Method, device and equipment for protecting nuclear power plant reactor and medium

Abstract

The invention provides a protection method, device, equipment and medium for a nuclear power plant reactor, and the method comprises the following steps: obtaining water level data in a reactor pressure vessel in real time, and sending a low water level signal when the water level data is lower than a preset low water level; a protection signal is sent out according to the low water level signal; based on the protection signal, a safety injection system supplements coolant into the reactor pressure vessel and initiates a blowdown isolation function of the chemical and volume control system. By means of the protection method, device and equipment for the nuclear power plant reactor and the medium, water can be supplemented to the reactor core under the condition that a reactor protection system fails.

Description

Technical Field

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

[0002] When a nuclear power plant is in a cold shutdown state for maintenance, the reactor is in a special operating condition. The large cover of the reactor pressure vessel is opened, resulting in the inability to pressurize the primary circuit. The safety injection system operates in the residual heat removal mode. In this state, the chemical and volume control system may experience a sudden excessive discharge flow. If the discharge flow is too large, the water level in the reactor pressure vessel will gradually drop. When the water level drops to the threshold, the reactor protection system should receive a signal and trigger a safety injection signal to start the safety injection to protect the core from water loss and exposure.

[0003] If the reactor protection system fails, no injection signal will be issued, resulting in the inability to start the safety injection system and replenish water to the core. In this case, the water level will continue to drop, which may cause serious safety hazards. Therefore, there is room for improvement. Summary of the invention

[0004] The object of the present invention is to provide a protection method, device, equipment and medium for a nuclear power plant reactor, which can replenish water to the core when the reactor protection system fails.

[0005] To solve the above technical problems, the present invention is achieved through the following technical solutions:

[0006] The present invention provides a protection method for a nuclear power plant reactor, which is applied to a nuclear power plant maintenance cold shutdown state, a reactor pressure vessel has an uncontrollable water level drop due to a sudden excessive discharge flow of a chemical and volume control system, and a reactor protection system fails. At this time, the safety injection system operates in a residual heat removal mode to continuously remove heat from the reactor pressure vessel. The protection method includes:

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

[0008] Sending a protection signal according to the low water level signal;

[0009] According to the protection signal, the safety injection system replenishes coolant into the reactor pressure vessel and activates the leakage isolation function of the chemical and volume control system.

[0010] In one embodiment of the present invention, the step of acquiring the water level data in the reactor pressure vessel in real time 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 starting the leakage 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 starts the leakage 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 stop water replenishment signal is issued; based on the stop water replenishment 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, it also 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; according to the pump-stop signal, sending a shutdown signal to the safety injection system; the safety injection system shuts down the waste heat discharge pump according to 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 by the safety injection system, the method 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 it is higher than the preset pump start water level, a cooling signal is sent; according to the cooling signal, a start signal is sent to the safety injection system; according to 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 one embodiment of the present invention, 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 downstream flow rate of the coolant of the chemical and volume control system.

[0024] In one embodiment of the present invention, 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;

[0025] 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;

[0026] 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;

[0027] 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;

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

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

[0030] A judgment module, used for obtaining water level data in the reactor pressure vessel in real time, and sending a low water level signal when the water level data is lower than a preset low water level;

[0031] A control module, configured to send a protection signal according to the low water level signal; and

[0032] The mitigation module is used for replenishing coolant into the reactor pressure vessel through a safe injection system according to the protection signal, and starting the leakage isolation function of the chemical and volume control system.

[0033] The present invention also provides a computer device, including a memory, a processor, and a computer program stored in the memory and executable on the processor, and the steps of the method for protecting a nuclear power plant reactor are implemented when the processor executes the computer program.

[0034] The present invention also provides a computer-readable storage medium, which 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 protection method, device, equipment and medium for a nuclear power plant reactor. Through multi-level monitoring and automatic response mechanisms, it is ensured that the coolant water level can always be maintained within a safe range, the core is prevented from being exposed, and the reactor is ensured not to be seriously damaged during an accident, thereby avoiding 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 when the water level is too low is avoided, ensuring that the residual heat removal pump can work under appropriate water level conditions, which not only protects the residual heat removal pump, but also ensures 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 operations, 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 accompanying drawings required for describing the embodiments will be briefly introduced below. Obviously, the accompanying drawings described below are only some embodiments of the present invention. For ordinary technicians in this field, other accompanying drawings can be obtained based on these accompanying drawings without paying creative work.

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

[0039] Figure 2 A schematic diagram of a protection device for a nuclear power plant reactor in one embodiment of the present invention;

[0040] Figure 3 FIG. 4 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 be combined with the drawings in the embodiments of the present invention to clearly and completely describe the technical solutions in the embodiments of the present invention. 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 creative work are within the scope of protection of the present invention.

[0043] The present invention provides a protection method for a nuclear power plant reactor. The protection method can be applied to a nuclear power plant maintenance cold shutdown state, a reactor pressure vessel uncontrollably drops in water level due to a sudden excessive discharge flow of a chemical and volume control system, and a reactor protection system failure. At this time, the safety injection system operates in a residual heat removal mode to continuously remove heat from the reactor pressure vessel.

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

[0045] In one embodiment, the chemical and volume control system (RCV) discharge flow is suddenly too large, which means that in some cases, the chemical and volume control system 300 may cause excessive coolant discharge (i.e., the coolant is discharged from the system through pipes or valves), and the water level drops rapidly. Possible reasons include: operator error, water level control failure, low-pressure pressure relief valve failure, etc. Among them, operator error refers to the operator's error in manually emptying a loop when managing the 3 / 4 loop (the water level is in the middle plane), which may cause a large amount of coolant to be discharged. Water level control failure refers to a problem with the water level control system of the reactor pressure vessel, resulting in the water level being unable to be maintained within the set safety range, and the coolant is discharged in large quantities through the discharge pipeline of the chemical and volume control system. Failure of the low-pressure pressure relief valve refers to the failure of the low-pressure pressure relief valve in the chemical and volume control system, which cannot properly 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) may be caused by multiple factors, which may 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, failure caused by environmental factors (such as excessive 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 drop. When the water level drops to a dangerous level, the core may be exposed, which will cause the core temperature to rise.

[0047] In one embodiment, in the event of a reactor protection system failure, if the chemical and volume control system is abnormal (e.g., the leakage flow is suddenly too large), the coolant level in the reactor pressure vessel will drop rapidly. This may be because the coolant loss rate is too fast, far exceeding the system's water replenishment capacity or the operator's intervention capacity. Due to the failure of the reactor protection system, the system cannot automatically trigger the water replenishment safety mechanism, further exacerbating the downward trend of the water level.

[0048] See also Figure 1 In one embodiment, under the above circumstances, the reactor pressure vessel may experience an uncontrollable drop in water level, superimposed with a safety failure caused by a failure of the reactor protection system. In this case, multiple factors occur simultaneously or continuously, causing the water level in the reactor pressure vessel to continue to drop, and this trend of water level drop cannot be controlled or alleviated by conventional means. These factors may include: failure of the reactor protection system (failure to automatically start the water replenishment mechanism), excessive discharge flow of the chemical and volume control system (a large amount of coolant is discharged from the reactor circuit), operator error or system equipment failure. When these factors occur in combination, the speed and amplitude of the water level drop exceed the normal control range, causing the water level to drop uncontrollably. This situation is very dangerous, and the continuous drop in water level may cause the core to be exposed and eventually damage the core. The protection method in this embodiment can be applied to the scenario where an uncontrollable drop in water level occurs in the reactor pressure vessel, and the protection method may include the following steps:

[0049] Step S10, acquiring water level data in the reactor pressure vessel in real time, 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 replenishes coolant into the reactor pressure vessel and starts the leakage isolation function of the chemical and volume control system; wherein the flow rate of the coolant replenished into the reactor pressure vessel by the safety injection system is greater than the leakage flow rate of the coolant of the chemical and volume control system;

[0052] Step S40, judging water level data:

[0053] Step S50: When the water level data is lower than the preset normal water level, the safety injection system replenishes coolant into the reactor pressure vessel and starts the leakage 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 issued; according to the normal signal, a stop water replenishment signal is issued; according to the stop water replenishment signal, the safety injection system stops replenishing coolant to 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 issued; according to the pump-stop signal, a shutdown signal is issued to the safety injection system; according to the shutdown signal, the safety injection system shuts down the waste heat discharge pump; wherein the preset pump-stop water level is lower than the preset low water level;

[0056] Step S80, determine 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 it is higher than the preset pump start water level, send a cooling signal; based on the cooling signal, send a start signal 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 discharge pump.

[0057] In one embodiment, when executing step S10, specifically, step S10 may include the following steps:

[0058] Step S11, obtaining water level data in the reactor pressure vessel in real time, 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 issued; when the water level data is higher than the preset low water level, no low water level signal is issued.

[0060] In one embodiment, when executing step S11, specifically, a plurality of water level sensors may be installed in the reactor pressure vessel 100, and these water level sensors are used to monitor the coolant water level at different positions to ensure that the reactor pressure vessel maintains safety and normal operation under different operating conditions. In this embodiment, the water level sensor may include at least a normal water level sensor, a low water level sensor, a pump stop sensor, and a pump start sensor.

[0061] In one embodiment, the normal water level sensor can be installed at the position of the preset normal water level to monitor whether the coolant water level is within the normal range. When the water level data of the coolant water level 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 position to detect whether the coolant water level is lower than a safety critical value. When the water level data of the coolant water level drops below the preset low water level, the sensor will send 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 that requires an emergency pump stop. When the water level data of the coolant water level 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 core active section to avoid core exposure. Among them, 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 water level position to detect whether the coolant water level is higher than a critical value for starting the residual heat removal pump. When the residual heat removal pump is stopped, the coolant water level in the reactor pressure vessel will gradually rise. When the coolant water level data reaches the preset pump start water level, a cooling signal can be issued to restart the residual heat removal pump. The preset pump start water level is higher than the preset pump stop water level.

[0065] In one embodiment, when executing step S12, specifically, when the chemical and volume control system has an increased discharge flow (the amount of discharged coolant exceeds the normal range), the coolant will be discharged or leaked from the primary circuit, causing the primary circuit water level to drop uncontrollably, at this time, the coolant water level data in the reactor pressure vessel will continue to drop. When the coolant water level drops to a preset low water level, the low water level sensor detects this situation and sends a low water level signal.

[0066] In one embodiment, when executing step S20, 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 time. 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, specifically, the diversity drive system can send a protection signal to the chemical and volume control system. The chemical and volume control system can start the leakage isolation function according to the protection signal to close or isolate the path that causes the coolant loss to prevent the water level data from further decreasing. Specifically, the leakage isolation function refers to the chemical and volume control system preventing further coolant loss by closing or isolating related valves (such as isolation valves, check valves) and pipelines.

[0068] In one embodiment, the diversity drive system can send a protection signal to the safety injection system. When the safety injection system receives the protection signal, it will start and add coolant to the reactor pressure vessel to prevent overheating and possible damage to the reactor core. At the same time, the flow rate of the coolant added by the safety injection system must be greater than the coolant flow rate discharged from the chemical and volume control system. This ensures that the supplementary coolant flow rate is sufficient to compensate for the loss caused by the discharge of the chemical and volume control system, and there is enough margin to restore and maintain the water level data of 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, so that the chemical and volume control system or the safety injection system works alone. The diversity drive system may also send a protection signal to both the chemical and volume control system and the safety injection system, so that the chemical and volume control system or the safety injection system works simultaneously. The specific control method may not be limited and may be set according to actual needs.

[0070] In one embodiment, when executing step S40, specifically, after receiving the protection signal, it takes a certain time for the chemical and volume control system to start and complete the downward isolation function, that is, the preset duration. It also takes a certain 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 are started and fully effective, the water level data of the coolant water level in the reactor pressure vessel may continue to decline. During the process of the water level data falling, the waste heat discharge pump of the safety injection system needs to continue to work to continuously export the residual heat of the core. When the water level data drops to the preset pump stop water level, the waste heat discharge pump may be at risk of cavitation. 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 to below the saturated vapor pressure of the liquid. When the bubbles burst in the high pressure area, they will cause impact and erosion to 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 discharge pump.

[0071] In one embodiment, when executing step S50, specifically, before the chemical and volume control system and the safety injection system are started and fully effective, the water level data of the reactor pressure vessel may continue to drop. When the water level data is lower than the preset normal water level, it can be considered that although the chemical and volume control system and the safety injection system are being started, the water level data of the reactor pressure vessel is not higher than the preset normal water level. At this time, the chemical and volume control system and the safety injection system need to continue to work. That is, the safety injection system replenishes coolant into the reactor pressure vessel, and the downflow pipeline of the chemical and volume control system remains isolated.

[0072] In one embodiment, when step S60 is executed, specifically, after the chemical and volume control system and the safety injection system are started and fully effective, the water level data of the reactor pressure vessel will gradually rise. When the water level data in the reactor pressure vessel is higher than the preset normal water level, the normal water level sensor can send a normal signal. After receiving the normal signal, the diversity drive system can send 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 started and fully effective, the water level data of the reactor pressure vessel may drop to a preset pump stop water level, at which point the waste heat removal pump may be at risk. Therefore, when the pump stop sensor detects that the water level data is lower than or equal to the preset pump stop water level, a pump stop signal may be issued. After receiving the pump stop signal, the diversity drive system may issue a shutdown signal to the safety injection system. After receiving the shutdown signal, the safety injection system may shut down the waste heat removal pump to avoid further mechanical damage.

[0074] In one embodiment, when executing step S80, specifically, after the safety injection system shuts down 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 will gradually rise. At this time, it can be determined whether the water level data is higher than the preset pump start 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 start water level, the residual heat removal pump needs to continue to be shut down. When the water level data is higher than the preset pump start water level, that is, after the pump start sensor detects the water level data, a cooling signal can be issued. After receiving the cooling signal, the diversity drive system can issue a start signal to the safety injection system. After receiving the start signal, the safety injection system can restart the residual heat removal pump to cool the reactor pressure vessel.

[0076] It should be understood that the order of execution of the steps in the above embodiment does not necessarily mean the order of execution. The execution order of each process should be determined by its function and internal logic, and should not constitute any limitation on the implementation process of the embodiment of the present invention.

[0077] It can be seen that in the above scheme, through multi-level monitoring and automatic response mechanisms, the coolant water level is guaranteed to be kept within the safe range at all times, the core exposure is prevented, and the reactor is ensured not to be seriously damaged during the accident, thus avoiding the potential risk of meltdown caused by core exposure. Through effective water level monitoring and reasonable pump stop and start control mechanism, the residual heat removal pump of the safety injection system is prevented from cavitation when the water level is too low, ensuring that the residual heat removal pump can work under appropriate water level conditions, which not only protects the residual heat removal pump, but also ensures 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, automatic control and linkage mechanisms are realized. This enables the system to respond quickly during an accident, avoiding delays in manual operations, and greatly improving the efficiency of accident response and the safety of the system.

[0078] See also Figure 2 The present invention also provides a protection device for a nuclear power plant reactor, which can be applied to the scenario where the nuclear power plant is in a cold shutdown state for maintenance, the discharge flow of the chemical and volume control system is suddenly too large, and the reactor protection system fails, resulting in an uncontrollable water level drop in the reactor pressure vessel. The above protection method can be applied to the protection device. The protection device may include a judgment module 100, a control module 200, and a mitigation module 300.

[0079] In one embodiment, the judgment module 100 can be used to obtain 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 may be configured to send a protection signal according to a low water level signal.

[0081] In one embodiment, the mitigation module 300 may be used to enable the safety injection system to replenish coolant into the reactor pressure vessel according to the protection signal, and to activate the leakage isolation function of the chemical and volume control system.

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

[0083] In one embodiment, the memory 12 includes at least one type of readable storage medium, and the readable storage medium includes a flash memory, a mobile hard disk, a multimedia card, a card-type memory (for example, SD or DX memory, etc.), a magnetic memory, a disk, an optical disk, etc. In some embodiments, the memory 12 may be an internal storage unit of the electronic device 1, such as a mobile hard disk of the electronic device 1. In other embodiments, the memory 12 may also be an external storage device of the electronic device 1, such as a plug-in mobile hard disk, a smart memory card (Smart Media Card, SMC), a secure digital (Secure Digital, SD) card, a flash card (Flash Card), etc. equipped on the electronic device 1. Further, the memory 12 may also include both an internal storage unit of the electronic device 1 and an external storage device. The memory 12 can not only be used to store application software and various types of data installed in the electronic device 1, such as the protection code of the nuclear power plant reactor, but also be used to temporarily store data that has been output or is to be output.

[0084] In one embodiment, the processor 13 may be composed of an integrated circuit, for example, 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, and combinations of various control chips. The processor 13 is the control core (ControlUnit) of the electronic device 1, and uses various interfaces and lines to connect various components of the entire electronic device 1, and executes or executes programs or modules (such as a power battery capacity correction program, etc.) stored in the memory 12, and calls data stored in the memory 12 to execute 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 protection method for the nuclear power plant reactor.

[0086] In one embodiment, the computer program may be divided into one or more modules, one or more modules are stored in the memory 12, and executed by the processor 13 to complete the present application. One or more modules may be a series of computer program instruction segments capable of completing 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 above-mentioned integrated unit implemented in the form of a software function module can be stored in a computer-readable storage medium, and the computer-readable storage medium can be non-volatile or volatile. The above-mentioned software function module is stored in a storage medium, including a number of instructions for enabling a computer device (which can be a personal computer, a computer device, or a network device, etc.) or a processor to perform part of the functions of the protection method of the nuclear power plant reactor in each embodiment of the present application.

[0088] The embodiments of the present invention disclosed above are only used to help illustrate the present invention. The embodiments do not describe all the details in detail, nor do they limit the invention to the specific embodiments described. Obviously, many modifications and changes can be made according to the content of this specification. This specification selects and specifically describes these embodiments in order to better explain the principles and practical applications of the present invention, so that those skilled in the art can understand and use the present invention well. 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: Applicable to the scenario where a nuclear power plant is in a cold shutdown state for maintenance, the reactor pressure vessel has an uncontrollable water level drop due to a sudden excessive discharge flow from the chemical and volume control system, and the reactor protection system fails. At this time, the safety injection system operates in a residual heat removal mode to continuously remove heat from the reactor pressure vessel. The protection method includes: Acquiring water level data in the reactor pressure vessel in real time, and sending a low water level signal when the water level data is lower than a preset low water level; Sending 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 leakage isolation function of the chemical and volume control system.

2. The method for protecting a nuclear power plant reactor according to claim 1, characterized in that: The step of acquiring the water level data in the reactor pressure vessel in real time and sending 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, characterized in that: After the step of replenishing coolant into the reactor pressure vessel by the safety injection system according to the protection signal and starting the leakage isolation function of the chemical and volume control system, the method further includes: 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 starts the leakage isolation function of the chemical and volume control system; wherein the preset low water level is lower than the 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.

4. The method for protecting a nuclear power plant reactor according to claim 3, characterized in that: 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, it also 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; according to the pump-stop signal, sending a shutdown signal to the safety injection system; the safety injection system shuts down the waste heat discharge pump according to the shutdown signal; wherein the preset pump-stop water level is lower than a preset low water level.

5. The method for protecting a nuclear power plant reactor according to claim 4, characterized in that: 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 it is higher than the preset pump start water level, a cooling signal is sent; according to the cooling signal, a start signal is sent to the safety injection system; according to the start signal, the safety injection system starts the waste heat discharge pump; Otherwise, continue to shut down the waste heat removal pump.

6. The method for protecting a nuclear power plant reactor according to claim 1, characterized in that: 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.

7. The method for protecting a nuclear power plant reactor according to claim 1, characterized in that: A normal water level sensor, a low water level sensor, a pump stop sensor and a pump start sensor are respectively installed at different positions in the reactor pressure vessel; 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 the preset pump start water level.

8. A protection device for a nuclear power plant reactor, characterized in that: Applicable to the scenario where the nuclear power plant is in a cold shutdown state for maintenance, the reactor pressure vessel has an uncontrollable water level drop due to a sudden excessive discharge flow from the chemical and volume control system, and the reactor protection system fails. At this time, the safety injection system operates in the residual heat removal mode to continuously remove the heat in the reactor pressure vessel. The protection device includes: A judgment module, used for obtaining water level data in the reactor pressure vessel in real time, and sending 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 used for replenishing coolant into the reactor pressure vessel through a safe injection system according to the protection signal, and starting the leakage isolation function of the chemical and volume control system.

9. A computer device comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, characterized in that: 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 7 are implemented.

10. 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 7 are implemented.

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