Nuclear power plant reactor coolant system pressurizer level control method and system

Abstract

The present application relates to a method and system for controlling the level of a pressurizer of a reactor coolant system of a nuclear power unit, comprising the following steps: switching to a newly added pressurizer water level set value control logic when the temperature of a primary loop is less than or equal to a first preset value; obtaining real-time temperature data of the primary loop after switching to the newly added pressurizer water level set value control logic; calculating the real-time temperature data to obtain a level setting value of the pressurizer; obtaining primary loop flow data and real-time level of the pressurizer; calculating the primary loop flow data, the level setting value and the real-time level to obtain valve position data; and adjusting the level of the pressurizer according to the valve position data. The present application switches to the newly added pressurizer water level set value control logic when the temperature of the primary loop is less than or equal to the first preset value, so as to raise the water level of the pressurizer to a reasonable level before connecting the residual heat removal system, thereby reducing the subsequent time length of the pressurizer steam elimination cavity, reducing the occupation of the overhaul critical path window, and significantly improving the economy.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of nuclear power plant nuclear power units, more particularly, to a pressurizer liquid level control method and system for a nuclear power unit reactor coolant system. BACKGROUND

[0002] During the descending process of a nuclear power plant nuclear power unit, there is a key operation after the RIS-RHR system is connected, which is the pressurizer steam cavity, but under the existing scheme, it takes a long time, seriously occupies the overhaul critical path window, and has poor economy. SUMMARY

[0003] The technical problem to be solved by the present application is to provide a pressurizer liquid level control method and system for a nuclear power unit reactor coolant system, which solves the defects of the prior art.

[0004] The technical scheme adopted by the present application to solve the technical problem is: a pressurizer liquid level control method for a nuclear power unit reactor coolant system is constructed, comprising the following steps:

[0005] When the primary loop temperature is less than or equal to a first preset value, switch to the newly added pressurizer water level set value control logic;

[0006] After switching to the newly added pressurizer water level set value control logic, real-time temperature data of the primary loop is obtained;

[0007] According to the real-time temperature data, the liquid level setting value of the pressurizer is obtained by calculation;

[0008] Obtain the primary loop flow data and the real-time liquid level of the pressurizer;

[0009] According to the primary loop flow data, the liquid level setting value, and the real-time liquid level, valve position data is obtained by calculation;

[0010] According to the valve position data, the liquid level of the pressurizer is adjusted.

[0011] In the pressurizer liquid level control method for a nuclear power unit reactor coolant system, the real-time temperature data of the primary loop includes:

[0012] Obtain the first real-time temperature of the first loop, the second real-time temperature of the second loop, and the third real-time temperature of the third loop;

[0013] The first real-time temperature, the second real-time temperature, and the third real-time temperature are processed by averaging to obtain an average temperature; the average temperature is the real-time temperature data.

[0014] In the nuclear power unit reactor coolant system pressurizer liquid level control method, the calculation according to the real-time temperature data to obtain the liquid level setting value of the pressurizer comprises:

[0015] The inverse function of the temperature is used to calculate the real-time temperature data to obtain the liquid level setting value of the pressurizer.

[0016] In the nuclear power unit reactor coolant system pressurizer liquid level control method, the one-loop flow data includes: the charging flow data and the discharge flow data;

[0017] The calculation according to the one-loop flow data, the liquid level setting value and the real-time liquid level to obtain the valve position data comprises:

[0018] According to the charging flow data and the discharge flow data, the flow difference value of the charging flow data and the discharge flow data is obtained;

[0019] According to the liquid level setting value and the real-time liquid level, the liquid level difference value of the liquid level setting value and the real-time liquid level is obtained;

[0020] Based on the flow difference value and the liquid level difference value, the valve position data is obtained.

[0021] In the nuclear power unit reactor coolant system pressurizer liquid level control method, the calculation based on the flow difference value and the liquid level difference value to obtain the valve position data comprises:

[0022] The liquid level difference value is converted to obtain a flow value corresponding to the liquid level difference value;

[0023] According to the flow difference value and the flow value, the valve position data is obtained.

[0024] In the nuclear power unit reactor coolant system pressurizer liquid level control method, the adjustment of the liquid level of the pressurizer according to the valve position data comprises:

[0025] According to the valve position data, a driving signal is outputted;

[0026] The opening degree of the discharge valve is controlled by the driving signal to adjust the liquid level of the pressurizer.

[0027] In the nuclear power unit reactor coolant system pressurizer liquid level control method, the method further comprises:

[0028] It is judged whether the one-loop is connected to the residual heat removal system;

[0029] If yes, cut off the newly added stabilizer water level setting value control logic.

[0030] The application further provides a stabilizer liquid level control system of a nuclear power unit reactor coolant system, comprising:

[0031] A switching unit is configured to switch to the newly added stabilizer water level setting value control logic when the primary loop temperature is less than or equal to a first preset value.

[0032] A first acquisition unit is configured to acquire real-time temperature data of the primary loop after switching to the newly added stabilizer water level setting value control logic.

[0033] A setting value calculation unit is configured to calculate the real-time temperature data to obtain a liquid level setting value of the stabilizer.

[0034] A second acquisition unit is configured to acquire primary loop flow data and real-time liquid level of the stabilizer.

[0035] A valve position calculation unit is configured to calculate the primary loop flow data, the liquid level setting value, and the real-time liquid level to obtain valve position data.

[0036] A control unit is configured to adjust the liquid level of the stabilizer according to the valve position data.

[0037] In the stabilizer liquid level control system of the nuclear power unit reactor coolant system, the first acquisition unit comprises a first temperature detection device, a second temperature detection device, a third temperature detection device, and a mean value processing module.

[0038] The first temperature detection device is configured to detect a first real-time temperature of a first loop and send the first real-time temperature to the mean value processing module.

[0039] The second temperature detection device is configured to detect a second real-time temperature of a second loop and send the second real-time temperature to the mean value processing module.

[0040] The third temperature detection device is configured to detect a third real-time temperature of a third loop and send the third real-time temperature to the mean value processing module.

[0041] The mean value processing module is connected to the first temperature detection device, the second temperature detection device, and the third temperature detection device, respectively, and is configured to perform mean value processing on the first real-time temperature, the second real-time temperature, and the third real-time temperature to obtain an average temperature; the average temperature is the real-time temperature data.

[0042] In the stabilizer liquid level control system of the nuclear power unit reactor coolant system, further comprising an isolation module; the second acquisition unit comprises a first flow detection device, a second flow detection device, and a liquid level detection device.

[0043] The isolation module is arranged between the average processing module and the set value calculation unit, and is used for performing an isolation operation and transmitting the real-time temperature data to the set value calculation unit.

[0044] The first flow detection device is used for detecting the charging flow to obtain charging flow data.

[0045] The second flow detection device is used for detecting the discharging flow to obtain discharging flow data.

[0046] The liquid level detection device is used for detecting the liquid level of the stabilizer to obtain real-time liquid level.

[0047] The stabilizer liquid level control method and system of the nuclear power unit reactor coolant system have the following beneficial effects: including the following steps: when the primary loop temperature is less than or equal to a first preset value, switching to the newly added stabilizer water level set value control logic; after switching to the newly added stabilizer water level set value control logic, obtaining real-time temperature data of the primary loop; calculating according to the real-time temperature data to obtain a liquid level set value of the stabilizer; obtaining primary loop flow data and real-time liquid level of the stabilizer; calculating according to the primary loop flow data, the liquid level set value, and the real-time liquid level to obtain valve position data; and adjusting the liquid level of the stabilizer according to the valve position data. The stabilizer water level is lifted to a reasonable level before the connection of the residual heat removal system, thereby reducing the subsequent stabilizer deaerator cavity time, reducing the occupation of the overhaul critical path window, and significantly improving the economy. BRIEF DESCRIPTION OF DRAWINGS

[0048] The present application will be further described below in conjunction with the accompanying drawings and embodiments. In the drawings:

[0049] Figure 1 is a flow chart of the stabilizer liquid level control method of the nuclear power unit reactor coolant system provided by the embodiments of the present application;

[0050] Figure 2 is a principle block diagram of the stabilizer liquid level control system of the nuclear power unit reactor coolant system provided by the embodiments of the present application. DETAILED DESCRIPTION

[0051] The technical solutions in the embodiments of the present application will be clearly and completely described below in conjunction with the accompanying drawings of the embodiments of the present application. Obviously, the described embodiments are only part of the embodiments of the present application, rather than all the embodiments of the present application. Based on the embodiments in the present application, all other embodiments obtained by those skilled in the art without creative labor fall within the protection scope of the present application.

[0052] In the process of the downlink pressure stabilizer of the nuclear power unit, the heater works continuously to maintain the saturated temperature of the vapor phase of the pressure stabilizer. The water filling process of the pressure stabilizer cannot be too fast, otherwise a large amount of cold water entering the pressure stabilizer will cause the vapor phase steam to condense rapidly, resulting in a loss of control of the primary loop pressure, endangering the safe operation of the main pump. The existing scheme takes a long time, therefore, in order to solve these problems, the present application provides a pressure stabilizer liquid level control method of a nuclear power unit waste heat removal system, which slowly lifts the water level of the pressure stabilizer to a reasonable water level before the pressure stabilizer cavity is started, which can not only avoid the risk of loss of control of the primary loop pressure due to a large amount of cold water entering the pressure stabilizer, but also reduce the subsequent pressure stabilizer cavity time and reduce the occupation of the key path window of the overhaul.

[0053] In a preferred embodiment, reference is made to Figure 1 The pressure stabilizer liquid level control method of the nuclear power unit reactor coolant system comprises the following steps:

[0054] Step S101, when the primary loop temperature is less than or equal to the first preset value, switch to the newly added pressure stabilizer water level set value control logic.

[0055] Alternatively, the first preset value can be set to 280℃. Specifically, when the primary loop is less than or equal to 280℃, the control logic can be switched to the newly added pressure stabilizer water level set value control logic by the operator controlling the selection button.

[0056] Specifically, during the primary loop temperature drop process, when the primary loop temperature drops to 280℃, the operator manually controls the selection button to switch. The switching of the newly added pressure stabilizer water level set value control logic is generally completed between 284℃ and 280℃. Step S102, after switching to the newly added pressure stabilizer water level set value control logic, obtaining real-time temperature data of the primary loop.

[0057] In some embodiments, obtaining real-time temperature data of the primary loop comprises: obtaining a first real-time temperature of a first loop, a second real-time temperature of a second loop, and a third real-time temperature of a third loop; and performing mean value processing on the first real-time temperature, the second real-time temperature, and the third real-time temperature to obtain an average temperature. The average temperature is the real-time temperature data.

[0058] Optionally, in some embodiments, the first loop, the second loop and the third loop are three loops of a loop. The first real-time temperature can be detected in real time by the first temperature detection device 121 arranged in the first loop, the second real-time temperature can be detected in real time by the second temperature detection device 122 arranged in the second loop, and the third real-time temperature can be detected in real time by the third temperature detection device 123 arranged in the third loop. The first temperature detection device 121, the second temperature detection device 122 and the third temperature detection device 123 can be realized by using a temperature sensor or a thermometer in the existing loop, and other temperature detection devices or equipment capable of detecting the temperature of the loop also belong to the scope of the embodiments of the present application.

[0059] In step S103, the liquid level setting value of the pressurizer is obtained by calculating according to the real-time temperature data.

[0060] Specifically, in some embodiments, the calculation according to the real-time temperature data to obtain the liquid level setting value of the pressurizer includes: using the inverse function of temperature to calculate the real-time temperature data to obtain the liquid level setting value of the pressurizer. The inverse function of temperature can realize the conversion between temperature and liquid level. When the loop temperature is 280℃, it corresponds to the loop zero-power liquid level (i.e. the pressurizer 34% relative water level), and when the loop temperature is 180℃, it corresponds to a higher reasonable liquid level. Alternatively, the reasonable liquid level can be set to be near the pressurizer 65% to 70% relative water level.

[0061] In step S104, the loop flow data and the real-time liquid level of the pressurizer are obtained.

[0062] In some embodiments, the loop flow data includes: the charging flow data and the discharge flow data. The charging flow data can be detected in real time by the first flow detection device 151, and the discharge flow data can be detected in real time by the second flow detection device 152. Optionally, the first flow detection device 151 and the second flow detection device 152 can use a general flow meter as long as the loop flow can be detected.

[0063] In the embodiments of the present application, the charging flow data is the flow from the chemical volume control system into the loop, and the discharge flow is the flow from the loop into the chemical volume control system.

[0064] In step S105, the valve position data is obtained by calculating according to the loop flow data, the liquid level setting value and the real-time liquid level.

[0065] In some embodiments, the valve position data is obtained by calculating the difference between the charging flow data and the discharging flow data according to the loop flow data, the set liquid level and the real-time liquid level.

[0066] In some embodiments, the valve position data is obtained by calculating the difference between the charging flow data and the discharging flow data according to the loop flow data, the set liquid level and the real-time liquid level.

[0067] In some embodiments, the valve position data is obtained by calculating the difference between the charging flow data and the discharging flow data according to the loop flow data, the set liquid level and the real-time liquid level.

[0068] In some embodiments, the valve position data is obtained by calculating the difference between the charging flow data and the discharging flow data according to the loop flow data, the set liquid level and the real-time liquid level.

[0069] Further, the method for controlling the liquid level of the pressurizer of the reactor coolant system of the nuclear power unit according to the embodiments of the present application further comprises: determining whether the loop is connected to the residual heat removal system; if yes, the newly added pressurizer water level setting control logic is removed. Specifically, when the loop is connected to the residual heat removal system, the newly added pressurizer water level setting control logic is manually removed by the operator, and the original control logic is switched back, so that the liquid level of the pressurizer continues to rise until the steam cavity of the pressurizer is close to disappearing.

[0070] Alternatively, the second preset value can be set to 180℃. Specifically, when the temperature of the loop reaches 180℃, through calculation, the steam space in the pressurizer is about 20m 3 to 25m3, and the pressurizer water level has a distance of at least 4m to the top of the pressurizer, so that the safety margin is sufficient to cope with potential fluctuations in the loop pressure. When the loop starts to extinguish the steam cavity, the operator controls the selection button to exit the newly added pressurizer water level setting control logic from the system, and then the pressurizer is filled with water according to the current liquid level of the pressurizer until the full water level, so as to complete the whole process of extinguishing the steam cavity of the pressurizer.

[0071] Further, in the embodiment of the present application, under the premise that all the heaters of the pressurizer are started, the subcooled water entering the pressurizer at a liquid level of 34% to 70% can be heated to saturated water in about 1 hour, so that the pressurizer liquid level control method of the nuclear power unit reactor coolant system of the present application can be applied even in the accident condition or when the primary loop is rapidly cooled, thereby providing a convenient condition for shortening the time of unit retreat.

[0072] In the embodiment of the present application, the primary loop temperature is reduced from 280℃ to 180℃ in about 4 hours, and in this interval, the set value of the pressurizer liquid level gradually increases with the decrease of the primary loop temperature, so that the dynamic process of the stable lifting of the pressurizer water level is realized, and the risk of primary loop pressure loss caused by possible rapid pressurizer water filling is avoided.

[0073] In a preferred embodiment, referring to Figure 2 The present application provides a pressurizer liquid level control system of a nuclear power unit reactor coolant system. The pressurizer liquid level control method of the nuclear power unit reactor coolant system disclosed in the embodiment of the present application can be applied to the pressurizer liquid level control system of the nuclear power unit reactor coolant system.

[0074] Specifically, as Figure 2 The pressurizer liquid level control system of the nuclear power unit reactor coolant system comprises:

[0075] The switching unit 11 is configured to switch to the newly added pressurizer water level set value control logic when the temperature of the primary loop is less than or equal to the first preset value.

[0076] Alternatively, the switching unit 11 can be a selection button. Specifically, when the primary loop is less than or equal to 284℃, the selection button can be controlled by the operator to switch the control logic to the newly added pressurizer water level set value control logic.

[0077] The first acquisition unit 12 is configured to acquire real-time temperature data of the primary loop after switching to the newly added pressurizer water level set value control logic.

[0078] In some embodiments, the first acquisition unit 12 comprises a first temperature detection device 121, a second temperature detection device 122, a third temperature detection device 123 and a mean value processing module 124.

[0079] The first temperature detection device 121 is configured to detect a first real-time temperature of the first loop and send the first real-time temperature to the average processing module 124; the second temperature detection device 122 is configured to detect a second real-time temperature of the second loop and send the second real-time temperature to the average processing module 124; the third temperature detection device 123 is configured to detect a third real-time temperature of the third loop and send the third real-time temperature to the average processing module 124; the average processing module 124 is connected with the first temperature detection device 121, the second temperature detection device 122 and the third temperature detection device 123, and is configured to perform average processing on the first real-time temperature, the second real-time temperature and the third real-time temperature to obtain an average temperature. The average temperature is real-time temperature data.

[0080] The first temperature detection device 121, the second temperature detection device 122 and the third temperature detection device 123 can be implemented by using a temperature sensor or a thermometer in the existing loop, and other temperature detection devices or equipment that can detect the temperature of the loop also belong to the scope of embodiments of the present application.

[0081] The setting value calculation unit 14 is configured to calculate the real-time temperature data to obtain a liquid level setting value of the voltage stabilizer.

[0082] Specifically, the setting value calculation unit 14 calculates the real-time temperature data by using an inverse function of temperature to obtain the liquid level setting value of the voltage stabilizer. The inverse function of temperature can convert the temperature and the liquid level. When the temperature of the loop is 284 ℃ to 280 ℃, the zero-power liquid level of the loop (i.e., the 34% relative water level of the voltage stabilizer) is obtained, and when the temperature of the loop is 180 ℃, a higher reasonable liquid level is obtained. Alternatively, the reasonable liquid level can be set to be near the 65% to 70% relative water level of the voltage stabilizer.

[0083] Further, an isolation module 13 is arranged between the average processing module 124 and the setting value calculation unit 14. The isolation module 13 is configured to perform an isolation operation and transmit the real-time temperature data to the setting value calculation unit 14.

[0084] The second acquisition unit 15 is configured to acquire the loop flow data and the real-time liquid level of the voltage stabilizer.

[0085] In some embodiments, the second acquisition unit 15 includes a first flow detection device 151, a second flow detection device 152 and a liquid level detection device 153. The first flow detection device 151 is configured to detect the charging flow to obtain charging flow data; the second flow detection device 152 is configured to detect the discharging flow to obtain discharging flow data; and the liquid level detection device 153 is configured to detect the liquid level of the voltage stabilizer to obtain the real-time liquid level.

[0086] In some embodiments, the loop flow data includes the charging flow data and the discharging flow data.

[0087] Optionally, the first flow detection device 151 and the second flow detection device 152 can adopt a general flow meter as long as the loop flow can be detected. In the embodiment of the present application, the upflow data is the flow from the chemical volume control system into the loop, and the downflow data is the flow from the loop into the chemical volume control system.

[0088] The valve position calculation unit 16 is configured to calculate the valve position data according to the loop flow data, the liquid level setting value and the real-time liquid level.

[0089] Specifically, the valve position calculation unit 16 calculates the flow difference value of the upflow data and the downflow data according to the upflow data and the downflow data, calculates the liquid level difference value of the liquid level setting value and the real-time liquid level according to the liquid level setting value and the real-time liquid level, and calculates the valve position data based on the flow difference value and the liquid level difference value.

[0090] In some embodiments, the data conversion between the liquid level and the flow can be achieved by using an existing data conversion method, which is not limited in the present application. Similarly, the calculation of the valve position data can also be achieved by using a general flow valve position calculation method, which is not limited in the present application.

[0091] The control unit 17 is configured to adjust the liquid level of the pressurizer according to the valve position data.

[0092] In some embodiments, the control unit 17 outputs a driving signal according to the valve position data, and controls the opening degree of the downflow valve by the driving signal to adjust the liquid level of the pressurizer.

[0093] Further, in the process of executing the new pressurizer water level setting value control logic, the operator judges whether the loop is connected with the residual heat removal system. If the loop is connected with the residual heat removal system, the operator manually switches to cut off the new pressurizer water level setting value control logic and switches back to the original control logic, so that the pressurizer water level continues to rise until the pressurizer vapor cavity approaches to disappear.

[0094] The embodiment of the present application automatically raises the pressurizer water level before the nuclear power unit residual heat removal system is connected, and converts the control mode of manually raising the pressurizer liquid level by the operator during the overhaul period into automatic control, which not only reduces the burden of the operator, but also avoids the potential risk of improper operation by personnel. Moreover, in the accident condition, if the unit needs to be quickly cooled and withdrawn after the loop temperature is lowered, the pressurizer liquid level control method of the nuclear power unit reactor coolant system of the present application can effectively shorten the unit withdrawal time.

[0095] The various embodiments described in the specification are progressive in nature, and each embodiment highlights the differences from other embodiments. The same or similar parts among the various embodiments can be mutually referred to. For the apparatus disclosed by the embodiments, since it corresponds to the method disclosed by the embodiments, the description is relatively simple, and the relevant parts can be referred to the method part.

[0096] Those skilled in the art will further appreciate that the units and algorithm steps of the examples described in connection with the embodiments disclosed herein can be implemented in electronic hardware, computer software, or both. The disclosure is not limited to one implementation in hardware or in software, but rather, the disclosure can be implemented in any combination of hardware and software to achieve the functionality described in the disclosure. The software comprises one or more computer program elements to provide the functionality described in the disclosure. The computer program elements can be stored in any computer readable medium for use by or in connection to an instruction execution system, apparatus, or device.

[0097] The steps of a method or algorithm described in connection with the embodiments disclosed herein can be embodied directly in hardware, in a software module executed by a processor, or in a combination of the two. A software module can reside in RAM, flash memory, ROM, electrically programmable ROM (EPROM), electrically erasable programmable ROM (EEPROM), registers, hard disk, a removable disk, a CD-ROM, or any other form of storage medium known in the art.

[0098] The above embodiments are only for illustrating the technical concept and characteristics of the present application, and the purpose is to enable those skilled in the art to understand the content of the present application and implement it accordingly, and cannot limit the protection scope of the present application. Any equivalent changes and modifications made within the scope of the claims of the present application shall be within the scope of the claims of the present application.

Claims

1. A pressurizer level control method for a nuclear power plant reactor coolant system, comprising: The method comprises the following steps: switching to the newly-added water level setting value control logic of the stabilizer when the temperature of the primary loop is less than or equal to a first preset value; obtaining real-time temperature data of the primary loop after switching to the newly-added water level setting value control logic of the stabilizer; calculating the liquid level setting value of the stabilizer according to the real-time temperature data; obtaining primary loop flow data and real-time liquid level of the stabilizer; calculating valve position data according to the primary loop flow data, the liquid level setting value and the real-time liquid level; adjusting the liquid level of the stabilizer according to the valve position data; The method further comprises: determining whether the primary loop is connected to a residual heat removal system; determining whether the current temperature of the primary loop is less than or equal to a second preset value according to the real-time temperature data; if yes, cutting off the newly-added water level setting value control logic of the stabilizer.

2. The method of claim 1, wherein, The method of obtaining real-time temperature data of the primary loop comprises: obtaining a first real-time temperature of a first loop, a second real-time temperature of a second loop and a third real-time temperature of a third loop; performing mean value processing on the first real-time temperature, the second real-time temperature and the third real-time temperature to obtain an average temperature; the average temperature is the real-time temperature data.

3. The method of claim 1, wherein, The method of calculating the liquid level setting value of the stabilizer according to the real-time temperature data comprises: calculating the liquid level setting value of the stabilizer by using the inverse function of temperature on the real-time temperature data.

4. The method of claim 1, wherein, The primary loop flow data comprises: charging flow data and bleeding flow data; The method of calculating valve position data according to the primary loop flow data, the liquid level setting value and the real-time liquid level comprises: calculating the flow difference between the charging flow data and the bleeding flow data according to the charging flow data and the bleeding flow data; calculating the liquid level difference between the liquid level setting value and the real-time liquid level according to the liquid level setting value and the real-time liquid level; calculating the valve position data based on the flow difference and the liquid level difference.

5. The method of claim 4, wherein, The method of calculating the valve position data based on the flow difference and the liquid level difference comprises: converting the liquid level difference to obtain a flow value corresponding to the liquid level difference; calculating the valve position data according to the flow difference and the flow value.

6. The method of claim 1, wherein, The method of adjusting the liquid level of the stabilizer according to the valve position data comprises: outputting a driving signal according to the valve position data; controlling the opening degree of the bleeding valve through the driving signal to adjust the liquid level of the stabilizer.

7. A pressurizer level control system for a nuclear power plant reactor coolant system, comprising: The method comprises: a switching unit configured to switch to the newly-added water level setting value control logic of the stabilizer when the temperature of the primary loop is less than or equal to a first preset value; a first obtaining unit configured to obtain real-time temperature data of the primary loop after switching to the newly-added water level setting value control logic of the stabilizer; a setting value calculation unit configured to calculate the liquid level setting value of the stabilizer according to the real-time temperature data; a second obtaining unit configured to obtain primary loop flow data and real-time liquid level of the stabilizer; a valve position calculation unit configured to calculate valve position data according to the primary loop flow data, the liquid level setting value and the real-time liquid level. A control unit is configured to adjust the liquid level of the stabilizer according to the valve position data. The switching unit is further configured to, after connecting the primary loop to the residual heat removal system, determine whether the current temperature of the primary loop is less than or equal to a second preset value according to the real-time temperature data, and if yes, switch off the newly added stabilizer water level set value control logic.

8. The pressurizer level control system of a nuclear power plant reactor coolant system of claim 7, wherein, The first acquisition unit comprises a first temperature detection device, a second temperature detection device, a third temperature detection device and a mean value processing module. The first temperature detection device is configured to detect a first real-time temperature of a first loop and send the first real-time temperature to the mean value processing module. The second temperature detection device is configured to detect a second real-time temperature of a second loop and send the second real-time temperature to the mean value processing module. The third temperature detection device is configured to detect a third real-time temperature of a third loop and send the third real-time temperature to the mean value processing module. The mean value processing module is connected to the first temperature detection device, the second temperature detection device and the third temperature detection device, respectively, and is configured to perform mean value processing on the first real-time temperature, the second real-time temperature and the third real-time temperature to obtain an average temperature; the average temperature is the real-time temperature data.

9. The pressurizer level control system of a nuclear power plant reactor coolant system of claim 8 wherein, Further comprising: an isolation module; The second acquisition unit comprises a first flow detection device, a second flow detection device and a liquid level detection device; The isolation module is arranged between the mean value processing module and the set value calculation unit, and is configured to perform an isolation operation and transmit the real-time temperature data to the set value calculation unit; The first flow detection device is configured to detect the charging flow to obtain charging flow data; The second flow detection device is configured to detect the discharge flow to obtain discharge flow data; The liquid level detection device is configured to detect the liquid level of the stabilizer to obtain real-time liquid level.

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