Reactor core control method and system for diversified utilization of nuclear energy, storage medium and electronic equipment

Abstract

The invention relates to a reactor core control method and system for diversified utilization of nuclear energy, a storage medium and electronic equipment. In a steam extraction mode, the following steps are executed: obtaining influence parameters in the steam extraction mode; adjusting the average temperature control of an average temperature control system according to the steam extraction load and the first-stage pressure of the steam turbine; adjusting the reactor core power control of the reactor core power control system according to the steam extraction load and the steam turbine load reference value of the secondary loop; parameter control of a steam generator water level control system is adjusted according to the steam extraction load, the turbine first-stage pressure, the GCT valve opening degree, the steam main pipe pressure and the ADG valve opening degree; and adjusting the temperature control of the steam turbine bypass emission control system according to the steam extraction load and the first-stage pressure of the steam turbine. According to the invention, a basic control scheme of the reactor core after diversified utilization of nuclear energy can be solved, the reactor core power of the reactor can be stably controlled, the utilization efficiency of the nuclear energy is improved, and the economic efficiency of a power plant is greatly improved.

Description

Technical Field

[0001] The present 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 Art

[0002] At present, the mainstream pressurized water reactor nuclear power plants use the reactor as the original heat source of the first circuit. After the fluid of the first circuit is heated, it is heat exchanged through the steam generator to generate high-temperature and high-pressure hot steam to drive the steam turbine unit to generate power, and finally realize the conversion of nuclear energy into electrical energy. When the high-temperature and high-pressure steam generated by the steam generator is not all used for power generation, such as extracting the steam originally used for power generation for other industrial production, or heating for urban residents, this realizes the comprehensive utilization of nuclear energy. When part of the steam originally used for power generation is extracted for other purposes, it will affect the load balance relationship between the first and second circuits of the original nuclear power plant. The essence of nuclear power plant reactor control is to always maintain the load balance of the first and second circuits.

[0003] Different types of nuclear power plants have different control schemes for their reactor cores. Different reactor control modes will be affected differently when steam is extracted from the secondary circuit for other purposes.

[0004] A nuclear power plant has designed a method for measuring the secondary circuit load for operation in nuclear energy heating mode. The total load of the secondary circuit is formed by measuring the turbine power and the heating load and adding them together. The total load of the secondary circuit is then used to adjust the power of the primary circuit. However, this scheme is only suitable for the case where only the first-stage pressure signal of the turbine is used as the interface signal of the primary and secondary circuits in the reactor core control scheme, that is, the existing technical scheme is suitable for the MSHIM mode of the AP1000 reactor type. For the MODE-G core control mode with more complex reactor-machine interfaces such as the CPR reactor type and the M310 unit, the existing technology cannot solve its reactor core control problem. In addition, this scheme only considers the use of steam extraction for heating, and is not generally applicable to other situations, such as other industrial steam uses. 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 in view of the problems existing in the prior art.

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

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

[0008] adjusting the average temperature control of the average temperature control system according to the extraction load and the first stage pressure of the steam turbine;

[0009] 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 circuit;

[0010] Adjusting the parameter control of the steam generator water level control system according to the extraction load, the first stage pressure of the steam turbine, the GCT valve opening, the steam main pipe pressure and the ADG valve opening;

[0011] Temperature control of a turbine bypass emission control system is adjusted based on the extraction load and the turbine first stage pressure.

[0012] In the reactor core control method for diversified utilization of nuclear energy described in the present invention, the average temperature control system adjusted according to the steam extraction load and the first stage pressure of the steam turbine includes:

[0013] Correcting the first-stage pressure of the steam turbine based on the extraction load to obtain a secondary circuit load characterization signal;

[0014] Calculating according to the load characterization signal of the secondary circuit and the total load calculation logic of the secondary circuit to obtain the total power load of the secondary circuit;

[0015] The core average temperature control system of the average temperature control system is executed according to the total power load of the secondary circuit.

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

[0017] Acquiring an operating mode of the steam turbine;

[0018] If the operation mode of the steam turbine is the normal operation mode, adjusting the core power control of the core power control system according to the extraction load and the steam turbine load reference value of the secondary circuit;

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

[0020] In the reactor core control method for diversified utilization of nuclear energy described in the present invention, if the operation mode of the steam turbine is the normal operation mode, 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 circuit includes:

[0021] If the operation mode of the steam turbine is the normal operation mode, the extraction steam load is superimposed on the steam turbine load reference value of the secondary circuit to obtain a total load representation value of the secondary circuit;

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

[0023] In the reactor core control method for diversified utilization of nuclear energy described in the present invention, if the operation mode of the steam turbine is the limited load operation mode, the core power control of the core power control system is adjusted according to the extraction load, the turbine load reference value of the secondary circuit and in combination with the steam flow limit and the first stage pressure limit of the steam turbine, including:

[0024] If the operation mode of the steam turbine is the load-limited operation mode, the extraction steam load is superimposed on the steam turbine load reference value of the secondary circuit to obtain a total load characterization value of the secondary circuit;

[0025] Comparing the steam flow limit with the first stage pressure limit of the steam turbine to obtain a limited load operation reference value;

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

[0027] In the reactor core control method for diversified utilization of nuclear energy according to the present 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 limit load operation reference value includes:

[0028] Compare and calculate the total load characterization value of the secondary circuit with the limited load operation reference value to obtain the smaller value of the two;

[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 the present invention, the parameter control of adjusting the steam generator water level control system according to the extraction load, the first stage pressure of the steam turbine, the GCT valve opening, the steam main pipe pressure and the ADG valve opening includes:

[0031] Correcting the first-stage pressure of the steam turbine based on the extraction load to obtain a secondary circuit load characterization signal;

[0032] The parameter control of the steam generator water level control system is adjusted according to the secondary circuit load characterization signal, the GCT valve opening, the steam main pipe pressure and the ADG valve opening.

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

[0034] Correcting the first-stage pressure of the steam turbine based on the extraction load to obtain a secondary circuit load characterization signal;

[0035] The temperature control of the turbine bypass emission control system is adjusted according to the secondary circuit load characterization signal.

[0036] In the reactor core control method for diversified utilization of nuclear energy described in the present invention, the temperature control of adjusting the turbine bypass emission control system according to the secondary circuit load characterization signal comprises:

[0037] Calculating according to the secondary circuit load characterization signal to obtain a reference average temperature;

[0038] Subtracting the reference average temperature from the measured average temperature to obtain a temperature deviation;

[0039] determining a target control signal 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 the present invention, the method further includes:

[0042] Correcting the first-stage pressure of the steam turbine based on the extraction load to obtain a secondary circuit load characterization signal;

[0043] The regulating valve interlock of the turbine bypass emission control system is adjusted based on the secondary circuit load characterization signal.

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

[0045] An influencing parameter acquisition unit is used to acquire influencing parameters in the extraction mode; the influencing parameters include: extraction load, first-stage pressure of the steam turbine, reference value of steam turbine load of the secondary circuit, GCT valve opening, steam main pipe pressure and ADG valve opening;

[0046] An average temperature control adjustment unit, used for adjusting the average temperature control of the average temperature control system according to the extraction load and the first stage pressure of the steam turbine;

[0047] A core power control adjustment unit, used for adjusting the core power control of the core power control system according to the extraction steam load and the steam turbine load reference value of the secondary circuit;

[0048] A steam generator water level control and adjustment unit, used to adjust the parameter control of the steam generator water level control system according to the extraction load, the first stage pressure of the steam turbine, the GCT valve opening, the steam main pipe pressure and the ADG valve opening;

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

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

[0051] The present invention also provides an electronic device, comprising 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 device implementing the present invention for diversified utilization of nuclear energy have the following beneficial effects: in the extraction mode, the following steps are performed: obtaining the influencing parameters in the extraction mode; adjusting the average temperature control of the average temperature control system according to the extraction load and the first stage pressure of the steam turbine; adjusting the core power control of the core power control system according to the extraction load and the reference value of the steam turbine load of the secondary circuit; adjusting the parameter control of the steam generator water level control system according to the extraction load, the first stage pressure of the steam turbine, the GCT valve opening, the steam main pipe pressure and the ADG valve opening; adjusting the temperature control of the steam turbine bypass emission control system according to the extraction load and the first stage pressure of the steam turbine. The present invention can solve the basic control scheme of the core after diversified utilization of nuclear energy, can stably control the core power of the reactor, improve the utilization efficiency of nuclear energy, and greatly increase the economic efficiency of the power plant. BRIEF DESCRIPTION OF THE DRAWINGS

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

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

[0055] Figure 2 It is a schematic diagram of the principle of adjusting the average temperature control system provided by the present invention;

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

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

[0058] Figure 5 It is a schematic diagram of the principle of adjusting the steam turbine bypass emission control system provided by the present invention;

[0059] Figure 6 It is a schematic diagram of the principle of interlocking adjustment of the regulating valve of the steam turbine bypass emission control system provided by the present invention;

[0060] Figure 7 It is a principle block diagram of a reactor core control system for diversified utilization of nuclear energy provided by the present invention. DETAILED DESCRIPTION

[0061] The following will be combined with the drawings in the embodiments of the present invention to clearly and completely describe the technical solutions in the embodiments of the present invention. Obviously, the described embodiments are only part of the embodiments of the present invention, not all of the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of the present invention.

[0062] The present invention provides a reactor core control method for diversified utilization of nuclear energy, which can solve the problem of the influence on the reactor control system in the process of reactor-machine matching after steam extraction from the turbine, namely, the problem on the average temperature control system, the core power control system, the steam generator water level control system and the turbine bypass emission control system.

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

[0064] Step S101: Obtain influencing parameters in the steam extraction mode.

[0065] Among them, the influencing parameters include: extraction load, first-stage steam turbine pressure, turbine load reference value of the secondary circuit, GCT valve opening, steam main pipe pressure and ADG valve opening. Among them, GCT refers to the turbine bypass emission control system, and ADG refers to the feedwater deaerator system.

[0066] Step S102: adjusting the average temperature control system 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, adjusting the average temperature control system according to the extraction load and the first-stage pressure of the steam turbine includes: correcting the first-stage pressure of the steam turbine based on the extraction load to obtain a secondary circuit load characterization signal; performing calculations based on the secondary circuit load characterization signal and the total load calculation logic of the secondary circuit to obtain the total power load of the secondary circuit; and executing the core average temperature control of the average temperature control system according to the total power load of the secondary circuit.

[0068] Specifically, the impact of the reactor-machine interface signal on the average core temperature control: the original design uses the first-stage pressure of the steam turbine to characterize the secondary circuit load, which is used to generate the average temperature control setting value, and when the unit is first put into operation to conduct core physical experiments, the corresponding relationship curve between thermal power and the first-stage pressure of the steam turbine is calibrated at each power platform through a thermal balance test. However, when the steam turbine is extracted for other purposes, the original first-stage pressure of the steam turbine can no longer be used to characterize the secondary circuit load. It is necessary to consider the impact of the extraction load as the total load of the secondary circuit (i.e., the secondary circuit load characterization signal). The specific adjustment plan is as follows: Figure 2 shown.

[0069] Specifically, Figure 2 As shown in the figure, when the steam in the secondary circuit is not all used for power generation, but a part of it is extracted for other purposes, the first-stage pressure of the steam turbine at this time cannot be used to characterize the total load of the secondary circuit, but it is necessary to correct the first-stage pressure of the steam turbine by the steam extraction load to obtain the corrected total load of the secondary circuit, that is, the secondary circuit load characterization signal, and then participate in the downstream logic control through the obtained secondary circuit load characterization signal to obtain the final total power of the secondary circuit, and control the average core temperature based on this.

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

[0071] It should be noted that Figure 2 In the embodiment, after obtaining the load characterization signal of the secondary circuit, the logic control of the downstream is the control logic in the original average temperature control system, which will not be described in detail in the present invention.

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

[0073] In some embodiments, adjusting the core power control of the core power control system according to the extraction steam load and the secondary circuit steam turbine load reference value includes: obtaining the operation mode of the steam turbine; if the operation mode of the steam turbine is the normal operation mode, adjusting the core power control of the core power control system according to the extraction steam load and the secondary circuit steam turbine load reference value;

[0074] If the operation mode of the steam turbine is the limited load operation mode, the core power control of the core power control system is adjusted according to the extraction load, the turbine load reference value of the secondary circuit and in combination with the steam flow limit and the first stage pressure limit of the steam turbine.

[0075] Among them, if the operation mode of the steam turbine is the normal operation 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 circuit, including: if the operation mode of the steam turbine is the normal operation mode, the extraction steam load is superimposed with the turbine load reference value of the secondary circuit to obtain the total load characterization value of the secondary circuit; the core power control of the core power control system is adjusted based on the total load characterization value of the secondary circuit.

[0076] If the operation mode of the steam turbine is the limited load operation mode, the core power control of the core power control system is adjusted according to the extraction load, the turbine load reference value of the secondary circuit and the steam flow limit and the first stage pressure limit of the steam turbine, including: if the operation mode of the steam turbine is the limited load operation mode, the extraction load is superimposed on the turbine load reference value of the secondary circuit to obtain the total load characterization value of the secondary circuit; the steam flow limit is compared with the first stage pressure limit of the steam turbine to obtain the limited load operation reference value; the core power control of the core power control system is adjusted based on the total load characterization value of the secondary circuit and the limited load operation reference value. Among them, adjusting the core power control of the core power control system based on the total load characterization value of the secondary circuit and the limited load operation reference value includes: comparing the total load characterization value of the secondary circuit with the limited load operation reference value to obtain the smaller value of the two; adjusting the core power control of the core power control system according to the smaller value.

[0077] Specifically, for the core power control system, the original design selects the corresponding load target signal (such as the target electric power signal) according to the different control operation modes of the turbine regulation system. However, if the steam turbine adds new extraction power and uses the steam for other purposes, the load target signal needs to be redesigned. When the steam turbine is in automatic control mode, the control function of the power rod group in the original control scheme is mainly to adjust the step rod position of the power rod group according to the electric power value of the secondary circuit given by the turbine load reference value signal to achieve coarse power adjustment. However, after the secondary circuit is extracted for other purposes, the turbine load reference value signal can no longer represent the total load of the secondary circuit and needs to be corrected. For details, see Figure 3 The part marked with a dotted 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 function of the power rod group during manual turbine control; the original operator steam flow limit and first-stage pressure limit on the turbine side participate in the restriction function; the original first-stage pressure measurement value on the turbine side participates in the rod position monitoring function of the power rod group. The above signals all need to consider the influence of the steam extraction function. That is, when the steam extraction mode is put into operation, the above signals will not be able to contain the demand value representing the current conventional island secondary circuit total load (electric power). The above signals need to be superimposed on the steam extraction load of the steam extraction system and converted into the total secondary circuit total load (electric power) value to be provided to the downstream core control system for power rod group related control.

[0079] Specifically, Figure 3 As shown in the figure, when the signal of the extraction mode takes effect, it means that the current state is in the extraction mode. At this time, the original turbine load reference value needs to be superimposed with the extraction load before it can participate in the downstream logic control. Figure 3 As shown in the figure, when the steam turbine is in normal operation mode, the extraction load is superimposed on the turbine load reference value to obtain the total load representation value of the secondary circuit, and then the total load representation value of the secondary circuit is used to participate in the downstream logic control to obtain the power setting value of the core control; when the steam turbine is in the limited operation load operation mode, then Figure 3 The two signals with gray background in the figure (i.e., operator steam flow limit and first-stage pressure limit) will be put into logic control. However, these two signals do not involve modification of automatic control logic, but will affect the operating procedures of power plant operators. Therefore, the operating procedure files of power plant operators are modified synchronously to avoid the impact of steam extraction.

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

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

[0082] Specifically, for the steam generator water level control system, the original design scheme uses the first-stage pressure of the turbine, the ADG valve opening, the GCT valve opening and the steam main pressure as input signals to generate the turbine reference load. However, after the steam turbine extraction is added for other functions, the turbine reference load needs to be redesigned. That is, it is necessary to evaluate the impact of steam extraction on the steam main pressure (affected by the thermal balance of the secondary circuit), and at the same time, it is necessary to obtain an accurate and effective steam extraction load, and correct the turbine load to characterize the secondary circuit load (to ensure the rated power under the maximum steam supply condition). See below for details. Figure 4 .

[0083] like Figure 4 As shown in the figure, after adding the steam extraction function, the first-stage pressure signal of the steam turbine cannot represent the entire load of the secondary circuit, and needs to be modified. The correction scheme is as follows Figure 4 In the upper left and upper right corners of the figure, the extraction load is introduced to correct the original first-stage pressure of the steam turbine, and the secondary circuit load characterization signal is obtained. Then, according to the secondary circuit load characterization signal, GCT valve opening, steam main pipe pressure and ADG valve opening, the downstream logic calculation is participated in to obtain the turbine reference load, which is used to realize the water level control of the steam generator. Among them, the extraction mode is used as a switch signal to introduce the extraction load or cut off the access of the extraction load.

[0084] In addition, the steam extraction of the steam turbine affects the thermal balance of the secondary circuit, resulting in a decrease in the feed water temperature. If the average temperature of the primary circuit is maintained unchanged, the temperature of the cold and hot pipe sections of the primary circuit or the feed water flow rate will change, affecting the steam parameters at the steam generator outlet. Therefore, the steam parameters of the steam turbine control system need to be matched again.

[0085] Step S105: adjusting the temperature control of the turbine bypass emission control system according to the extraction load and the first stage pressure of the turbine.

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

[0087] Among them, adjusting the temperature control of the turbine bypass emission control system according to the secondary circuit load characterization signal includes: calculating according to the secondary circuit load characterization signal to obtain a reference average temperature; subtracting the reference average temperature from the measured average temperature to obtain a temperature deviation; determining a target control signal based on the temperature deviation; and executing temperature control of the turbine bypass emission control system according to the target control signal.

[0088] Specifically, the impact of steam extraction from the turbine on the average temperature control mode (i.e., T mode) of the turbine bypass emission control system (GCT) is as follows: the original design uses the first-stage pressure of the turbine to characterize the turbine load, which is used to calculate the reference average temperature, and the difference with the processed measured average temperature is used to obtain the temperature deviation, which is used as the main control signal to participate in the control of the first control channel of the T mode. After the steam turbine is extracted, the first-stage pressure signal of the turbine needs to be corrected. The specific correction scheme is the same as the correction scheme of step S102, that is, the first-stage pressure of the turbine is corrected by the steam extraction load to obtain the second-circuit load characterization signal, and then the temperature control of the turbine bypass emission control system is adjusted according to the second-circuit load characterization signal.

[0089] Specifically, Figure 5 As shown, the correction scheme is Figure 5 The modification scheme in the above needs to use the secondary circuit load signal to replace the original turbine first stage pressure signal. Except that the above signal is affected by the turbine first stage pressure, the rest of the control logic is not affected.

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

[0091] Specifically, Figure 6 As shown, the impact on the interlocking of the regulating valves: All valves of GCT are locked in T mode: When the steam turbine (represented by the first stage pressure of the steam turbine) is unloaded at a certain rate, C7A and C7B signals will be generated to unlock the first, second and third groups of valves respectively. The same control logic of the average temperature control mode (T mode) of the steam turbine bypass emission control system mentioned above, considering that after the steam turbine is extracted, the first stage pressure of the steam turbine also needs to be corrected with reference to the correction scheme of the first stage pressure signal of the steam turbine of the average temperature control system in step S102.

[0092] Further, it should be noted that, in the embodiment of the present invention, step S102, step S103, step S104, and step S105 are in parallel relationship, and there is no requirement for the order of precedence.

[0093] The present invention can solve the problem of the basic control scheme of the core after the diversified utilization of nuclear energy. The core control is the core key control system in the 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, so that traditional nuclear energy that is only used for power generation can be applied to more scenarios, such as seawater desalination, heating, industrial steam, nuclear energy hydrogen production, etc., fully improving the utilization efficiency of nuclear energy and greatly improving 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, Figure 7 As shown, the reactor core control system for the diversified utilization of nuclear energy includes:

[0096] The influencing parameter acquisition unit 701 is used to acquire influencing parameters in the extraction mode, wherein the influencing parameters include: extraction load, first stage pressure of steam turbine, reference value of steam turbine load of secondary circuit, GCT valve opening, steam main pipe 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 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 secondary circuit turbine load reference value.

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

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

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

[0102] In addition, 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 utilization of nuclear energy as described in any one of the above. Specifically, according to an embodiment of the present invention, the process described with reference to the flowchart above can be implemented as a computer software program. For example, an embodiment of the present invention includes a computer program product, which includes a computer program carried on a computer-readable medium, and the computer program contains a program code for executing the method shown in the flowchart. In such an embodiment, the computer program can be downloaded and installed by an electronic device and when executed, it executes the above functions defined in the method of the embodiment of the present invention. The electronic device in the present invention can be a terminal such as a notebook, a desktop, a tablet computer, a smart phone, or a server.

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

[0104] The computer-readable medium may be included in the electronic device, or may exist independently without being incorporated into the electronic device.

[0105] In this specification, each embodiment is described in a progressive manner, and each embodiment focuses on the differences from other embodiments. The same or similar parts between the embodiments can be referred to each other. For the device disclosed in the embodiment, since it corresponds to the method disclosed in the embodiment, the description is relatively simple, and the relevant parts can be referred to the method part.

[0106] Professionals may further appreciate that the units and algorithm steps of each example described in conjunction with the embodiments disclosed herein can be implemented in electronic hardware, computer software, or a combination of the two. In order to clearly illustrate the interchangeability of hardware and software, the composition and steps of each example have been generally described in the above description according to function. Whether these functions are performed in hardware or software depends on the specific application and design constraints of the technical solution. Professionals and technicians may use different methods to implement the described functions for each specific application, but such implementation should not be considered to be beyond the scope of the present invention.

[0107] The steps of the method or algorithm described in conjunction with the embodiments disclosed herein may be implemented directly using hardware, a software module executed by a processor, or a combination of the two. The software module may be placed in a random access memory (RAM), a memory, a read-only memory (ROM), an electrically programmable ROM, an electrically erasable programmable ROM, a register, a hard disk, a removable disk, a 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 their purpose is to enable people familiar with the technology to understand the content of the present invention and implement it accordingly, and they cannot limit the scope of protection of the present invention. All equivalent changes and modifications made to 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 Extraction mode, perform the following steps: Obtain influencing parameters in the extraction mode; the influencing parameters include: extraction load, first-stage steam turbine pressure, turbine load reference value of the secondary circuit, GCT valve opening, steam main pipe pressure and ADG valve opening; adjusting the average temperature control of the average temperature control system according to the extraction load and the first stage pressure of the steam turbine; 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 circuit; Adjusting the parameter control of the steam generator water level control system according to the extraction load, the first stage pressure of the steam turbine, the GCT valve opening, the steam main pipe pressure and the ADG valve opening; Temperature control of a turbine bypass emission control system is adjusted based on the extraction 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 control system for adjusting the average temperature according to the extraction load and the first stage pressure of the steam turbine comprises: Correcting the first-stage pressure of the steam turbine based on the extraction load to obtain a secondary circuit load characterization signal; Calculating according to the load characterization signal of the secondary circuit and the total load calculation logic of the secondary circuit to obtain the total power load of the secondary circuit; The core average temperature control system of the average temperature control system is executed according to the total power load of the secondary circuit.

3. The reactor core control method for diversified utilization of nuclear energy according to claim 1, characterized in that: The core power control of adjusting the core power control system according to the extraction steam load and the secondary circuit steam turbine load reference value comprises: Acquiring an operating mode of the steam turbine; If the operation mode of the steam turbine is the normal operation mode, adjusting the core power control of the core power control system according to the extraction load and the steam turbine load reference value of the secondary circuit; If the operation mode of the steam turbine is the limited load operation mode, the core power control of the core power control system is adjusted according to the extraction load, the turbine load reference value of the secondary circuit and in combination with the steam flow limit and the first stage pressure limit of the steam turbine.

4. The reactor core control method for diversified utilization of nuclear energy according to claim 3, characterized in that: If the operation mode of the steam turbine is the normal operation mode, adjusting the core power control of the core power control system according to the extraction steam load and the steam turbine load reference value of the secondary circuit includes: If the operation mode of the steam turbine is the normal operation mode, the extraction steam load is superimposed on the steam turbine load reference value of the secondary circuit to obtain a total load representation value of the secondary circuit; The core power control of the core power control system is adjusted based on the total load characterization value of the secondary loop.

5. The reactor core control method for diversified utilization of nuclear energy according to claim 3, characterized in that: If the operation mode of the steam turbine is the limited load operation mode, adjusting the core power control of the core power control system according to the extraction load, the turbine load reference value of the secondary circuit and in combination with the steam flow limit and the first stage pressure limit of the steam turbine includes: If the operation mode of the steam turbine is the load-limited operation mode, the extraction steam load is superimposed on the steam turbine load reference value of the secondary circuit to obtain a total load characterization value of the secondary circuit; Comparing the steam flow limit with the first stage pressure limit of the steam turbine to obtain a limited load operation reference value; The core power control of the core power control system is adjusted based on the total load characterization value of the secondary circuit and the limit load operation reference value.

6. The reactor core control method for diversified utilization of nuclear energy according to claim 5, characterized in that: The step of adjusting the core power control of the core power control system based on the total load characterization value of the secondary circuit and the limit load operation reference value includes: Compare and calculate the total load characterization value of the secondary circuit with the limited load operation reference value to obtain the smaller value of the two; The core power control of the core power control system is adjusted according to the smaller value.

7. The reactor core control method for diversified utilization of nuclear energy according to claim 1, characterized in that: The parameter control of adjusting the steam generator water level control system according to the extraction load, the first stage pressure of the steam turbine, the GCT valve opening, the steam main pipe pressure and the ADG valve opening includes: Correcting the first-stage pressure of the steam turbine based on the extraction load to obtain a secondary circuit load characterization signal; The parameter control of the steam generator water level control system is adjusted according to the secondary circuit load characterization signal, the GCT valve opening, the steam main pipe pressure and the ADG valve opening.

8. The reactor core control method for diversified utilization of nuclear energy according to claim 1, characterized in that: The temperature control of adjusting the steam turbine bypass emission control system according to the steam extraction load and the first stage pressure of the steam turbine comprises: Correcting the first-stage pressure of the steam turbine based on the extraction load to obtain a secondary circuit load characterization signal; The temperature control of the turbine bypass emission control system is adjusted according to the secondary circuit load characterization signal.

9. The reactor core control method for diversified utilization of nuclear energy according to claim 8, characterized in that: The step of adjusting the temperature control of the steam turbine bypass emission control system according to the secondary circuit load characterization signal comprises: Calculating according to the secondary circuit load characterization signal to obtain a reference average temperature; Subtracting the reference average temperature from the measured average temperature to obtain a temperature deviation; determining a target control signal based on the temperature deviation; Temperature control of the turbine bypass emission control system is performed according to the target control signal.

10. The reactor core control method for diversified utilization of nuclear energy according to claim 8, characterized in that: The method further comprises: Correcting the first-stage pressure of the steam turbine based on the extraction load to obtain a secondary circuit load characterization signal; The regulating valve interlock of the turbine bypass emission control system is adjusted based on the secondary circuit load characterization signal.

11. A reactor core control system for diversified utilization of nuclear energy, characterized in that: include: An influencing parameter acquisition unit is used to acquire influencing parameters in the extraction mode; the influencing parameters include: extraction load, first-stage pressure of the steam turbine, reference value of steam turbine load of the secondary circuit, GCT valve opening, steam main pipe pressure and ADG valve opening; An average temperature control adjustment unit, used for adjusting the average temperature control of the average temperature control system according to the extraction load and the first stage pressure of the steam turbine; A core power control adjustment unit, used for adjusting the core power control of the core power control system according to the extraction steam load and the steam turbine load reference value of the secondary circuit; A steam generator water level control and adjustment unit, used to adjust the parameter control of the steam generator water level control system according to the extraction load, the first stage pressure of the steam turbine, the GCT valve opening, the steam main pipe pressure and the ADG valve opening; The bypass emission system control adjustment unit is used to adjust the temperature control of the turbine bypass emission control system according to the extraction load and the first stage pressure of the turbine.

12. A storage medium, characterized in that: The storage medium stores a computer program, and the computer program is suitable for being loaded by a processor to execute the steps of the reactor core control method for diversified utilization of nuclear energy as described in any one of claims 1 to 10.

13. An electronic device, characterized in that: It comprises 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 in any one of claims 1 to 10 by calling the computer program stored in the memory.

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