Control method and device of nuclear reactor system

Abstract

The invention discloses a control method and device of a nuclear reactor system, a coolant circulation loop of the nuclear reactor system comprises a main pump channel and a bypass channel arranged in parallel with the main pump channel, the bypass channel is provided with a bypass valve, and the method comprises the following steps: obtaining operation state information of the nuclear reactor system; if it is determined that the nuclear reactor system operates in a first operation mode according to the operation state information, the target power of the nuclear reactor system and the target temperature difference of a cold section and a hot section of a coolant circulation loop are obtained, and the first operation mode is an operation mode in which the nuclear reactor system performs natural circulation; determining a target opening degree of a bypass valve according to the target power and the target temperature difference of the cold and hot sections; and the bypass valve is controlled to be opened to the target opening degree.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of nuclear reactors, and particularly relates to a control method and device of a nuclear reactor system. BACKGROUND

[0002] Nuclear reactors are generally operated in forced flow mode, that is, a coolant circulating pump (main pump) is arranged in a loop, and the coolant in the loop is driven to flow by the main pump. Some small reactors are operated in natural circulation mode, that is, no main pump is arranged in the loop, and the driving force is generated between coolants at different temperatures due to different gravity caused by different densities of the coolants at different temperatures, so that the circulation of flow is formed.

[0003] In the related art, a nuclear reactor integrates forced flow operation and natural circulation operation, and can switch between the two operation modes. However, when switching to the natural circulation operation mode, the flow resistance in the loop is greatly increased due to the shutdown of the main pump in the loop, and the cooling performance of the nuclear reactor is difficult to meet the demand. SUMMARY

[0004] The present application aims to provide a control method and device of a nuclear reactor system, which can improve the cooling performance of the nuclear reactor.

[0005] In a first aspect, an embodiment of the present application provides a control method of a nuclear reactor system, a coolant circulating loop of the nuclear reactor system comprising a main pump channel and a bypass channel arranged in parallel with the main pump channel, and a bypass valve arranged on the bypass channel, and the method comprising:

[0006] obtaining operation state information of the nuclear reactor system;

[0007] if it is determined according to the operation state information that the nuclear reactor system is operated in a first operation mode, obtaining a target power of the nuclear reactor system and a target temperature difference of a cold-heat section of the coolant circulating loop, wherein the first operation mode is a natural circulation operation mode of the nuclear reactor system;

[0008] determining a target opening degree of the bypass valve according to the target power and the target temperature difference of the cold-heat section;

[0009] controlling the bypass valve to open to the target opening degree.

[0010] According to some embodiments of the present application, the determination of the target opening degree of the bypass valve according to the target power and the target temperature difference of the cold-heat section comprises:

[0011] obtaining a power-temperature difference-opening degree calibration relationship, the power-temperature difference-opening degree calibration relationship comprising a mapping relationship of a plurality of powers, a plurality of cold-heat section temperature differences and a plurality of opening degree calibration values of the bypass valve of the nuclear reactor system;

[0012] determining, based on the power-temperature difference-opening degree calibration relationship, an opening degree calibration value corresponding to the target power and the target cold-heat section temperature difference as the target opening degree.

[0013] According to some embodiments of the present application, after obtaining the target power of the nuclear reactor system, the method further comprises:

[0014] obtaining a real-time power of the nuclear reactor system;

[0015] controlling a control rod of the nuclear reactor system according to the real-time power and the target power.

[0016] According to some embodiments of the present application, the method further comprises:

[0017] controlling a steam turbine of the nuclear reactor system to operate at a preset first inlet steam pressure;

[0018] controlling the steam turbine to operate at a preset second inlet steam pressure after a preset first time, the second inlet steam pressure being greater than the first inlet steam pressure, the first inlet steam pressure being a preset inlet steam pressure of the steam turbine in a second operation mode, the second operation mode being an operation mode in which the nuclear reactor system is forced to operate at a flow rate.

[0019] According to some embodiments of the present application, the method further comprises:

[0020] obtaining a preset load of a steam turbine of the nuclear reactor system;

[0021] controlling the steam turbine to operate at the preset load.

[0022] According to some embodiments of the present application, the method further comprises:

[0023] obtaining a real-time steam pressure of a steam generator of the nuclear reactor system;

[0024] controlling an opening degree of a feed water valve of the steam generator according to the real-time steam pressure and a preset target steam pressure, the target steam pressure gradually decreasing from a first steam pressure to a second steam pressure and then gradually increasing to the first steam pressure, the first steam pressure being a preset steam pressure setting value of the steam generator in a second operation mode.

[0025] According to some embodiments of the present application, the method further comprises:

[0026] obtain a feedwater flow reference value, the feedwater flow reference value being calculated according to a feedwater flow theoretical value corresponding to the target power, the cold-hot section target temperature difference and a real-time cold-hot section temperature difference;

[0027] control an opening degree of a feedwater valve of the steam generator according to the feedwater flow reference value, the real-time steam pressure and a target steam pressure.

[0028] According to some embodiments of the present application, the obtaining of the feedwater flow reference value comprises:

[0029] divide the cold-hot section target temperature difference by the real-time cold-hot section temperature difference to obtain a temperature difference intermediate value;

[0030] multiply the temperature difference intermediate value by the feedwater flow theoretical value to obtain the feedwater flow reference value.

[0031] According to some embodiments of the present application, the obtaining of the operation state information of the nuclear reactor system comprises:

[0032] obtain a real-time rotating speed of the main pump on the main pump passage;

[0033] obtain the operation state information according to the real-time rotating speed and a preset rotating speed threshold.

[0034] In a second aspect, embodiments of the present application provide a control device of a nuclear reactor system, a coolant circulation loop of the nuclear reactor system comprising a main pump passage and a bypass passage arranged in parallel with the main pump passage, a bypass valve being arranged on the bypass passage, the device comprising:

[0035] a first obtaining module configured to obtain operation state information of the nuclear reactor system;

[0036] a second obtaining module configured to, if it is determined according to the operation state information that the nuclear reactor system is running in a first operation mode, obtain a target power of the nuclear reactor system and a cold-hot section target temperature difference of the coolant circulation loop, wherein the first operation mode is a natural circulation operation mode of the nuclear reactor system;

[0037] an opening degree determining module configured to determine a target opening degree of the bypass valve according to the target power and the cold-hot section target temperature difference;

[0038] a valve control module configured to control the bypass valve to open to the target opening degree.

[0039] In a third aspect, embodiments of the present application provide a nuclear reactor system, which is provided with an electronic device, the electronic device being executed to implement the control method of the nuclear reactor system as described above.

[0040] In a fourth aspect, an electronic device is provided, comprising:

[0041] at least one processor;

[0042] at least one memory for storing at least one program;

[0043] The at least one program, when executed by the at least one processor, implements the method for controlling a nuclear reactor system as described above.

[0044] In a fifth aspect, a computer readable storage medium is provided, which stores a program executable by a processor, and the program, when executed by the processor, implements the method for controlling a nuclear reactor system as described above.

[0045] In the embodiments of the present application, by adding a bypass channel, in the circulating operation mode, the target opening of the bypass valve is determined according to the target power of the nuclear reactor system and the target temperature difference of the cold and hot sections, and then the bypass valve is controlled to open to the target opening, so as to control the flow of the coolant circulating loop, which can avoid excessive resistance of the coolant circulating loop and improve the cooling performance of the nuclear reactor.

[0046] Additional aspects and advantages of the present application will be in part apparent and in part pointed out hereinafter. BRIEF DESCRIPTION OF DRAWINGS

[0047] The present application will be further described below in conjunction with the accompanying drawings and embodiments, in which:

[0048] Figure 1 Flowchart of the embodiment of the method for controlling a nuclear reactor system provided by the present application;

[0049] Figure 2 Functional block diagram of the nuclear reactor system provided by the present application;

[0050] Figure 3 In the embodiment of the method for controlling a nuclear reactor system provided by the present application, the power control logic diagram of the nuclear reactor system;

[0051] Figure 4 In the embodiment of the method for controlling a nuclear reactor system provided by the present application, the control logic diagram of the steam turbine;

[0052] Figure 5 In the embodiment of the method for controlling a nuclear reactor system provided by the present application, the control logic diagram of the steam generator;

[0053] Figure 6 Structural schematic diagram of the embodiment of the control device of the nuclear reactor system provided by the present application;

[0054] Figure 7 A structural schematic diagram of an embodiment of an electronic device provided in the present application is shown.

[0055] Reference signs:

[0056] The reactor core 100, the steam generator 200, the main pump 300, the steam turbine 400, the feedwater system 500, the bypass valve 600, the control device 700, the first acquisition module 710, the second acquisition module 720, the opening degree determination module 730, the valve control module 740, the electronic device 800, the processor 810, and the memory 820. DETAILED DESCRIPTION

[0057] The embodiments of the present application are described in detail below, examples of which are shown in the accompanying drawings, wherein the same or similar notations represent the same or similar elements or elements having the same or similar functions throughout. The embodiments described below by referring to the accompanying drawings are exemplary and are only used to explain the present application, and cannot be understood as a limitation of the present application.

[0058] In the description of the present application, it should be understood that the orientation description, such as the orientation or position relationship indicated by up, down, etc. is based on the orientation or position relationship shown in the drawings, and is only for the purpose of facilitating the description of the present application and simplifying the description, and does not indicate or imply that the device or element referred to must have a particular orientation, be constructed and operated in a particular orientation, and therefore cannot be understood as a limitation of the present application.

[0059] In the description of the present application, multiple refers to more than two. If there is a description of first, second, it is only for the purpose of distinguishing technical features, and cannot be understood as indicating or implying relative importance or implicitly indicating the number of technical features indicated or the sequence relationship of the technical features indicated.

[0060] In the description of the present application, unless otherwise explicitly limited, the words such as setting, installing, connecting, etc. should be broadly understood, and the person skilled in the art can reasonably determine the specific meaning of the above words in the present application in combination with the specific content of the technical solution.

[0061] The following refers to Figures 1 to 7 A control method and device of a nuclear reactor system according to an embodiment of the present application are described.

[0062] The embodiment of the present application provides a control method of a nuclear reactor system, a coolant circulation loop of the nuclear reactor system comprises a main pump passage and a bypass passage arranged in parallel with the main pump passage, a bypass valve 600 is arranged on the bypass passage, and the method comprises the following steps.

[0063] Step S100: acquiring operation state information of the nuclear reactor system;

[0064] Step S200: If it is determined based on the operating status information that the nuclear reactor system is operating in the first operating mode, a target power of the nuclear reactor system and a target temperature difference between the cold and hot sections of the coolant circulation loop are obtained, wherein the first operating mode is an operating mode in which the nuclear reactor system performs natural circulation;

[0065] Step S300: Determine the target opening of the bypass valve 600 according to the target power and the target temperature difference between the hot and cold sections;

[0066] Step S400: Control the bypass valve 600 to open to a target opening.

[0067] In an embodiment of the present application, by adding a bypass channel, in the circulation operation mode, the target opening of the bypass valve 600 is determined according to the target power of the nuclear reactor system and the target temperature difference between the cold and hot sections, and then the bypass valve 600 is controlled to open to the target opening, thereby controlling the flow of the coolant circulation loop, avoiding excessive resistance in the coolant circulation loop, and improving the cooling performance of the nuclear reactor.

[0068] In the event that the main pump 300 is shut down voluntarily or due to a fault, the nuclear reactor system can maintain a high power and continue to generate electricity by switching from forced flow operation to natural circulation operation. When the fault is eliminated, the nuclear reactor system can be switched from natural circulation operation to forced flow, avoiding shutdown of the nuclear reactor system and improving economic efficiency.

[0069] In step S100, the nuclear reactor system may be any one of a pressurized water reactor, a liquid metal fast reactor, and the like.

[0070] The above-mentioned operating status information may be any information that can reflect the operating status of the nuclear reactor system. Specifically, the operating status information may include at least one of the main pump start-stop information, main pump speed information, and the like.

[0071] The above-mentioned acquisition of the operating status information of the nuclear reactor system can be achieved by providing an operating status acquisition device (such as a sensor) in the nuclear reactor system, and collecting the operating status information through the operating status acquisition device. For example, a speed sensor can be provided on the main pump to measure the main pump speed and obtain the operating status information.

[0072] The operating status information of the nuclear reactor system is used to indicate the operating mode of the nuclear reactor system. The operating modes of the nuclear reactor system include a first operating mode and a second operating mode. The first operating mode is an operating mode in which the nuclear reactor system operates in natural circulation, and the second operating mode is an operating mode in which the nuclear reactor system operates in forced flow. By obtaining the operating status information of the nuclear reactor system, the operating mode of the nuclear reactor system can be determined based on the operating status information.

[0073] In step S200, if the nuclear reactor system is in the first operation mode, since the main pump 300 stops running, the flow resistance of the main pump passage greatly increases, the coolant does not flow through the main pump passage with high resistance, but flows through the bypass passage, thereby establishing a natural circulation flow. The driving pressure head of the coolant circulation loop is derived from the temperature difference between the cold and hot sections of the coolant circulation loop, which is used to overcome the loop resistance, and there is an approximate proportional relationship between the temperature difference between the cold and hot sections and the loop resistance. The relationship between the power of the nuclear reactor system and the temperature difference between the cold and hot sections is as follows:

[0074] ΔT d =k×Q 2 ;

[0075] P=C×ΔT d ×Q;

[0076] Wherein, ΔTd is the temperature difference between the cold and hot sections, Q is the flow rate of the bypass passage, k is the opening degree coefficient of the bypass valve 600, which is determined through debugging stage experiments, and C is the specific heat capacity of the coolant.

[0077] The target power of the nuclear reactor system is the power expected to be reached by the nuclear reactor system in the first operation mode, and the target temperature difference between the cold and hot sections is the temperature difference between the cold and hot sections corresponding to the target power. By obtaining the target power of the nuclear reactor system and the target temperature difference between the cold and hot sections, the target flow rate of the bypass passage is determined, so as to control the flow rate of the bypass passage, so that the power of the nuclear reactor system reaches the target power, and the temperature difference between the cold and hot sections reaches the target temperature difference between the cold and hot sections.

[0078] In the above step S300, controlling the opening degree of the bypass valve 600 determines the flow rate of the bypass passage, so according to the target power and the target temperature difference between the cold and hot sections, the target opening degree corresponding to the target flow rate of the bypass passage is determined.

[0079] In the above step S400, the bypass valve 600 is controlled to open to the target opening degree, so that the flow rate of the bypass passage reaches the target flow rate, that is, the cooling performance of the nuclear reactor system meets the requirement of executing the target power and the target temperature difference between the cold and hot sections.

[0080] In some embodiments of the present application, as Figure 2As shown, the nuclear reactor system comprises a reactor core 100, a steam generator 200, a main pump 300, a steam turbine 400 and a feedwater system 500. A first outlet of the steam generator 200 is connected to an inlet of the reactor core 100 through a main pump passage, and the main pump 300 is arranged on the main pump passage. A first outlet of the steam generator 200 is connected to an inlet of the reactor core 100 through a bypass passage, and the bypass passage is parallel to the main pump passage, and a bypass valve 600 is arranged on the bypass passage. An outlet of the reactor core 100 is connected to a first inlet of the steam generator 200. An outlet of the feedwater system 500 is connected to a second inlet of the steam generator 200, a second outlet of the steam generator 200 is connected to an inlet of the steam turbine 400, and an outlet of the steam turbine 400 is connected to an inlet of the feedwater system 500.

[0081] In the embodiment, the coolant enters the reactor core 100 through the main pump passage or the bypass passage to absorb heat and cool the reactor core 100, and the coolant after absorbing heat flows into the steam generator 200. The feedwater system 500 delivers water to the steam generator 200, and the steam generator 200 heats the water by using the heat provided by the coolant to generate steam, which is delivered to the steam turbine 400 to drive the blades of the steam turbine 400 to rotate and convert thermal energy into mechanical energy to generate electricity. The exhaust steam discharged from the steam turbine 400 is cooled to liquid water and then input to the feedwater system 500. After the coolant flows out of the steam generator 200, it enters the reactor core 100 through the main pump passage or the bypass passage to complete the cycle.

[0082] In some embodiments of the present application, a thermometer is arranged at the core inlet and outlet of the reactor core 100 to measure the coolant temperature at the core inlet to obtain the cold section temperature and measure the coolant temperature at the outlet to obtain the hot section temperature, so as to obtain the cold-hot section temperature difference according to the cold section temperature and the hot section temperature.

[0083] In some embodiments of the present application, the number of main pumps 300 arranged on the main pump passage is not limited, and the number of main pumps 300 can be set according to actual application requirements, for example, the number of main pumps 300 arranged on the main pump passage is set to 1, 2 or 5.

[0084] In some embodiments of the present application, the bypass valve 600 can also be adjusted in a manual mode. In the manual mode, an operator directly issues an opening or closing command and sets a valve opening requirement value.

[0085] In some embodiments of the present application, the step S300 of "determining the target opening of the bypass valve 600 according to the target power and the cold-hot section target temperature difference" is further described, and the step S300 comprises:

[0086] Step S310: Obtain a power-temperature difference-opening degree calibration relationship, the power-temperature difference-opening degree calibration relationship comprising a mapping relationship of a plurality of powers of the nuclear reactor system, a plurality of temperature differences between hot and cold sections, and a plurality of opening degree calibration values of the bypass valve 600;

[0087] Step S320: Based on the power-temperature difference-opening degree calibration relationship, determine the opening degree calibration value that has a mapping relationship with the target power and the target temperature difference between hot and cold sections as the target opening degree.

[0088] In the embodiment, since there is a certain deviation between the theoretically calculated operating parameters of the nuclear reactor system and the actual operating parameters of the nuclear reactor system, a series of natural circulation condition calibration experiments are carried out in the debugging stage of the nuclear reactor system. At m different reactor powers, by adjusting the opening degree (n different opening degrees) of the bypass valve 600, the flow rate of the bypass passage can be changed, and thus the temperature difference between hot and cold sections of the nuclear reactor system changes. Thus, the temperature difference between hot and cold sections at different nuclear reactor system powers and different bypass valve 600 opening degrees can be obtained, and the flow rate and opening degree coefficient of the bypass passage are calculated according to the above-mentioned relationship between the power of the nuclear reactor system and the temperature difference between hot and cold sections. Thus, a plurality of sets of data of the power of the nuclear reactor system, the temperature difference between hot and cold sections, the opening degree of the bypass valve 600, the flow rate of the bypass passage, and the opening degree coefficient are obtained, i.e., the power-temperature difference-opening degree calibration relationship is obtained, and the power-temperature difference-opening degree calibration relationship is shown in Table 1. Based on the power-temperature difference-opening degree calibration relationship, the opening degree calibration value that has a mapping relationship with the target power and the target temperature difference between hot and cold sections can be determined as the target opening degree.

[0089] Table 1. Power-temperature difference-opening degree calibration relationship table

[0090]

[0091] In some embodiments of the present application, after "obtaining the target power of the nuclear reactor system" in step S200, the method further comprises:

[0092] Step S210: Obtain the real-time power of the nuclear reactor system;

[0093] Step S220: Control the control rod action of the nuclear reactor system according to the real-time power and the target power.

[0094] In the embodiment, by obtaining the real-time power of the nuclear reactor system, a power deviation signal is obtained according to the real-time power and the target power, and the control rod action of the nuclear reactor system is controlled based on the power deviation signal, so that the real-time power reaches the target power.

[0095] In some embodiments of the present application, as Figure 3As shown, the power control of the nuclear reactor system comprises a temperature channel and a power channel. The temperature channel is used to calculate the difference between the coolant average temperature measurement and the coolant average temperature set value, and then pass through a PI controller to obtain a temperature deviation signal. The coolant average temperature set value is obtained according to the target power.

[0096] The power channel is used to calculate the difference between the real-time power and the target power, and then pass through a PI controller to obtain a power deviation signal. The target power is the power load of the steam turbine 400 in the second operation mode, and is a preset load in the first operation mode. The power deviation signal and the temperature deviation signal are added to obtain a total deviation signal, which is sent to a rod speed program to generate a control rod action signal.

[0097] When the nuclear reactor system operates in the first operation mode, the main pump 300 is normally put into operation, and both the power channel and the temperature channel of the power control module are effective. When the nuclear reactor system operates in the second operation mode, the main pump 300 is not put into operation, only the power channel of the power control module is effective, the target power is adjusted to the preset load, and the temperature channel is not effective; when the nuclear reactor system is switched from the first operation mode to the second operation mode, the target power of the power channel is restored to the power load of the steam turbine 400, and the temperature channel is restored to be effective.

[0098] In step S210, a neutron flux measurement channel is arranged outside the reactor core 100, and a neutron detector is arranged in the measurement channel to detect the neutron flux level. The signal of the measurement channel is calculated to obtain the real-time power of the nuclear reactor system.

[0099] In some embodiments of the present application, the method further comprises:

[0100] In step S230, a coolant average temperature measurement is obtained.

[0101] In step S240, if the coolant average temperature measurement is lower than a first temperature threshold, the control rod insertion action is blocked until the coolant temperature rises to be higher than the first temperature threshold to be unlocked.

[0102] In step S250, if the coolant average temperature measurement is higher than a second temperature threshold, the control rod extraction action is blocked until the coolant temperature decreases to be lower than the second temperature threshold to be unlocked.

[0103] In the embodiment, during the switching process of the first operation mode and the second operation mode of the nuclear reactor system, the coolant average temperature should not exceed the specified limit value. By setting a control rod blocking signal, the control rod action is blocked according to the coolant average temperature measurement, so that the coolant average temperature is ensured to be between the first temperature threshold and the second temperature threshold.

[0104] In some embodiments of the present application, as Figure 4As shown, the method further comprises:

[0105] Step S500: obtaining a preset load of the turbine 400 of the nuclear reactor system;

[0106] Step S510: controlling the turbine 400 to operate at the preset load.

[0107] In the embodiment, when the nuclear reactor system operates in the first operation mode, the preset load of the turbine 400 of the nuclear reactor system is obtained, and the preset load is determined according to the minimum stable power generation power of the nuclear reactor system. The turbine 400 is controlled to operate at a lower preset load.

[0108] In some embodiments of the present application, if the nuclear reactor system is switched to operate in the second operation mode, the turbine 400 is controlled to operate at the power consumption load.

[0109] In some embodiments of the present application, as shown in Figure 4 As shown, the method further comprises:

[0110] Step S600: controlling the turbine 400 of the nuclear reactor system to operate at a preset first inlet steam pressure;

[0111] Step S610: after a preset first time, controlling the turbine 400 to operate at a preset second inlet steam pressure, the second inlet steam pressure being greater than the first inlet steam pressure, the first inlet steam pressure being a preset inlet steam pressure of the turbine 400 in the second operation mode, and the second operation mode being an operation mode in which the nuclear reactor system operates in forced flow.

[0112] In the embodiment, the turbine 400 is first operated at a reduced pressure for a period of time at the first inlet steam pressure, and then restored to the second inlet steam pressure after the temperature is increased, so as to avoid the steam-water mixture in the turbine 400 due to insufficient superheat degree of the steam, which affects the working efficiency of the turbine 400, and the turbine 400 failure caused by cavitation.

[0113] In some embodiments of the present application, a pressure transmitter is arranged at the inlet of the turbine 400, for measuring the inlet steam pressure of the turbine 400.

[0114] In some embodiments of the present application, as shown in Figure 5 As shown, the method further comprises:

[0115] Step S700: obtaining a real-time steam pressure of the steam generator 200 of the nuclear reactor system;

[0116] Step S710: controlling the opening degree of the feedwater valve of the steam generator 200 according to the real-time steam pressure and the preset target steam pressure, the target steam pressure gradually decreasing from the first steam pressure to the second steam pressure and then gradually increasing to the first steam pressure, the first steam pressure being the preset steam pressure setting value of the steam generator 200 in the second operation mode.

[0117] In the embodiment, when the nuclear reactor system is in the second operation mode, the steam generator 200 operates at the preset first steam pressure as the target steam pressure. When the nuclear reactor system switches to the first operation mode, the target steam pressure in the steam generator 200 gradually decreases from the first steam pressure to the second steam pressure and then gradually increases to the first steam pressure. According to the real-time steam pressure and the preset target steam pressure, the opening degree of the feedwater valve of the steam generator 200 is controlled by the PI controller, so that the steam pressure is first decreased and then increased after the superheat degree is increased. This can avoid insufficient superheat degree of the steam, which causes mixing of steam and water in the steam turbine 400, affects the working efficiency of the steam turbine 400, and causes failure of the steam turbine 400 due to cavitation.

[0118] In some embodiments of the present application, a pressure sensor is arranged at the second outlet of the steam generator 200 to measure the real-time steam pressure.

[0119] In some embodiments of the present application, the method further comprises:

[0120] Step S800: obtaining a feedwater flow reference value, the feedwater flow reference value being calculated from a theoretical feedwater flow value corresponding to the target power, a cold-hot section target temperature difference, and a real-time cold-hot section temperature difference value;

[0121] Step S810: controlling the opening degree of the feedwater valve of the steam generator 200 according to the feedwater flow reference value, the real-time steam pressure, and the target steam pressure.

[0122] In the first operation mode, the nuclear reactor system, due to the influence of the coolant circulation loop resistance, the theoretical calculation of the operation parameters and the actual operation state of the nuclear reactor system may have a large deviation. When the cold-hot section temperature difference is too large, there is a risk that the cold-hot section temperature difference exceeds the temperature difference limit, and the feedwater flow of the steam generator 200 needs to be reduced to reduce the cold-hot section temperature difference. When the cold-hot section temperature difference is too small, it may lead to insufficient natural circulation driving force, and the natural circulation flow cannot be established, and the feedwater flow of the steam generator 200 needs to be increased to increase the cold-hot section temperature difference. Therefore, by obtaining the feedwater flow reference value, according to the feedwater flow reference value, the real-time steam pressure and the target steam pressure, controlling the opening of the feedwater valve of the steam generator 200, and adjusting the opening of the feedwater valve, the feedwater flow of the steam generator 200 can be controlled. When the cold-hot section temperature difference is too large, the feedwater flow of the steam generator 200 is reduced to reduce the cold-hot section temperature difference, so as to avoid that the cold-hot section temperature difference exceeds the temperature difference limit, and when the cold-hot section temperature difference is too small, the feedwater flow of the steam generator 200 is increased to increase the cold-hot section temperature difference, so as to avoid insufficient natural circulation driving force.

[0123] In some embodiments of the present application, flow meters are arranged at the second inlet and the second outlet of the steam generator 200 respectively to measure the feedwater flow of the steam generator 200.

[0124] In some embodiments of the present application, the step S800 of "obtaining the feedwater flow reference value" is further described, and the step S800 includes:

[0125] Step S801: dividing the target cold-hot section temperature difference by the real-time cold-hot section temperature difference to obtain an intermediate temperature difference value;

[0126] Step S802: multiplying the intermediate temperature difference value by the theoretical feedwater flow to obtain the feedwater flow reference value.

[0127] In the present embodiment, the target cold-hot section temperature difference is divided by the real-time cold-hot section temperature difference to obtain an intermediate temperature difference value, and the intermediate temperature difference value is multiplied by the theoretical feedwater flow to obtain the feedwater flow reference value. For example, the feedwater flow reference value is calculated by the following formula:

[0128]

[0129] Wherein, P1 is the target power, Q N is the theoretical feedwater flow corresponding to the target power, the unit is kg / s, ΔT is the target cold-hot section temperature difference, the unit is ℃, T h -T c is the real-time cold-hot section temperature difference, the unit is ℃.

[0130] In some embodiments of the present application, to avoid the water flow reference value changing too much during mode switching, the water flow reference value is limited in a certain range, for example, the water flow reference value is limited between 80% and 120% of the water flow theoretical value.

[0131] In some embodiments of the present application, the step of "obtaining the operation state information of the nuclear reactor system" in step S100 is further described, including:

[0132] Step S101: obtaining the real-time rotating speed of the main pump 300;

[0133] Step S102: obtaining the operation state information according to the real-time rotating speed and the preset rotating speed threshold.

[0134] In the present embodiment, the real-time rotating speed of the main pump 300 is sent to a threshold comparator, and if it is lower than the preset rotating speed threshold, a first operation mode information is generated to indicate that the nuclear reactor system operates in the operation mode of natural circulation, otherwise a second operation mode signal is generated to indicate that the nuclear reactor system operates in the operation mode of forced flow operation.

[0135] In addition, the present application provides a control device 700 of a nuclear reactor system, wherein a coolant circulation loop of the nuclear reactor system includes a main pump passage and a bypass passage arranged in parallel with the main pump passage, and a bypass valve 600 is arranged on the bypass passage, as shown in Figure 6 The control device 700 includes:

[0136] A first obtaining module 710 is configured to obtain operation state information of the nuclear reactor system;

[0137] A second obtaining module 720 is configured to, if it is determined according to the operation state information that the nuclear reactor system operates in a first operation mode, obtain a target power of the nuclear reactor system and a cold-hot section target temperature difference of the coolant circulation loop, wherein the first operation mode is an operation mode in which the nuclear reactor system performs natural circulation.

[0138] An opening degree determining module 730 is configured to determine a target opening degree of the bypass valve 600 according to the target power and the cold-hot section target temperature difference.

[0139] A valve control module 740 is configured to control the bypass valve 600 to open to the target opening degree.

[0140] The control device 700 provided by the present application can realize each process realized by the method embodiments and achieve the same beneficial effects. To avoid repetition, details are not described here.

[0141] In some embodiments of the present application, the opening degree determining module 730 includes:

[0142] The relationship obtaining submodule is configured to obtain a power-temperature difference-opening degree calibration relationship, the power-temperature difference-opening degree calibration relationship comprising a mapping relationship among a plurality of powers, a plurality of cold-heat section temperature differences, and a plurality of opening degree calibration values of the bypass valve 600 of the nuclear reactor system.

[0143] The opening degree determining submodule is configured to determine, based on the power-temperature difference-opening degree calibration relationship, an opening degree calibration value that has a mapping relationship with the target power and the cold-heat section target temperature difference as the target opening degree.

[0144] In some embodiments of the present application, the control device 700 further comprises:

[0145] The third obtaining module is configured to obtain a real-time power of the nuclear reactor system.

[0146] The control rod control module is configured to control a control rod of the nuclear reactor system to act according to the real-time power and the target power.

[0147] In some embodiments of the present application, the control device 700 further comprises:

[0148] The steam turbine first control module is configured to control the steam turbine 400 of the nuclear reactor system to operate at a preset first inlet steam pressure.

[0149] The steam turbine second control module is configured to control the steam turbine 400 to operate at a preset second inlet steam pressure after a preset first time, the second inlet steam pressure being greater than the first inlet steam pressure, the first inlet steam pressure being a preset inlet steam pressure of the steam turbine 400 in a second operation mode, and the second operation mode being an operation mode in which the nuclear reactor system is forced to operate at a flow rate.

[0150] In some embodiments of the present application, the control device 700 further comprises:

[0151] The fourth obtaining module is configured to obtain a real-time steam pressure of the steam generator 200 of the nuclear reactor system.

[0152] The steam generator control module is configured to control an opening degree of a feedwater valve of the steam generator 200 according to the real-time steam pressure and a preset target steam pressure, the target steam pressure gradually decreasing from a first steam pressure to a second steam pressure and then gradually increasing to the first steam pressure, the first steam pressure being a preset steam pressure setting value of the steam generator 200 in a second operation mode.

[0153] In some embodiments of the present application, the control device 700 further comprises:

[0154] The fifth obtaining module is configured to obtain a feedwater flow reference value, the feedwater flow reference value being calculated from a feedwater flow theoretical value corresponding to the target power, the cold-heat section target temperature difference, and a real-time value of the cold-heat section temperature difference.

[0155] The steam generator control submodule is configured to control the opening degree of the feedwater valve of the steam generator 200 according to the feedwater flow reference value, the real-time steam pressure and the target steam pressure.

[0156] In some embodiments of the present application, the fifth obtaining module comprises:

[0157] The first calculating submodule is configured to divide the cold-hot section target temperature difference by the real-time cold-hot section temperature difference to obtain a temperature difference intermediate value.

[0158] The second calculating submodule is configured to multiply the temperature difference intermediate value by the feedwater flow theoretical value to obtain the feedwater flow reference value.

[0159] In some embodiments of the present application, the first obtaining module comprises:

[0160] The rotating speed obtaining submodule is configured to obtain the real-time rotating speed of the main pump 300.

[0161] The running state judging submodule is configured to obtain the running state information according to the real-time rotating speed and a preset rotating speed threshold.

[0162] In addition, an electronic device is provided in an embodiment of the present application, and the electronic device implements the control method of the nuclear reactor system as described above when executed.

[0163] In addition, an electronic device is provided in an embodiment of the present application, and the electronic device implements the control method of the nuclear reactor system as described above when executed.

[0164] The computer readable storage medium provided in the embodiments of the present application can implement each process of the above-mentioned method embodiments and achieve the same beneficial effects, and thus details are not repeated here.

[0165] In addition, an electronic device 800 is disclosed in an embodiment of the present application, as shown in the accompanying drawings, comprising: Figure 7

[0166] at least one processor 810;

[0167] at least one memory 820 configured to store at least one program;

[0168] When the at least one program is executed by the at least one processor 810, the control method of the nuclear reactor system as described above is implemented.

[0169] The electronic device 800 provided in the embodiments of the present application can implement each process of the above-mentioned method embodiments and achieve the same beneficial effects, and thus details are not repeated here.

[0170] ​As will be appreciated by one of ordinary skill in the art, all or some steps, systems of the above-disclosed methods can be implemented as software, firmware, hardware, or suitable combinations thereof. Some or all of the physical components can be implemented as software executed by a processor, such as a central processing unit, a digital signal processor, or a microprocessor, or as hardware, or as an integrated circuit, such as an application-specific integrated circuit. Such software can be distributed on computer readable media, which can comprise computer storage media (or non-transitory media), and communication media (or transitory media). As is well known to those of ordinary skill in the art, computer storage media includes all computer-readable media in which data, computer executable instructions, or other computer readable data, are permanently, non-transitorily, or semi-permanently stored or maintained. Computer storage media includes, but is not limited to, volatile and non-volatile, removable and non-removable media implemented in any method or technology for storage of information such as computer readable instructions, data structures, program modules or other data. Computer storage media includes, but is not limited to, RAM, ROM, EEPROM, flash memory or other memory technology, CD-ROM, digital versatile disks (DVD) or other optical disk storage, magnetic cassettes, magnetic tape, magnetic disk storage or other magnetic storage devices, or any other medium which can be used to store the desired information and which can be accessed by a computer. Further, as is well known to those of ordinary skill in the art, communication media typically embodies computer readable instructions, data structures, program modules or other data in a modulated data signal such as a carrier wave or other transport mechanism and includes any information delivery media. In the foregoing specification, the concepts have been described with reference to specific embodiments. However, one of ordinary skill in the art appreciates that various modifications and changes can be made without departing from the scope of the application as set forth in the claims below. Accordingly, the specification is to be regarded in an illustrative rather than a restrictive sense.

[0171] The above detailed description has shown, by way of example, various features of embodiments of the application. It is specifically intended that changes and modifications not specifically described herein can be made within the scope of the following claims.

Claims

1. A control method for a nuclear reactor system, characterized in that: The coolant circulation loop of the nuclear reactor system includes a main pump channel and a bypass channel arranged in parallel with the main pump channel, and the bypass channel is provided with a bypass valve. The method includes: Acquiring operating status information of the nuclear reactor system; If it is determined according to the operating state information that the nuclear reactor system is operating in a first operating mode, obtaining a target power of the nuclear reactor system and a target temperature difference between the cold and hot sections of the coolant circulation loop, wherein the first operating mode is an operating mode in which the nuclear reactor system performs natural circulation; Determining a target opening of the bypass valve according to the target power and the target temperature difference between the hot and cold sections; The bypass valve is controlled to open to the target opening.

2. The control method of a nuclear reactor system according to claim 1, characterized in that: Determining the target opening of the bypass valve according to the target power and the target temperature difference between the hot and cold sections includes: Acquiring a power-temperature difference opening calibration relationship, wherein the power-temperature difference opening calibration relationship includes a mapping relationship between multiple powers of the nuclear reactor system, multiple cold and hot section temperature differences, and multiple opening calibration values ​​of the bypass valve; Based on the power-temperature difference opening calibration relationship, an opening calibration value having a mapping relationship with the target power and the target temperature difference between the hot and cold sections is determined as the target opening.

3. The control method of a nuclear reactor system according to claim 1, wherein: After obtaining the target power of the nuclear reactor system, the method further includes: obtaining the real-time power of the nuclear reactor system; According to the real-time power and the target power, the control rod movement of the nuclear reactor system is controlled.

4. The control method of a nuclear reactor system according to claim 1, wherein: The method further comprises: controlling the steam turbine of the nuclear reactor system to operate at a preset first steam inlet pressure; After a preset first time, the steam turbine is controlled to operate at a preset second steam inlet pressure, wherein the second steam inlet pressure is greater than the first steam inlet pressure, and the first steam inlet pressure is the preset steam inlet pressure of the steam turbine in a second operating mode, and the second operating mode is an operating mode in which the nuclear reactor system performs forced flow operation.

5. The nuclear reactor system control method according to claim 1, wherein: The method further comprises: obtaining a preset load of a steam turbine of the nuclear reactor system; The steam turbine is controlled to operate at the preset load.

6. The control method of a nuclear reactor system according to claim 1, characterized in that: The method further comprises: obtaining a real-time steam pressure of a steam generator of the nuclear reactor system; The opening of the water supply valve of the steam generator is controlled according to the real-time steam pressure and the preset target steam pressure. The target steam pressure gradually decreases from the first steam pressure to the second steam pressure, and then gradually increases to the first steam pressure. The first steam pressure is the preset steam pressure setting value of the steam generator in the second operating mode.

7. The control method of a nuclear reactor system according to claim 6, characterized in that: The method further comprises: Obtaining a water flow reference value, wherein the water flow reference value is calculated based on a theoretical water flow value corresponding to the target power, the target temperature difference between the hot and cold sections, and a real-time temperature difference between the hot and cold sections; The opening of the feedwater valve of the steam generator is controlled according to the feedwater flow reference value, the real-time steam pressure and the target steam pressure.

8. The control method of a nuclear reactor system according to claim 7, characterized in that: The obtaining of the water supply flow reference value includes: Divide the target temperature difference between the hot and cold sections by the real-time temperature difference between the hot and cold sections to obtain an intermediate temperature difference value; The water supply flow reference value is obtained by multiplying the intermediate temperature difference value by the water supply flow theoretical value.

9. The control method of a nuclear reactor system according to claim 1, characterized in that: The obtaining of the operating status information of the nuclear reactor system includes: Obtaining the real-time rotation speed of the main pump on the main pump channel; The operating status information is obtained according to the real-time rotation speed and a preset rotation speed threshold.

10. A control device for a nuclear reactor system, characterized in that: The coolant circulation loop of the nuclear reactor system includes a main pump channel and a bypass channel arranged in parallel with the main pump channel, and a bypass valve is provided on the bypass channel. The device includes: A first acquisition module is used to obtain the operating status information of the nuclear reactor system; a second acquisition module, configured to, if it is determined according to the operating status information that the nuclear reactor system is operating in a first operating mode, acquire a target power of the nuclear reactor system and a target temperature difference between the cold and hot sections of the coolant circulation loop, wherein the first operating mode is an operating mode in which the nuclear reactor system performs natural circulation; an opening determination module, configured to determine a target opening of the bypass valve according to the target power and the target temperature difference between the hot and cold sections; The valve control module is used to control the bypass valve to open to the target opening.

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