuit to the second circuit superimposed on the steam rupture outside the containment shell. If the pressure of the secondary circuit outside the containment shell does not increase, the seventh judgment result block is entered, indicating the execution of the accident procedure of leakage from the first circuit to the second circuit.

9. The instrumentation and control monitoring method for automatic diagnosis and prompting of nuclear power plant accident procedures according to claim 1 or 2, characterized in that: The judgment of secondary circuit breach accidents includes the following steps: Step 5.1: Triggering a shutdown signal: triggering a first judgment module through any shutdown signal; Step 5.2: Determine whether the load section busbar of the factory power supply is deenergized during normal operation through the second judgment module. If not, enter the fourth judgment module; Step 5.3: Determine whether the cooling water system of the nuclear island system equipment is lost through the fourth judgment module. If not, enter the fifth judgment module; Step 5.4: Determine whether an earthquake has occurred through the fifth determination module, and if not, enter the sixth determination module; Step 5.5: Determine whether the leakage signal from the first circuit to the second circuit is triggered by the sixth judgment module. If not, enter the ninth judgment module; Step 5.6: If it is determined through the ninth judgment module that a breach and leakage of the secondary circuit occurs, the eighth judgment result block is entered to instruct the execution of the secondary circuit breach accident handling procedure.

10. The instrumentation and control monitoring method for automatic diagnosis and prompting of nuclear power plant accident procedures according to claim 1 or 2, characterized in that: The judgment of a circuit rupture accident includes the following steps: Step 6.1: Triggering a shutdown signal: triggering a first judgment module through any shutdown signal; Step 6.2: Determine whether the load section busbar of the factory power supply is deenergized during normal operation through the second judgment module. If not, enter the fourth judgment module; Step 6.3: Determine whether the cooling water system of the nuclear island system equipment is lost through the fourth judgment module. If not, enter the fifth judgment module; Step 6.4: Determine whether an earthquake has occurred through the fifth determination module, and if not, enter the sixth determination module; Step 6.5: Determine whether the leakage signal from the first circuit to the second circuit is triggered by the sixth judgment module. If not, enter the ninth judgment module; Step 6.6: Determine whether there is a rupture or leakage in the secondary circuit through the ninth judgment module. If not, enter the tenth judgment module; Step 6.7: Determine whether a circuit has a breach through the tenth judgment module. If so, enter the ninth judgment result block to instruct the execution of the circuit breach fault handling procedure.

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