Reactor core control methods, systems, storage media, and electronic equipment for diversified nuclear energy utilization

Abstract

This invention relates to a reactor core control method, system, storage medium, and electronic equipment for diversified nuclear energy utilization. In extraction mode, the following steps are performed: acquiring the influencing parameters under extraction mode; adjusting the average temperature control of the average temperature control system based on the extraction load and the turbine's first-stage pressure; adjusting the core power control of the core power control system based on the extraction load and the turbine load reference value in the secondary loop; adjusting the parameter control of the steam generator water level control system based on the extraction load, turbine's first-stage pressure, GCT valve opening, steam header pressure, and ADG valve opening; and adjusting the temperature control of the turbine bypass discharge control system based on the extraction load and turbine's first-stage pressure. This invention can solve the basic control scheme of the reactor core after diversified nuclear energy utilization, can stably control the reactor core power, improve the utilization efficiency of nuclear energy, and greatly enhance the economic efficiency of the power plant.

Description

Technical Field

[0001] This invention relates to the technical field of nuclear energy utilization in nuclear power plants, and more specifically, to a reactor core control method, system, storage medium, and electronic equipment for diversified utilization of nuclear energy. Background Technology

[0002] In current mainstream pressurized water reactor nuclear power plants, the reactor serves as the primary heat source for the primary loop. The fluids in the primary loop are heated and then exchanged through a steam generator to produce high-temperature, high-pressure steam. This steam drives the turbine to generate electricity, ultimately converting nuclear energy into electrical energy. When not all the high-temperature, high-pressure steam generated by the steam generator is used for power generation—for example, by extracting steam originally intended for power generation for other industrial production or urban heating—this achieves comprehensive utilization of nuclear energy. However, if some of the steam originally intended for power generation is extracted for other purposes, it will affect the load balance between the primary and secondary loops of the nuclear power plant. The essence of reactor control in a nuclear power plant is to consistently maintain the load balance between the primary and secondary loops.

[0003] Different types of nuclear power plants have different control schemes for their reactor cores, and the impact of different reactor control modes on the secondary loop when steam is extracted and used for other purposes varies.

[0004] A nuclear power plant has designed a method for measuring the secondary loop load in nuclear heating mode. This method involves measuring and summing the turbine power and heating load to form the total secondary loop load. The primary loop power is then regulated using this total secondary loop load. However, this scheme is only suitable for reactor core control systems that use only the turbine's first-stage pressure signal as the interface signal between the primary and secondary loops. In other words, the existing technology is applicable to the MSHIM mode of the AP1000 reactor type. For CPR reactor types and the more complex MODE-G core control mode of the M310 unit, the existing technology cannot solve the reactor core control problem. Furthermore, this scheme only considers steam extraction for heating and is not universally applicable to other scenarios, such as steam used for other industrial purposes. Summary of the Invention

[0005] The technical problem to be solved by the present invention is to provide a reactor core control method, system, storage medium and electronic equipment for diversified utilization of nuclear energy, addressing the problems existing in the prior art.

[0006] The technical solution adopted by this invention to solve its technical problem is: to construct a reactor core control method for diversified utilization of nuclear energy, and to perform the following steps in steam extraction mode:

[0007] Obtain the influencing parameters under the extraction steam mode; the influencing parameters include: extraction steam load, turbine first-stage pressure, turbine load reference value of the secondary loop, GCT valve opening, steam header pressure, and ADG valve opening;

[0008] The average temperature control of the average temperature control system is adjusted according to the extraction steam load and the first-stage pressure of the steam turbine.

[0009] The core power control of the core power control system is adjusted according to the extraction steam load and the turbine load reference value of the secondary loop.

[0010] The parameters of the steam generator water level control system are adjusted according to the extraction steam load, the first stage pressure of the steam turbine, the opening degree of the GCT valve, the steam header pressure, and the opening degree of the ADG valve.

[0011] The temperature control of the turbine bypass emission control system is adjusted according to the extraction steam load and the turbine first-stage pressure.

[0012] In the reactor core control method for diversified utilization of nuclear energy described in this invention, the average temperature control system that adjusts the average temperature based on the extraction steam load and the first-stage pressure of the steam turbine includes:

[0013] Based on the extraction steam load, the first-stage pressure of the steam turbine is corrected to obtain the second loop load characterization signal;

[0014] The total power load of the two circuits is calculated based on the load characterization signal of the two circuits and the total load calculation logic of the two circuits.

[0015] The core average temperature control of the average temperature control system is performed based on the total power load of the two loops.

[0016] In the reactor core control method for diversified utilization of nuclear energy described in this invention, the core power control of adjusting the core power control system according to the extraction steam load and the turbine load reference value of the secondary loop includes:

[0017] Obtain the operating mode of the steam turbine;

[0018] If the turbine is in normal operating mode, the core power control of the core power control system is adjusted according to the extraction steam load and the turbine load reference value of the secondary loop.

[0019] If the turbine is operating in a limited load mode, the core power control of the core power control system is adjusted according to the extraction steam load, the turbine load reference value of the secondary loop, and in combination with the steam flow limit and the turbine first-stage pressure limit.

[0020] In the reactor core control method for diversified utilization of nuclear energy described in this invention, if the turbine is in normal operating mode, the core power control of the core power control system, which adjusts the core power control system according to the extraction steam load and the turbine load reference value of the secondary loop, includes:

[0021] If the turbine is in normal operating mode, the extraction load is superimposed with the turbine load reference value of the secondary loop to obtain the total load characterization value of the secondary loop.

[0022] The core power control of the core power control system is adjusted based on the total load characterization value of the two loops.

[0023] In the reactor core control method for diversified utilization of nuclear energy described in this invention, if the turbine's operating mode is a load-limited operating mode, then adjusting the core power control of the core power control system based on the extraction steam load, the turbine load reference value of the secondary loop, and in combination with the steam flow limit and the turbine's first-stage pressure limit includes:

[0024] If the turbine is operating in a load-limited mode, the extraction load is superimposed with the turbine load reference value of the secondary loop to obtain the total load characterization value of the secondary loop.

[0025] The steam flow limit is compared with the turbine first-stage pressure limit to obtain a reference value for restricted load operation.

[0026] The core power control of the core power control system is adjusted based on the total load characterization value of the two loops and the limit load operation reference value.

[0027] In the reactor core control method for diversified utilization of nuclear energy described in this invention, the core power control of adjusting the core power control system based on the total load characterization value of the secondary loop and the limiting load operation reference value includes:

[0028] The total load characterization value of the two circuits is compared with the restricted load operation reference value, and the smaller value between the two is obtained.

[0029] The core power control of the core power control system is adjusted according to the smaller value.

[0030] In the reactor core control method for diversified utilization of nuclear energy described in this invention, the parameter control of adjusting the steam generator water level control system based on the extraction steam load, the turbine first-stage pressure, the GCT valve opening, the steam header pressure, and the ADG valve opening includes:

[0031] Based on the extraction steam load, the first-stage pressure of the steam turbine is corrected to obtain the second loop load characterization signal;

[0032] The parameters of the steam generator water level control system are adjusted based on the load characterization signal of the second loop, the opening degree of the GCT valve, the steam header pressure, and the opening degree of the ADG valve.

[0033] In the reactor core control method for diversified utilization of nuclear energy described in this invention, the temperature control of adjusting the turbine bypass emission control system according to the extraction steam load and the turbine first-stage pressure includes:

[0034] Based on the extraction steam load, the first-stage pressure of the steam turbine is corrected to obtain the second loop load characterization signal;

[0035] Adjust the temperature control of the turbine bypass emission control system based on the secondary loop load characterization signal.

[0036] In the reactor core control method for diversified utilization of nuclear energy described in this invention, the temperature control of adjusting the turbine bypass emission control system based on the secondary loop load characterization signal includes:

[0037] The reference average temperature is obtained by calculating based on the dual-loop load characterization signal.

[0038] The temperature deviation is obtained by subtracting the reference average temperature from the measured average temperature.

[0039] The target control signal is determined based on the temperature deviation.

[0040] Temperature control of the turbine bypass emission control system is performed according to the target control signal.

[0041] In the reactor core control method for diversified utilization of nuclear energy described in this invention, the method further includes:

[0042] Based on the extraction steam load, the first-stage pressure of the steam turbine is corrected to obtain the second loop load characterization signal;

[0043] The interlocking of the regulating valves of the turbine bypass emission control system is adjusted based on the load characterization signal of the second loop.

[0044] The present invention also provides a reactor core control system for diversified nuclear energy utilization, comprising:

[0045] The influencing parameter acquisition unit is used to acquire the influencing parameters under the extraction steam mode; the influencing parameters include: extraction steam load, turbine first-stage pressure, turbine load reference value of the secondary loop, GCT valve opening, steam header pressure, and ADG valve opening;

[0046] An average temperature control adjustment unit is used to adjust the average temperature control of the average temperature control system according to the extraction steam load and the first stage pressure of the steam turbine.

[0047] The core power control adjustment unit is used to adjust the core power control of the core power control system according to the extraction steam load and the turbine load reference value of the secondary loop.

[0048] The steam generator water level control and adjustment unit is used to adjust the parameters of the steam generator water level control system according to the extraction steam load, the first stage pressure of the steam turbine, the opening degree of the GCT valve, the steam header pressure, and the opening degree of the ADG valve.

[0049] The bypass discharge system control adjustment unit is used to adjust the temperature control of the turbine bypass discharge control system according to the extraction steam load and the turbine first-stage pressure.

[0050] The present invention also provides a storage medium storing a computer program adapted for loading by a processor to execute the steps of the reactor core control method for diversified nuclear energy utilization as described above.

[0051] The present invention also provides an electronic device, including a memory and a processor, wherein the memory stores a computer program, and the processor executes the steps of the reactor core control method for diversified utilization of nuclear energy as described above by calling the computer program stored in the memory.

[0052] The reactor core control method, system, storage medium, and electronic equipment for diversified nuclear energy utilization of the present invention have the following beneficial effects: In extraction mode, the following steps are performed: acquiring the influencing parameters under extraction mode; adjusting the average temperature control of the average temperature control system according to the extraction load and the turbine first-stage pressure; adjusting the core power control of the core power control system according to the extraction load and the turbine load reference value of the secondary loop; adjusting the parameter control of the steam generator water level control system according to the extraction load, turbine first-stage pressure, GCT valve opening, steam header pressure, and ADG valve opening; and adjusting the temperature control of the turbine bypass discharge control system according to the extraction load and turbine first-stage pressure. The present invention can solve the basic control scheme of the reactor core after diversified nuclear energy utilization, can stably control the reactor core power, improve the utilization efficiency of nuclear energy, and greatly enhance the economic efficiency of the power plant. Attached Figure Description

[0053] The present invention will be further described below with reference to the accompanying drawings and embodiments. In the accompanying drawings:

[0054] Figure 1This is a schematic flowchart of the reactor core control method for diversified utilization of nuclear energy provided by the present invention;

[0055] Figure 2 This is a simplified diagram illustrating the principle of adjusting the average temperature control system provided by the present invention.

[0056] Figure 3 This is a simplified schematic diagram of the principle of adjusting the reactor core power control system provided by the present invention;

[0057] Figure 4 This is a simplified schematic diagram of the principle of adjusting the water level control system of a steam generator provided by the present invention;

[0058] Figure 5 This is a simplified schematic diagram of the principle of adjusting the bypass emission control system for steam turbines provided by the present invention;

[0059] Figure 6 This is a simplified diagram illustrating the principle of the interlock adjustment of the regulating valve in the turbine bypass emission control system provided by the present invention.

[0060] Figure 7 This is a schematic diagram of the reactor core control system for diversified utilization of nuclear energy provided by the present invention. Detailed Implementation

[0061] The technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.

[0062] This invention provides a reactor core control method for diversified utilization of nuclear energy. This method can solve the problem of the impact on the reactor control system during the process of turbine extraction affecting reactor matching, namely the problems of the average temperature control system, core power control system, steam generator water level control system, and turbine bypass emission control system.

[0063] Specifically, such as Figure 1 As shown, in a preferred embodiment, the reactor core control method for diversified nuclear energy utilization performs the following steps in extraction mode:

[0064] Step S101: Obtain the influence parameters under the steam extraction mode.

[0065] The influencing parameters include: extraction steam load, turbine first-stage pressure, turbine load reference value in the secondary loop, GCT valve opening, steam header pressure, and ADG valve opening. GCT refers to the turbine bypass discharge control system, and ADG refers to the feedwater deaerator system.

[0066] Step S102: Adjust the average temperature control of the average temperature control system according to the extraction steam load and the first stage pressure of the steam turbine.

[0067] In some embodiments, the average temperature control system that adjusts the average temperature based on the extraction steam load and the turbine first-stage pressure includes: correcting the turbine first-stage pressure based on the extraction steam load to obtain a secondary loop load characterization signal; calculating the total power load of the secondary loop based on the secondary loop load characterization signal and the total load calculation logic of the secondary loop; and performing core average temperature control of the average temperature control system based on the total power load of the secondary loop.

[0068] Specifically, the impact of the reactor interface signal on the core average temperature control: The original design used the turbine's first-stage pressure to characterize the secondary loop load and generate the average temperature control setpoint. Furthermore, during the unit's first up-state core physics experiment, the correlation curves between thermal power and turbine's first-stage pressure at various power platforms were calibrated through thermal balance tests. However, when turbine extraction steam is used for other purposes, the original turbine's first-stage pressure can no longer be used to characterize the secondary loop load. The impact of the extraction steam load needs to be considered before being used as the total secondary loop load (i.e., the secondary loop load characterization signal). The specific adjustment scheme is as follows: Figure 2 As shown.

[0069] Specifically, such as Figure 2 As shown, when not all the steam in the secondary loop is used for power generation, but a portion is extracted for other purposes, the turbine's first-stage pressure cannot be used to characterize the total load of the secondary loop. Instead, the turbine's first-stage pressure needs to be corrected by the extracted steam load to obtain the corrected total load of the secondary loop, i.e., the secondary loop load characterization signal. The obtained secondary loop load characterization signal is then used to participate in downstream logic control to obtain the final total power of the secondary loop, and this is used as the basis for controlling the core average temperature.

[0070] When the CGT system is in T mode, if the turbine power before the transient occurs is greater than or equal to 30% FP, the final power setting value is 30% FP; if the turbine power before the transient occurs is less than 30% FP, the final power setting value is the turbine power value before the transient. When the GCT system is in P mode, the total load of the secondary loop is calculated from the GCT steam discharge pressure setting value.

[0071] It should be noted that, Figure 2 In this process, after obtaining the load characterization signal of the second loop, the downstream logic control is the control logic in the original average temperature control system, which will not be elaborated here.

[0072] Step S103: Adjust the core power control of the core power control system according to the extraction steam load and the turbine load reference value of the secondary loop.

[0073] In some embodiments, adjusting the core power control of the core power control system based on the extraction steam load and the turbine load reference value of the secondary loop includes: obtaining the turbine's operating mode; if the turbine's operating mode is normal operating mode, then adjusting the core power control of the core power control system based on the extraction steam load and the turbine load reference value of the secondary loop.

[0074] If the turbine is operating in a limited load mode, the core power control of the core power control system is adjusted based on the extraction steam load, the turbine load reference value of the secondary loop, and in combination with the steam flow limit and the turbine first-stage pressure limit.

[0075] Specifically, if the turbine is operating in normal mode, the core power control of the core power control system, which adjusts the core power control system based on the extraction steam load and the turbine load reference value of the secondary loop, includes: if the turbine is operating in normal mode, the extraction steam load and the turbine load reference value of the secondary loop are superimposed to obtain the total load characterization value of the secondary loop; and the core power control of the core power control system is adjusted based on the total load characterization value of the secondary loop.

[0076] If the turbine operates in a load-limited mode, the core power control of the core power control system, adjusted based on the extraction steam load, the turbine load reference value of the secondary loop, and the steam flow limit and turbine first-stage pressure limit, includes: If the turbine operates in a load-limited mode, the extraction steam load is superimposed with the turbine load reference value of the secondary loop to obtain the total load characterization value of the secondary loop; the steam flow limit is compared with the turbine first-stage pressure limit to obtain the load-limited operating reference value; and the core power control of the core power control system is adjusted based on the total load characterization value of the secondary loop and the load-limited operating reference value. Specifically, the core power control based on the total load characterization value of the secondary loop and the load-limited operating reference value includes: comparing the total load characterization value of the secondary loop with the load-limited operating reference value to obtain the smaller value; and adjusting the core power control of the core power control system based on the smaller value.

[0077] Specifically, for the core power control system, the original design selected the corresponding load target signal (such as the target electrical power signal) based on different control operation modes of the turbine regulation system. However, if the turbine adds extraction steam power to be used for other purposes, the load target signal needs to be redesigned. When the turbine is in automatic control mode, the power rod group control function in the original control scheme mainly adjusts the stacked rod position of the power rod group based on the electrical power value of the secondary loop given by the turbine load reference signal to achieve coarse power adjustment. However, after the secondary loop extraction steam is used for other purposes, the turbine load reference signal can no longer represent the total load of the secondary loop and needs to be corrected. For details, see [link to specific scheme]. Figure 3 The part marked with a dashed box.

[0078] like Figure 3 As shown, the original turbine load reference value on the turbine side is used for the automatic control logic of the power rod group during automatic turbine control; the original frequency control signal and turbine opening reference value on the turbine side are used for the automatic control logic of the power rod group during manual turbine control; the original operator steam flow limit and first-level pressure limit on the turbine side participate in the limiting function; the original first-level pressure measurement value on the turbine side participates in the power rod group position monitoring function. All of the above signals need to consider the impact of the steam extraction function. That is, when the steam extraction mode is in operation, the above signals will not contain the demand value representing the current total load (electric power) of the secondary loop in the conventional island. The above signals need to be superimposed with the steam extraction load of the steam extraction system to convert it into a total secondary loop load (electric power) value, which is then provided to the downstream core control system for power rod group-related control.

[0079] Specifically, such as Figure 3 As shown, when the extraction mode signal is activated, it indicates that the system is currently in extraction mode. In this mode, the original turbine load reference value needs to be superimposed with the extraction load before it can participate in downstream logic control. That is, as... Figure 3 As shown, when the turbine is in normal operating mode, the extraction steam load is superimposed with the turbine load reference value to obtain the total load characterization value of the secondary loop. This total load characterization value is then used in downstream logic control to obtain the power setting value for core control. When the turbine is in limited operating load mode, then... Figure 3 The two signals with gray backgrounds (i.e., the operator's steam flow limit and the first-level pressure limit) will be input into the logic control. However, these two signals do not involve the modification of the automatic control logic, but they will affect the operating procedures of the power plant operators. Therefore, the operating procedure documents of the power plant operators should be modified simultaneously to avoid the impact of the steam extraction.

[0080] Step S104: Adjust the parameters of the steam generator water level control system according to the extraction steam load, the first stage pressure of the steam turbine, the opening degree of the GCT valve, the steam header pressure, and the opening degree of the ADG valve.

[0081] In some embodiments, adjusting the parameters of the steam generator water level control system based on the extraction steam load, the turbine first-stage pressure, the GCT valve opening, the steam header pressure, and the ADG valve opening includes: correcting the turbine first-stage pressure based on the extraction steam load to obtain a secondary loop load characterization signal; and adjusting the parameters of the steam generator water level control system based on the secondary loop load characterization signal, the GCT valve opening, the steam header pressure, and the ADG valve opening.

[0082] Specifically, for the steam generator water level control system, the original design used the turbine's first-stage pressure, ADG valve opening, GCT valve opening, and steam header pressure as input signals to generate the turbine reference load. However, with the addition of turbine extraction for other functions, the turbine reference load needs to be redesigned. This means assessing the impact of extraction on the steam header pressure (affected by the secondary loop thermal balance), obtaining an accurate and effective extraction load, and correcting the turbine load to characterize the secondary loop load (ensuring rated power under maximum steam supply conditions). See below for details. Figure 4 .

[0083] like Figure 4 As shown, after the addition of the steam extraction function, the first-stage pressure signal of the turbine cannot represent the full load of the secondary loop, and needs to be modified. The correction scheme is as follows: Figure 4 In the upper left and upper right corners of the circuit, extraction steam load is introduced to correct the original first-stage turbine pressure, obtaining a secondary loop load characterization signal. Then, based on the secondary loop load characterization signal, GCT valve opening, steam header pressure, and ADG valve opening, downstream logic calculations are performed to obtain the turbine reference load, which is used to control the steam generator water level. The extraction steam mode is used as a switching signal to introduce or remove the extraction steam load.

[0084] In addition, the extraction of steam from the turbine affects the thermal balance of the secondary loop, resulting in a decrease in feedwater temperature. If the average temperature of the primary loop is kept constant, the temperature of the hot and cold pipe sections of the primary loop or the feedwater flow rate will change, affecting the steam parameters at the steam generator outlet. Therefore, it is necessary to re-match the steam parameters of the turbine control system.

[0085] Step S105: Adjust the temperature control of the turbine bypass discharge control system according to the extraction steam load and the turbine first-stage pressure.

[0086] In some embodiments, adjusting the temperature control of the turbine bypass emission control system based on the extraction steam load and the turbine first-stage pressure includes: correcting the turbine first-stage pressure based on the extraction steam load to obtain a secondary loop load characterization signal; and adjusting the temperature control of the turbine bypass emission control system based on the secondary loop load characterization signal.

[0087] The temperature control of the turbine bypass emission control system based on the secondary loop load characterization signal includes: calculating a reference average temperature based on the secondary loop load characterization signal; calculating the difference between the reference average temperature and the measured average temperature to obtain the temperature deviation; determining the target control signal based on the temperature deviation; and executing the temperature control of the turbine bypass emission control system based on the target control signal.

[0088] Specifically, the impact of turbine steam extraction on the average temperature control mode (i.e., T-mode) of the turbine bypass emission control system (GCT): The original design used the turbine's first-stage pressure to characterize the turbine load and calculate the reference average temperature. The difference between this reference average temperature and the processed measured average temperature was used to obtain the temperature deviation, which served as the main control signal in the first control channel of the T-mode. After turbine steam extraction, the turbine's first-stage pressure signal needs correction. The specific correction scheme is the same as that in step S102, i.e., the turbine's first-stage pressure is corrected by adjusting the extraction load to obtain the secondary loop load characterization signal, and then the temperature control of the turbine bypass emission control system is adjusted based on the secondary loop load characterization signal.

[0089] Specifically, such as Figure 5 As shown, the corrective solution is... Figure 5 The proposed modification requires replacing the original turbine first-stage pressure signal with the secondary loop load signal. Aside from the signal being affected by the turbine first-stage pressure, the rest of the control logic remains unaffected.

[0090] Furthermore, in this embodiment of the invention, the reactor core control method for diversified utilization of nuclear energy further includes: correcting the first-stage pressure of the steam turbine based on the extraction steam load to obtain a secondary loop load characterization signal; and adjusting the regulating valve interlock of the steam turbine bypass emission control system based on the secondary loop load characterization signal.

[0091] Specifically, such as Figure 6 As shown, the impact on the interlocking of regulating valves is as follows: In T mode, all GCT valves are locked. When the turbine (representing the first-stage pressure of the turbine) sheds load at a certain rate, C7A and C7B signals are generated to unlock the first, second, and third groups of valves, respectively. Similar to the control logic of the average temperature control mode (T mode) of the turbine bypass emission control system described above, considering that after turbine extraction, the first-stage pressure of the turbine also needs to be corrected according to the correction scheme for the first-stage pressure signal of the average temperature control system in step S102.

[0092] Furthermore, it should be noted that in this embodiment of the invention, steps S102, S103, S104, and S105 are parallel and have no specific order requirement.

[0093] This invention solves the fundamental control scheme problem of reactor core after the diversified utilization of nuclear energy. Core control is the core and critical control system in a nuclear power plant control system; only by safely and stably controlling the reactor core power can the nuclear power plant operate safely and economically. This patent solves the key bottleneck problem of nuclear energy diversification, enabling nuclear energy, traditionally used only for power generation, to be applied to more scenarios, such as seawater desalination, heating, industrial steam, and nuclear hydrogen production, thus significantly improving the utilization efficiency of nuclear energy and greatly enhancing the economic efficiency of power plants.

[0094] refer to Figure 7 The present invention also provides a reactor core control system for diversified utilization of nuclear energy.

[0095] Specifically, such as Figure 7 As shown, the reactor core control system for diversified nuclear energy utilization includes:

[0096] The influencing parameter acquisition unit 701 is used to acquire the influencing parameters under the extraction steam mode. These influencing parameters include: extraction steam load, turbine first-stage pressure, turbine load reference value in the secondary loop, GCT valve opening, steam header pressure, and ADG valve opening.

[0097] The average temperature control adjustment unit 702 is used to adjust the average temperature control of the average temperature control system according to the extraction steam load and the first stage pressure of the steam turbine.

[0098] The core power control adjustment unit 703 is used to adjust the core power control of the core power control system according to the extraction steam load and the turbine load reference value of the secondary loop.

[0099] The steam generator water level control adjustment unit 704 is used to adjust the parameters of the steam generator water level control system according to the extraction steam load, the first stage pressure of the steam turbine, the opening degree of the GCT valve, the steam header pressure, and the opening degree of the ADG valve.

[0100] The bypass discharge system control adjustment unit 705 is used to adjust the temperature control of the turbine bypass discharge control system according to the extraction steam load and the turbine first-stage pressure.

[0101] Specifically, the specific coordination and operation process between the various units in the reactor core control system for diversified nuclear energy utilization can be referred to the above-mentioned reactor core control method for diversified nuclear energy utilization, and will not be repeated here.

[0102] Furthermore, an electronic device of the present invention includes a memory and a processor; the memory is used to store a computer program; the processor is used to execute the computer program to implement a reactor core control method for diversified nuclear energy utilization as described above. Specifically, according to embodiments of the present invention, the processes described above with reference to the flowchart can be implemented as computer software programs. For example, embodiments of the present invention include a computer program product comprising a computer program carried on a computer-readable medium, the computer program containing program code for performing the methods shown in the flowchart. In such embodiments, when the computer program is downloaded, installed, and executed by an electronic device, it performs the functions defined above in the methods of the embodiments of the present invention. The electronic device of the present invention can be a terminal such as a laptop, desktop computer, tablet computer, or smartphone, or it can be a server.

[0103] Furthermore, one type of storage medium of the present invention stores a computer program thereon, which, when executed by a processor, implements the reactor core control method for diversified nuclear energy utilization described above. Specifically, it should be noted that the storage medium described above in the present invention can be a computer-readable signal medium or a computer-readable storage medium, or any combination of the two. A computer-readable storage medium can be, for example, but not limited to, an electrical, magnetic, optical, electromagnetic, infrared, or semiconductor system, apparatus, or device, or any combination thereof. More specific examples of a computer-readable storage medium may include, but are not limited to: an electrical connection having one or more wires, a portable computer disk, a hard disk, random access memory (RAM), read-only memory (ROM), erasable programmable read-only memory (EPROM or flash memory), optical fiber, portable compact disk read-only memory (CD-ROM), optical storage device, magnetic storage device, or any suitable combination thereof. In the present invention, a computer-readable storage medium can be any tangible medium containing or storing a program that can be used by or in conjunction with an instruction execution system, apparatus, or device. In the present invention, a computer-readable signal medium can include a data signal propagated in baseband or as part of a carrier wave, carrying computer-readable program code. The transmitted data signal can take various forms, including but not limited to electromagnetic signals, optical signals, or any suitable combination thereof. The computer-readable signal medium can also be any computer-readable medium other than a computer-readable storage medium, which can send, propagate, or transmit a program for use by or in connection with an instruction execution system, apparatus, or device. The program code contained on the computer-readable medium can be transmitted using any suitable medium, including but not limited to: wires, optical fibers, RF (radio frequency), etc., or any suitable combination thereof.

[0104] The aforementioned computer-readable medium may be included in the aforementioned electronic device; or it may exist independently and not assembled into the electronic device.

[0105] The various embodiments in this specification are described in a progressive manner, with each embodiment focusing on its differences from other embodiments. Similar or identical parts between embodiments can be referred to interchangeably. For the apparatus disclosed in the embodiments, since they correspond to the methods disclosed in the embodiments, the description is relatively simple; relevant parts can be referred to the method section.

[0106] Those skilled in the art will further recognize that the units and algorithm steps of the various examples described in conjunction with the embodiments disclosed herein can be implemented in electronic hardware, computer software, or a combination of both. To clearly illustrate the interchangeability of hardware and software, the components and steps of the various examples have been generally described in terms of functionality in the foregoing description. Whether these functions are implemented in hardware or software depends on the specific application and design constraints of the technical solution. Those skilled in the art can use different methods to implement the described functions for each specific application, but such implementations should not be considered beyond the scope of this invention.

[0107] The steps of the methods or algorithms described in conjunction with the embodiments disclosed herein can be implemented directly by hardware, a software module executed by a processor, or a combination of both. The software module can be located in random access memory (RAM), main memory, read-only memory (ROM), electrically programmable ROM, electrically erasable programmable ROM, registers, hard disk, removable disk, CD-ROM, or any other form of storage medium known in the art.

[0108] The above embodiments are only for illustrating the technical concept and features of the present invention, and are intended to enable those skilled in the art to understand the content of the present invention and implement it accordingly. They do not limit the scope of protection of the present invention. All equivalent changes and modifications made within the scope of the claims of the present invention should fall within the scope of the claims of the present invention.

Claims

1. A reactor core control method for diversified utilization of nuclear energy, characterized in that, In steam extraction mode, perform the following steps: Obtain the influencing parameters under the extraction steam mode; the influencing parameters include: extraction steam load, turbine first-stage pressure, turbine load reference value of the secondary loop, GCT valve opening, steam header pressure, and ADG valve opening; The average temperature control of the average temperature control system is adjusted according to the extraction steam load and the first-stage pressure of the steam turbine. The core power control of the core power control system is adjusted according to the extraction steam load and the turbine load reference value of the secondary loop. This adjustment includes: obtaining the turbine's operating mode; if the turbine's operating mode is normal operation, adjusting the core power control of the core power control system according to the extraction steam load and the turbine load reference value of the secondary loop; if the turbine's operating mode is a load-limited operation mode, adjusting the core power control of the core power control system according to the extraction steam load, the turbine load reference value of the secondary loop, and in conjunction with the steam flow limit and the turbine's first-stage pressure limit. The parameters of the steam generator water level control system are adjusted according to the extraction steam load, the first stage pressure of the steam turbine, the opening degree of the GCT valve, the steam header pressure, and the opening degree of the ADG valve. The temperature control of the turbine bypass emission control system is adjusted according to the extraction steam load and the turbine first-stage pressure.

2. The reactor core control method for diversified utilization of nuclear energy according to claim 1, characterized in that, The average temperature adjustment control system based on the extraction steam load and the first-stage pressure of the steam turbine includes: Based on the extraction steam load, the first-stage pressure of the steam turbine is corrected to obtain the second loop load characterization signal; The total power load of the two circuits is calculated based on the load characterization signal of the two circuits and the total load calculation logic of the two circuits. The core average temperature control of the average temperature control system is performed based on the total power load of the two loops.

3. The reactor core control method for diversified utilization of nuclear energy according to claim 1, characterized in that, If the turbine is operating in normal mode, then the core power control of the core power control system, which adjusts the core power control system according to the extraction steam load and the turbine load reference value of the secondary loop, includes: If the turbine is in normal operating mode, the extraction load is superimposed with the turbine load reference value of the secondary loop to obtain the total load characterization value of the secondary loop. The core power control of the core power control system is adjusted based on the total load characterization value of the two loops.

4. The reactor core control method for diversified utilization of nuclear energy according to claim 1, characterized in that, If the turbine is operating in a load-limited mode, then adjusting the core power control of the core power control system based on the extraction steam load, the turbine load reference value of the secondary loop, and in conjunction with the steam flow limit and the turbine first-stage pressure limit includes: If the turbine is operating in a load-limited mode, the extraction load is superimposed with the turbine load reference value of the secondary loop to obtain the total load characterization value of the secondary loop. The steam flow limit is compared with the turbine first-stage pressure limit to obtain a reference value for restricted load operation. The core power control of the core power control system is adjusted based on the total load characterization value of the two loops and the limit load operation reference value.

5. The reactor core control method for diversified utilization of nuclear energy according to claim 4, characterized in that, The core power control, which adjusts the core power control system based on the total load characterization value of the two loops and the load limitation operation reference value, includes: The total load characterization value of the two circuits is compared with the restricted load operation reference value, and the smaller value between the two is obtained. The core power control of the core power control system is adjusted according to the smaller value.

6. The reactor core control method for diversified utilization of nuclear energy according to claim 1, characterized in that, The parameter control of the steam generator water level control system, which adjusts the steam extraction load, the turbine first-stage pressure, the GCT valve opening, the steam header pressure, and the ADG valve opening, includes: Based on the extraction steam load, the first-stage pressure of the steam turbine is corrected to obtain the second loop load characterization signal; The parameters of the steam generator water level control system are adjusted based on the load characterization signal of the second loop, the opening degree of the GCT valve, the steam header pressure, and the opening degree of the ADG valve.

7. The reactor core control method for diversified utilization of nuclear energy according to claim 1, characterized in that, The temperature control of the turbine bypass discharge control system, which adjusts the steam extraction load and the turbine first-stage pressure, includes: Based on the extraction steam load, the first-stage pressure of the steam turbine is corrected to obtain the second loop load characterization signal; Adjust the temperature control of the turbine bypass emission control system based on the secondary loop load characterization signal.

8. The reactor core control method for diversified utilization of nuclear energy according to claim 7, characterized in that, The temperature control of the turbine bypass emission control system adjusted according to the secondary loop load characterization signal includes: The reference average temperature is obtained by calculating based on the dual-loop load characterization signal. The temperature deviation is obtained by subtracting the reference average temperature from the measured average temperature. The target control signal is determined based on the temperature deviation. Temperature control of the turbine bypass emission control system is performed according to the target control signal.

9. The reactor core control method for diversified utilization of nuclear energy according to claim 7, characterized in that, The method further includes: Based on the extraction steam load, the first-stage pressure of the steam turbine is corrected to obtain the second loop load characterization signal; The interlocking of the regulating valves of the turbine bypass emission control system is adjusted based on the load characterization signal of the second loop.

10. A reactor core control system for diversified utilization of nuclear energy, characterized in that, include: The influencing parameter acquisition unit is used to acquire the influencing parameters under the extraction steam mode; the influencing parameters include: extraction steam load, turbine first-stage pressure, turbine load reference value of the secondary loop, GCT valve opening, steam header pressure, and ADG valve opening; An average temperature control adjustment unit is used to adjust the average temperature control of the average temperature control system according to the extraction steam load and the first stage pressure of the steam turbine. The core power control adjustment unit is used to adjust the core power control of the core power control system according to the extraction steam load and the turbine load reference value of the secondary loop. The adjustment of the core power control system according to the extraction steam load and the turbine load reference value of the secondary loop includes: acquiring the operating mode of the turbine; if the turbine's operating mode is normal operation mode, adjusting the core power control of the core power control system according to the extraction steam load and the turbine load reference value of the secondary loop; if the turbine's operating mode is a load-limited operation mode, adjusting the core power control of the core power control system according to the extraction steam load, the turbine load reference value of the secondary loop, and in conjunction with the steam flow limit and the turbine's first-stage pressure limit. The steam generator water level control and adjustment unit is used to adjust the parameters of the steam generator water level control system according to the extraction steam load, the first stage pressure of the steam turbine, the opening degree of the GCT valve, the steam header pressure, and the opening degree of the ADG valve. The bypass discharge system control adjustment unit is used to adjust the temperature control of the turbine bypass discharge control system according to the extraction steam load and the turbine first-stage pressure.

11. A storage medium, characterized in that, The storage medium stores a computer program adapted for loading by a processor to perform the steps of the reactor core control method for diversified nuclear energy utilization as described in any one of claims 1 to 9.

12. An electronic device, characterized in that, It includes a memory and a processor, wherein the memory stores a computer program, and the processor executes the steps of the reactor core control method for diversified nuclear energy utilization as described in any one of claims 1 to 9 by calling the computer program stored in the memory.

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