A method, apparatus, device, and medium for protecting a nuclear power plant reactor

Abstract

The application provides a nuclear power plant reactor protection method, device, equipment and medium, and the method comprises the following steps: acquiring water level data in a reactor pressure vessel in real time; issuing a low water level signal when the water level data is lower than a preset low water level; issuing a protection signal according to the low water level signal; and according to the protection signal, a safety injection system supplements a coolant into the reactor pressure vessel, and a letdown isolation function of a chemical and volume control system is started. Through the nuclear power plant reactor protection method, device, equipment and medium provided by the application, the reactor core can be supplemented with water in the case that the reactor protection system fails.

Description

TECHNICAL FIELD

[0001] The present application relates to the field of nuclear power, in particular to a nuclear power plant reactor protection method, device, equipment and medium. BACKGROUND

[0002] In the maintenance cold shutdown state of the nuclear power plant, the reactor is in a special operating condition, the large cover of the reactor pressure vessel is opened, the primary loop cannot be pressurized, and the safety injection system operates in the residual heat removal mode. In this state, the chemical and volume control system may have a sudden large discharge flow. If the discharge flow is too large, the water level in the reactor pressure vessel will gradually decrease. When the water level drops to a threshold value, the reactor protection system should receive a signal and trigger an injection signal to start safety injection to protect the core from being exposed to water loss.

[0003] If the reactor protection system fails, the injection signal will not be sent, the safety injection system will not be started, and the core will not be watered. In this case, the water level will continue to drop, which may cause serious safety hazards. Therefore, there is room for improvement. SUMMARY

[0004] The purpose of the present application is to provide a nuclear power plant reactor protection method, device, equipment and medium, which can water the core in the case of reactor protection system failure.

[0005] To solve the above technical problems, the present application is realized by the following technical scheme:

[0006] The present application provides a nuclear power plant reactor protection method, which is applied to the scene of the maintenance cold shutdown state of the nuclear power plant, the uncontrollable water level drop of the reactor pressure vessel due to the sudden large discharge flow of the chemical and volume control system, and the failure of the reactor protection system. At this time, the safety injection system operates in the residual heat removal mode and continuously removes the heat in the reactor pressure vessel. The protection method comprises:

[0007] Real-time acquisition of water level data in the reactor pressure vessel, and sending a low water level signal when the water level data is lower than a preset low water level;

[0008] According to the low water level signal, a protection signal is sent;

[0009] According to the protection signal, the safety injection system supplements the coolant in the reactor pressure vessel, and starts the discharge isolation function of the chemical and volume control system.

[0010] In an embodiment of the present application, the step of real-time acquisition of water level data in the reactor pressure vessel, and sending a low water level signal when the water level data is lower than a preset low water level comprises:

[0011] Acquire water level data in the reactor pressure vessel in real time, and determine whether the water level data is consistent with a preset low water level:

[0012] When the water level data is lower than or equal to a preset low water level, a low water level signal is issued;

[0013] When the water level data is higher than the preset low water level, no low water level signal is issued.

[0014] In one embodiment of the present invention, after the step of replenishing coolant into the reactor pressure vessel by the safety injection system according to the protection signal and activating the downflow isolation function of the chemical and volume control system, the method further includes:

[0015] Determine the water level data:

[0016] When the water level data is lower than a preset normal water level, the safety injection system replenishes coolant into the reactor pressure vessel and activates the downflow isolation function of the chemical and volume control system; wherein the preset low water level is lower than the preset normal water level;

[0017] When the water level data is higher than or equal to a preset normal water level, a normal signal is issued; based on the normal signal, a water replenishment stop signal is issued; based on the water replenishment stop signal, the safety injection system stops replenishing coolant to the reactor pressure vessel.

[0018] In one embodiment of the present invention, after the step of the safety injection system replenishing coolant into the reactor pressure vessel and starting the downflow isolation function of the chemical and volume control system, the step further includes: when the water level data continues to drop and is lower than or equal to a preset pump-stop water level, sending a pump-stop signal; based on the pump-stop signal, sending a shutdown signal to the safety injection system; the safety injection system shuts down the waste heat discharge pump based on the shutdown signal; wherein the preset pump-stop water level is lower than a preset low water level.

[0019] In one embodiment of the present invention, after the step of shutting down the residual heat removal pump according to the shutdown signal, the step further includes:

[0020] Determine whether the water level data is higher than a preset pump start water level, wherein the preset pump start water level is higher than a preset pump stop water level;

[0021] If the water level is higher than the preset pump start water level, a cooling signal is sent; based on the cooling signal, a start signal is sent to the safety injection system; based on the start signal, the safety injection system starts the waste heat discharge pump;

[0022] Otherwise, continue to shut down the waste heat removal pump.

[0023] In an embodiment of the present application, in the step of supplementing the coolant into the reactor pressure vessel, the safety injection system supplements the coolant into the reactor pressure vessel at a flow rate greater than the flow rate of the coolant discharged by the chemical and volume control system.

[0024] In an embodiment of the present application, the normal water level sensor, the low water level sensor, the pump stop sensor and the pump start sensor are respectively installed at different positions in the reactor pressure vessel.

[0025] The normal water level sensor is configured to send a normal signal when the water level data is higher than a preset normal water level.

[0026] The low water level sensor is configured to send a low water level signal when the water level data is lower than a preset low water level.

[0027] The pump stop sensor is configured to send a pump stop signal when the water level data is lower than a preset pump stop water level.

[0028] The pump start sensor is configured to send a cooling signal when the water level data is higher than a preset pump start water level.

[0029] The present application also provides a protection device for a nuclear power plant reactor, which is applied to a scenario where a nuclear power plant is in a maintenance cold shutdown state, the flow rate of a chemical and volume control system suddenly becomes too large, and a reactor protection system fails, resulting in uncontrollable water level drop of a reactor pressure vessel, and the protection device comprises:

[0030] A judging module is configured to acquire water level data in the reactor pressure vessel in real time, and send a low water level signal when the water level data is lower than a preset low water level.

[0031] A control module is configured to send a protection signal according to the low water level signal.

[0032] A relieving module is configured to supplement the coolant into the reactor pressure vessel by a safety injection system and start a discharge isolation function of the chemical and volume control system according to the protection signal.

[0033] The present application also provides a computer device comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, wherein the processor implements the steps of the protection method for a nuclear power plant reactor when executing the computer program.

[0034] The present application also provides a computer readable storage medium, wherein the computer readable storage medium stores a computer program, and the steps of the protection method for a nuclear power plant reactor are implemented when the computer program is executed by a processor.

[0035] As described above, the present invention provides a method, device, equipment and medium for protecting a nuclear power plant reactor. Through multi-level monitoring and automatic response mechanisms, it ensures that the coolant water level can always be maintained within a safe range, prevents core exposure, ensures that the reactor will not be seriously damaged during an accident, and avoids the potential risk of meltdown caused by core exposure. Through effective water level monitoring and a reasonable pump stop and start control mechanism, cavitation of the residual heat removal pump of the safety injection system is avoided when the water level is too low, ensuring that the residual heat removal pump can operate under appropriate water level conditions, not only protecting the residual heat removal pump, but also ensuring that the residual heat of the core can be continuously discharged, maintaining the reactor in a safe state after the accident. Through multiple signal settings, automatic control and linkage mechanisms are realized. This enables the system to respond quickly during an accident, avoids delays in manual operation, and greatly improves the efficiency of accident response and the safety of the system.

[0036] Of course, any product implementing the present invention does not necessarily need to achieve all of the advantages described above at the same time. BRIEF DESCRIPTION OF THE DRAWINGS

[0037] In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the following briefly introduces the drawings required for describing the embodiments. Obviously, the drawings described below are only some embodiments of the present invention. For ordinary technicians in this field, other drawings can be obtained based on these drawings without creative work.

[0038] Figure 1 This is a flow chart of a method for protecting a nuclear power plant reactor according to one embodiment of the present invention;

[0039] Figure 2 Schematic diagram of a protection device for a nuclear power plant reactor according to one embodiment of the present invention;

[0040] Figure 3 FIG. 1 is a schematic diagram of an electronic device according to an embodiment of the present invention.

[0041] In the figure: 100, judgment module; 200, control module; 300, mitigation module; 1, electronic device; 12, memory; 13, processor. DETAILED DESCRIPTION

[0042] The following will clearly and completely describe the technical solutions in the embodiments of the present invention in conjunction with the accompanying drawings. Obviously, the described embodiments are only part of the embodiments of the present invention, not all of the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without making any creative efforts shall fall within the scope of protection of the present invention.

[0043] The application provides a protection method for a nuclear power plant reactor. The protection method can be applied to the scenario that the nuclear power plant is in a maintenance cold shutdown state, the water level in the reactor pressure vessel suddenly drops uncontrollably due to excessive discharge flow of the chemical and volume control system, and the reactor protection system fails. At this time, the safety injection system is running in a residual heat removal mode, and the heat in the reactor pressure vessel is continuously discharged.

[0044] In one embodiment, the maintenance cold shutdown state of the nuclear power plant refers to a shutdown mode of the nuclear power plant, in which the reactor core has stopped running and the coolant system is cooled to a lower temperature. In this state, the large cover of the reactor pressure vessel (RCP) is open, and the primary circuit cannot be pressurized. When the reactor core in the reactor pressure vessel enters the cold shutdown operation state, the fuel in the core will still generate heat due to radioactive decay even if the nuclear fission reaction is no longer carried out. If not discharged in time, the core temperature may still rise. At this time, the safety injection system is running in a residual heat removal mode (RHR). The residual heat removal mode can continuously remove the residual heat generated by the core through the circulation of the coolant to cool the reactor state in the reactor pressure vessel and prevent the temperature from rising again.

[0045] In one embodiment, the excessive discharge flow of the chemical and volume control system (RCV) refers to the fact that in some cases, the chemical and volume control system can cause excessive discharge of the coolant (i.e., the coolant is discharged from the system through the pipeline or valve), and the water level drops rapidly. Possible reasons include operator error, water level control failure, low-pressure relief valve failure, etc. Among them, operator error refers to the error in the operation of the operator in managing the 3 / 4 loop (water level at the middle plane) and manually emptying the primary circuit, which can cause a large amount of coolant to be discharged. Water level control failure refers to the problem of the water level control system of the reactor pressure vessel, which causes the water level to be unable to remain within the set safety range, and a large amount of coolant is discharged through the discharge line of the chemical and volume control system. Low-pressure relief valve failure refers to the failure of the low-pressure relief valve in the chemical and volume control system, which cannot correctly control the coolant flow, resulting in a significant increase in the discharge flow.

[0046] In one embodiment, the failure of the reactor protection system (RPS) can be caused by multiple factors, which can include: sensor (such as temperature, pressure, water level) failure, electronic component (such as circuit board, relay, processor, etc.) failure, power supply interruption or failure, communication failure, operator error and improper maintenance or program setting error, environmental factors (such as high temperature, humidity, strong electromagnetic interference or natural disasters, etc.), hardware wear and aging failure. After the failure of the reactor protection system, the water level of the coolant in the reactor pressure vessel cannot be replenished in time, and will continue to decrease. When the water level decreases to a dangerous level, the core may be exposed, which will cause the temperature of the core to rise.

[0047] In one embodiment, in the case of failure of the reactor protection system, if the chemical and volume control system is abnormal (such as sudden excessive leakage flow), the water level of the coolant in the reactor pressure vessel will decrease rapidly. This situation can be caused by the fact that the coolant is lost too quickly, far exceeding the system's ability to replenish water or the operator's intervention ability. Due to the failure of the reactor protection system, the system cannot automatically trigger the water replenishment safety mechanism, further exacerbating the trend of water level decrease.

[0048] Please refer to Figure 1 In one embodiment, in the above-mentioned case, it can cause uncontrolled water level decrease of the reactor pressure vessel to superimpose the failure of the reactor protection system. The case refers to the simultaneous or continuous occurrence of multiple factors, which causes the water level in the reactor pressure vessel to continuously decrease, and this trend of water level decrease cannot be controlled or alleviated by conventional means. These factors can include: failure of the reactor protection system (cannot automatically start the water replenishment mechanism), excessive leakage flow of the chemical and volume control system (a large amount of coolant is discharged from the reactor loop), operator operation error or system equipment failure. When these factors superimpose, the speed and amplitude of water level decrease exceed the normal control range, so that the water level decreases uncontrollably. This situation is very dangerous, and continuous decrease of the water level can cause the core to be exposed, and eventually damage the core. The protection method in this embodiment can be applied in the case of superimposition of uncontrolled water level decrease of the reactor pressure vessel, and the protection method can include the following steps:

[0049] Step S10, real-time acquisition of water level data in the reactor pressure vessel, and sending a low water level signal when the water level data is lower than a preset low water level;

[0050] Step S20, sending a protection signal according to the low water level signal;

[0051] Step S30, according to the protection signal, the safety injection system supplements the coolant into the reactor pressure vessel, and starts the blowdown isolation function of the chemical and volume control system; wherein the flow of the safety injection system supplementing the coolant into the reactor pressure vessel is greater than the blowdown flow of the coolant of the chemical and volume control system;

[0052] Step S40, judging the water level data:

[0053] Step S50, when the water level data is lower than the preset normal water level, the safety injection system supplements the coolant into the reactor pressure vessel, and starts the blowdown isolation function of the chemical and volume control system;

[0054] Step S60, when the water level data is higher than or equal to the preset normal water level, a normal signal is sent; according to the normal signal, a stop water supplement signal is sent; according to the stop water supplement signal, the safety injection system stops supplementing the coolant into the reactor pressure vessel; wherein the preset normal water level is higher than the preset low water level;

[0055] Step S70, when the water level data is lower than or equal to the preset pump stop water level, a pump stop signal is sent; according to the pump stop signal, a closing signal is sent to the safety injection system; according to the closing signal, the safety injection system closes the residual heat removal pump; wherein the preset pump stop water level is lower than the preset low water level;

[0056] Step S80, judging whether the water level data is higher than the preset pump start water level, wherein the preset pump start water level is higher than the preset pump stop water level; if higher than the preset pump start water level, a cooling signal is sent; according to the cooling signal, a starting signal is sent to the safety injection system; according to the starting signal, the safety injection system starts the residual heat removal pump; otherwise, the residual heat removal pump is kept closed.

[0057] In one embodiment, when step S10 is performed, specifically, step S10 can include the following steps:

[0058] Step S11, real-time acquiring the water level data in the reactor pressure vessel, and judging the water level data and the preset low water level:

[0059] Step S12, when the water level data is lower than or equal to the preset low water level, a low water level signal is sent; when the water level data is higher than the preset low water level, no low water level signal is sent.

[0060] In one embodiment, when step S11 is performed, specifically, a plurality of water level sensors can be installed in the reactor pressure vessel, which are used to monitor the coolant water level at different positions, to ensure that the reactor pressure vessel maintains safe and normal operation in different operating states. In this embodiment, the water level sensors can at least include a normal water level sensor, a low water level sensor, a pump stop sensor and a pump start sensor.

[0061] In one embodiment, a normal water level sensor can be installed at a preset normal water level position to monitor whether the coolant water level is within a normal range. When the coolant water level data is higher than the preset normal water level, the sensor will send a normal signal, indicating that the water level is within a safe and normal range.

[0062] In one embodiment, a low water level sensor can be installed at a preset low water level location to detect whether the coolant water level is below a safety threshold. When the coolant water level drops below the preset low water level, the sensor will issue a low water level signal. The preset low water level is lower than the preset normal water level.

[0063] In one embodiment, a pump stop sensor can be installed at the location of a preset pump stop water level to monitor whether the water level has reached a critical value requiring an emergency pump stop. When the coolant water level data further drops below the preset pump stop water level, the pump stop sensor will send a pump stop signal. The preset pump stop water level is the lowest water level line, indicating that the water level has dropped to a very dangerous level and requires immediate pump stop protection. The preset pump stop water level needs to be higher than the top of the active section of the core to avoid core exposure. The preset pump stop water level is lower than the preset low water level.

[0064] In one embodiment, a pump start sensor can be installed at a preset pump start level to detect whether the coolant level is above a critical value for activating the residual heat removal pump. When the residual heat removal pump is deactivated, the coolant level within the reactor pressure vessel gradually rises. When the coolant level reaches the preset pump start level, a cooling signal can be issued to restart the residual heat removal pump. The preset pump start level is higher than the preset pump stop level.

[0065] In one embodiment, when executing step S12, specifically, if the chemical and volumetric control system experiences an increase in downstream flow (the amount of coolant discharged exceeds a normal range), coolant may be discharged or leaked from the primary circuit, causing the primary circuit water level to drop uncontrollably. In this case, the coolant level data within the reactor pressure vessel may continue to drop. When the coolant level drops to a preset low water level, the low water level sensor detects this and sends a low water level signal.

[0066] In one embodiment, when step S20 is executed, specifically, the Diverse Actuation System (KDS) is a redundant protection system that provides additional safety protection for the nuclear reactor. The Diversity Actuation System and the Reactor Protection System are independent of each other. When the reactor protection system fails, the Diversity Actuation System can serve as an additional safety line to protect the safe operation of the reactor. The Diversity Actuation System can receive various signals from the water level sensor in the reactor pressure vessel to control the operation of the chemical and volume control system, the safety injection system, etc., and replenish the coolant in the reactor pressure vessel in a timely manner. When the Diversity Actuation System receives a low water level signal from the low water level sensor, it will process the signal and send a protection signal according to the preset logic.

[0067] In one embodiment, when executing step S30, the diversity drive system may send a protection signal to the chemical and volumetric control system. Based on the protection signal, the chemical and volumetric control system may activate a downlink isolation function to close or isolate the path leading to coolant loss, thereby preventing further drops in the water level data. Specifically, the downlink isolation function involves the chemical and volumetric control system preventing further coolant loss by closing or isolating relevant valves (e.g., isolation valves, check valves) and pipelines.

[0068] In one embodiment, the diversity drive system can send a protection signal to the safety injection system. Upon receiving the protection signal, the safety injection system activates and replenishes coolant into the reactor pressure vessel to prevent overheating and possible damage to the reactor core. Furthermore, the flow rate of coolant replenished by the safety injection system must be greater than the coolant flow rate released by the chemical and volumetric control systems. This ensures that the replenished coolant flow rate is sufficient to compensate for losses caused by leaks from the chemical and volumetric control systems, while also providing sufficient margin to restore and maintain the coolant level within a safe range.

[0069] In one embodiment, the diversity drive system may send a protection signal only to the chemical and volume control system or the safety injection system, thereby enabling the chemical and volume control system or the safety injection system to operate independently. Alternatively, the diversity drive system may send a protection signal simultaneously to the chemical and volume control system and the safety injection system, thereby enabling the chemical and volume control system or the safety injection system to operate simultaneously. The specific control method is not limited and can be set according to actual needs.

[0070] In one embodiment, when executing step S40, specifically, after receiving the protection signal, it takes a certain amount of time, i.e., a preset duration, for the chemical and volume control system to start and complete the downflow isolation function. It also takes a certain amount of time for the safety injection system to start the process and replenish the coolant to the reactor pressure vessel. Before the chemical and volume control system and the safety injection system start and take full effect, the water level data of the coolant water level in the reactor pressure vessel may continue to drop. During the process of the water level data dropping, the waste heat removal pump of the safety injection system needs to continue to work to continuously extract the waste heat of the core. When the water level data drops to the preset pump stop water level, there may be a risk of cavitation in the waste heat removal pump. Cavitation risk refers to the phenomenon that bubbles are generated when the coolant is under high temperature and high pressure conditions due to the local pressure dropping below the saturated vapor pressure of the liquid. When the bubbles burst in the high-pressure area, they will cause impact and erosion on the pump blades and other components, resulting in mechanical damage and reduced efficiency. Therefore, it is necessary to continue to judge the water level data to prevent problems with the waste heat removal pump.

[0071] In one embodiment, when executing step S50, specifically, before the chemical and volumetric control system and the safety injection system are activated and fully effective, the water level data of the reactor pressure vessel may continue to drop. If the water level data falls below the preset normal water level, it can be considered that although the chemical and volumetric control system and the safety injection system are being activated, the water level data of the reactor pressure vessel has not yet risen above the preset normal water level. At this time, the chemical and volumetric control system and the safety injection system need to continue operating. In other words, the safety injection system replenishes coolant into the reactor pressure vessel, and the downflow line of the chemical and volumetric control system remains isolated.

[0072] In one embodiment, when executing step S60, specifically, after the chemical and volume control system and the safety injection system are activated and fully effective, the water level data of the reactor pressure vessel will gradually increase. When the water level data in the reactor pressure vessel exceeds the preset normal water level, the normal water level sensor can issue a normal signal. After receiving the normal signal, the diversity drive system can issue a stop water replenishment signal. After receiving the stop water replenishment signal, the safety injection system can stop replenishing coolant into the reactor pressure vessel.

[0073] In one embodiment, when executing step S70, specifically, before the chemical and volume control system and the safety injection system are activated and fully effective, the water level data of the reactor pressure vessel may drop to a preset pump-off level. At this time, the residual heat removal pump may be at risk. Therefore, when the pump-off sensor detects that the water level data is lower than or equal to the preset pump-off level, a pump-off signal may be issued. After receiving the pump-off signal, the diversity drive system may send a shutdown signal to the safety injection system. After receiving the shutdown signal, the safety injection system may shut down the residual heat removal pump to prevent further mechanical damage.

[0074] In one embodiment, when step S80 is performed, specifically, after the safety injection system turns off the residual heat removal pump, at this time, the chemical and volume control system and the safety injection system are started and fully effective, and the water level data of the reactor pressure vessel gradually rises. At this time, it can be judged whether the water level data is higher than the preset pump starting water level, to determine whether the residual heat removal pump needs to be restarted.

[0075] In one embodiment, when the water level data is lower than or equal to the preset pump starting water level, the residual heat removal pump needs to be continued to be turned off. When the water level data is higher than the preset pump starting water level, that is, after the pump starting sensor detects the water level data, a cooling signal can be sent. After the diversity driving system receives the cooling signal, a starting signal can be sent to the safety injection system. After the safety injection system receives the starting signal, the residual heat removal pump can be restarted to cool the reactor pressure vessel.

[0076] It should be understood that the size of the serial number of each step in the above embodiment does not mean the order of execution, and the execution order of each process should be determined according to its function and internal logic, and should not constitute any limitation on the implementation process of the embodiment of the present application.

[0077] It can be seen that in the above scheme, through the multi-level monitoring and automatic response mechanism, it is ensured that the coolant water level can always be kept within a safe range, the core is prevented from being exposed, and the reactor is ensured not to be severely damaged during an accident, and the potential risk of core melt caused by core exposure is avoided. Through effective water level monitoring and reasonable pump stop-start control mechanism, the residual heat removal pump of the safety injection system is prevented from cavitation when the water level is too low, and it is ensured that the residual heat removal pump can work under appropriate water level conditions, not only protecting the residual heat removal pump, but also ensuring that the residual heat of the core can be continuously discharged, maintaining the safety state of the reactor after the accident. Through multiple signal settings, an automatic control and linkage mechanism is realized. The system can quickly respond during an accident, avoiding the delay of manual operation, greatly improving the efficiency of accident response and the safety of the system.

[0078] Please refer to Figure 2 The present application also provides a protection device for a nuclear power plant reactor, which can be applied to a scene where the reactor pressure vessel has an uncontrollable water level drop under the condition that the nuclear power plant is in a maintenance cold shutdown state, the leakage flow of the chemical and volume control system is suddenly too large, and the reactor protection system fails. The above protection method can be applied to the protection device. The protection device can include a judgment module 100, a control module 200, and a relief module 300.

[0079] In one embodiment, the judgment module 100 can be used to acquire water level data in the reactor pressure vessel in real time, and send a low water level signal when the water level data is lower than a preset low water level.

[0080] In one embodiment, the control module 200 can be configured to send a protection signal according to the low water level signal.

[0081] In one embodiment, the mitigation module 300 can be configured to safely inject the system with coolant into the reactor pressure vessel according to the protection signal, and to initiate the letdown isolation function of the chemical and volume control system.

[0082] Referring to Figure 3 In one embodiment, the electronic device 1 can include a memory 12, a processor 13, and a bus, and can further include a computer program, such as a protection program for a nuclear power plant reactor, stored in the memory 12 and executable on the processor 13.

[0083] In one embodiment, the memory 12 includes at least one type of readable storage medium, such as a flash memory, a mobile hard disk, a multimedia card, a card-type memory (e.g., an SD or DX memory, etc.), a magnetic memory, a disk, an optical disk, etc. The memory 12 can be an internal storage unit of the electronic device 1 in some embodiments, such as a mobile hard disk of the electronic device 1. The memory 12 can also be an external storage device of the electronic device 1 in other embodiments, such as a plug-in mobile hard disk, a smart media card (SMC), a secure digital (SD) card, a flash card, etc. Further, the memory 12 can include both an internal storage unit and an external storage device of the electronic device 1. The memory 12 can be used to store application software and various data installed in the electronic device 1, such as a code for protection of a nuclear power plant reactor, and can also be used to temporarily store data that has been output or will be output.

[0084] In one embodiment, the processor 13 can be composed of an integrated circuit in some embodiments, such as a single packaged integrated circuit, or a plurality of packaged integrated circuits with the same or different functions, including one or more central processing units (CPUs), microprocessors, digital processing chips, graphics processors, combinations of various control chips, etc. The processor 13 is a control unit of the electronic device 1, and is connected to various components of the electronic device 1 using various interfaces and lines, and executes or runs programs or modules stored in the memory 12 (such as a correction program for the capacity of a power battery, etc.), and calls data stored in the memory 12, to perform various functions of the electronic device 1 and process data.

[0085] In one embodiment, the processor 13 executes the operating system and various installed application programs of the electronic device 1. The processor 13 executes the application programs to implement the steps in the above-mentioned method for protecting a nuclear power plant reactor.

[0086] In one embodiment, the computer program may be divided into one or more modules, one or more of which are stored in the memory 12 and executed by the processor 13 to complete the present application. The one or more modules may be a series of computer program instruction segments capable of performing specific functions, and the instruction segments are used to describe the execution process of the computer program in the electronic device 1.

[0087] In one embodiment, the integrated unit implemented in the form of a software functional module can be stored in a computer-readable storage medium, which can be either non-volatile or volatile. The software functional module is stored in a storage medium and includes a number of instructions for causing a computer device (which can be a personal computer, computer equipment, or network equipment, etc.) or a processor to perform part of the functions of the nuclear power plant reactor protection method of each embodiment of the present application.

[0088] The embodiments of the present invention disclosed above are intended only to illustrate the present invention. They do not describe all details in detail, nor do they limit the present invention to the specific embodiments described. Obviously, many modifications and variations are possible based on the content of this specification. These embodiments are selected and described in detail in this specification to better explain the principles and practical applications of the present invention, thereby enabling those skilled in the art to better understand and utilize the present invention. The present invention is limited only by the claims and their full scope and equivalents.

Claims

1. A method for protecting a nuclear power plant reactor, characterized in that: The invention is applied to a scenario where a nuclear power plant is in a cold shutdown state for maintenance, the reactor pressure vessel experiences an uncontrollable drop in water level due to a sudden excessive discharge flow from the chemical and volume control system, and the reactor protection system fails. In this case, the safety injection system operates in a residual heat removal mode to continuously remove heat from the reactor pressure vessel. The diversity drive system receives various signals from the water level sensor in the reactor pressure vessel to control the operation of the chemical and volume control system and the safety injection system. The protection method includes: acquiring water level data in the reactor pressure vessel in real time, and issuing a low water level signal when the water level data is lower than a preset low water level; issuing a protection signal according to the low water level signal; According to the protection signal, the safety injection system replenishes coolant into the reactor pressure vessel and activates the downflow isolation function of the chemical and volume control system; Determine the water level data: When the water level data is lower than a preset normal water level, the safety injection system replenishes coolant into the reactor pressure vessel and activates the downflow isolation function of the chemical and volume control system; when the water level data continues to drop and is lower than or equal to a preset pump-stop water level, a pump-stop signal is issued; based on the pump-stop signal, a shutdown signal is issued to the safety injection system; the safety injection system shuts down the waste heat removal pump based on the shutdown signal; wherein the preset pump-stop water level is lower than a preset low water level; wherein the preset low water level is lower than a preset normal water level; When the water level data is higher than or equal to a preset normal water level, a normal signal is issued; based on the normal signal, a water replenishment stop signal is issued; based on the water replenishment stop signal, the safety injection system stops replenishing coolant to the reactor pressure vessel.

2. The method for protecting a nuclear power plant reactor according to claim 1, characterized in that: The step of acquiring water level data in the reactor pressure vessel in real time and issuing a low water level signal when the water level data is lower than a preset low water level comprises: Acquire water level data in the reactor pressure vessel in real time, and determine whether the water level data is consistent with a preset low water level: When the water level data is lower than or equal to a preset low water level, a low water level signal is issued; When the water level data is higher than the preset low water level, no low water level signal is issued.

3. The method for protecting a nuclear power plant reactor according to claim 1, wherein: After the step of shutting down the residual heat removal pump according to the shutdown signal by the safety injection system, the method further includes: Determine whether the water level data is higher than a preset pump start water level, wherein the preset pump start water level is higher than a preset pump stop water level; If the water level is higher than the preset pump start water level, a cooling signal is sent; based on the cooling signal, a start signal is sent to the safety injection system; based on the start signal, the safety injection system starts the waste heat discharge pump; Otherwise, continue to shut down the waste heat removal pump.

4. The method for protecting a nuclear power plant reactor according to claim 1, wherein: In the step of replenishing coolant into the reactor pressure vessel, the flow rate of the coolant replenished into the reactor pressure vessel by the safety injection system is greater than the coolant leakage flow rate of the chemical and volume control system.

5. The method for protecting a nuclear power plant reactor according to claim 1, wherein: A normal water level sensor, a low water level sensor, a pump stop sensor, and a pump start sensor are installed at different positions in the reactor pressure vessel respectively; The normal water level sensor is used to send a normal signal when the water level data is higher than the preset normal water level; The low water level sensor is used to send a low water level signal when the water level data is lower than a preset low water level; The pump stop sensor is used to send a pump stop signal when the water level data is lower than the preset pump stop water level; The pump start sensor is used to send a cooling signal when the water level data is higher than a preset pump start water level.

6. A protection device for a nuclear power plant reactor, characterized in that: The protection method for a nuclear power plant reactor according to any one of claims 1 to 5 is applied, wherein the protection device comprises: a judgment module, configured to obtain water level data in the reactor pressure vessel in real time, and to issue a low water level signal when the water level data is lower than a preset low water level; a control module, configured to send a protection signal according to the low water level signal; and The mitigation module is configured to, based on the protection signal, enable a safety injection system to replenish coolant into the reactor pressure vessel and activate a downflow isolation function of the chemical and volume control system.

7. A computer device comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, wherein: When the processor executes the computer program, the steps of the method for protecting a nuclear power plant reactor according to any one of claims 1 to 5 are implemented.

8. A computer-readable storage medium storing a computer program, characterized in that: When the computer program is executed by a processor, the steps of the method for protecting a nuclear power plant reactor according to any one of claims 1 to 5 are implemented.

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