Nuclear power station reactor-engine coordination control method and device, medium and equipment

Abstract

The invention relates to a nuclear power station reactor-engine coordination control method and device, a medium and equipment. The method comprises the following steps: S1, determining a first load from a load corresponding to a steam flow instruction and a steam turbine load set value according to a first preset condition; and S2, determining a second load from the load corresponding to the regulating stage pressure instruction and the maximum load value according to a second preset condition. And S3, comparing the first load with the second load, and obtaining the minimum value as the minimum load. And S4, generating a corresponding reactor power instruction according to the minimum load. Under the working condition that the heat efficiency of a conventional island is reduced, unbalance of reactor power cannot be caused, and the influence of reactor temperature control and nuclear safety can be effectively reduced.

Description

Technical Field

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

[0002] The CPR1000 nuclear power unit adopts a reactor-follow-machine control method, that is, the reactor receives the power instructions sent by the turbine to respond to changes in the unit, and ultimately maintains the balance of reactor-machine power.

[0003] However, the current reactor control has the following problems: when the conventional island thermal efficiency is reduced, the power command sent by the turbine to the reactor cannot fully reflect the conventional island thermal power, causing an imbalance in the reactor power and having a negative impact on the reactor temperature control. Summary of the invention

[0004] The technical problem to be solved by the present invention is to provide a nuclear power plant reactor-machine coordinated control method, device, medium and equipment to address the defect of reactor-machine power imbalance when the efficiency of the above-mentioned conventional island is reduced.

[0005] The technical solution adopted by the present invention to solve the technical problem is: a nuclear power plant reactor machine coordinated control method, comprising the following steps:

[0006] S1. Determine a first load from a load corresponding to a steam flow instruction and a turbine load setting value according to a first preset condition;

[0007] S2. Determine a second load from the load corresponding to the regulating stage pressure instruction and the maximum load value according to a second preset condition;

[0008] S3, comparing the first load and the second load, and obtaining the minimum value thereof as the minimum load;

[0009] S4. Generate a corresponding reactor power instruction according to the minimum load.

[0010] Further, in the nuclear power plant reactor-machine coordinated control method of the present invention, step S1 comprises:

[0011] The first preset condition includes:

[0012] Condition 1: The output of the pressure controller is less than the output of the load controller;

[0013] Condition 2: Detect the rapid drop in load on the turbine;

[0014] If it is determined that any of the above conditions is met, the load corresponding to the steam flow instruction is used as the first load; if not, the steam turbine load setting value is used as the first load.

[0015] Further, in the nuclear power plant reactor-machine coordinated control method of the present invention, step S2 comprises:

[0016] Determine whether the pressure controller output is less than the load controller output;

[0017] If yes, the load corresponding to the regulating stage pressure instruction is used as the second load;

[0018] If not, the maximum load value is used as the second load.

[0019] Furthermore, in the nuclear power plant reactor-machine coordinated control method of the present invention, before step S1, it also includes:

[0020] S0. Obtain the load corresponding to the steam flow command, the turbine load setting value, the load corresponding to the regulating stage pressure command, and the maximum load value.

[0021] In addition, the present invention provides a nuclear power plant reactor-machine coordination control device, comprising:

[0022] A first determining unit, configured to determine a first load from a load corresponding to a steam flow instruction and a turbine load setting value according to a first preset condition;

[0023] A second determining unit, configured to determine a second load from a load corresponding to the regulating stage pressure instruction and a maximum load value according to a second preset condition;

[0024] A comparing unit, configured to compare the first load and the second load, and obtain a minimum value thereof as a minimum load;

[0025] A generating unit is used to generate a corresponding reactor power instruction according to the minimum load.

[0026] Further, in the nuclear power plant reactor-machine coordinated control device of the present invention, the first preset condition includes:

[0027] Condition 1: The output of the pressure controller is less than the output of the load controller;

[0028] Condition 2: Detect the rapid drop in load on the turbine;

[0029] The first determination unit is used for: if it is determined that any of the above conditions is met, then the load corresponding to the steam flow instruction is used as the first load; if not, then the steam turbine load setting value is used as the first load.

[0030] Further, in the nuclear power plant reactor-machine coordinated control device of the present invention, the second determination unit is used for:

[0031] Determine whether the pressure controller output is less than the load controller output; if so, use the load corresponding to the regulating stage pressure instruction as the second load; if not, use the maximum load value as the second load.

[0032] Furthermore, in the nuclear power plant reactor-machine coordinated control device of the present invention, it also includes:

[0033] The acquisition unit is used to obtain the load corresponding to the steam flow instruction, the steam turbine load setting value, the load corresponding to the regulating stage pressure instruction, and the maximum load value.

[0034] In addition, the present invention also provides a computer-readable storage medium, which stores a computer program, and the computer program is suitable for loading by a processor to execute the steps of the nuclear power plant reactor-machine coordinated control method as described above.

[0035] In addition, the present invention also provides a computer device, including a memory and a processor, wherein the memory stores a computer program, and the processor executes the steps of the above-mentioned nuclear power plant reactor-machine coordinated control method by calling the computer program stored in the memory.

[0036] The nuclear power plant reactor-machine coordinated control method, device, medium and equipment implementing the present invention have the following beneficial effects: the present invention can effectively reduce the impact on reactor temperature control and nuclear safety without causing reactor power imbalance under the condition of reduced thermal efficiency of conventional islands. BRIEF DESCRIPTION OF THE DRAWINGS

[0037] The present invention will be further described below with reference to the accompanying drawings and embodiments, in which:

[0038] Figure 1 It is a flow chart of a nuclear power plant reactor-machine coordinated control method provided by an embodiment of the present invention;

[0039] Figure 2 It is a flow chart of a nuclear power plant reactor-machine coordinated control method provided by an embodiment of the present invention;

[0040] Figure 3 It is a structural schematic diagram of a reactor-machine coordinated control device for a nuclear power plant provided by an embodiment of the present invention;

[0041] Figure 4 It is a logic schematic diagram of a nuclear power plant reactor-machine coordination control device provided by an embodiment of the present invention;

[0042] Figure 5 It is a logical schematic diagram of a nuclear power plant reactor-machine coordinated control method in the related technology. DETAILED DESCRIPTION

[0043] In order to have a clearer understanding of the technical features, purposes and effects of the present invention, specific embodiments of the present invention are now described in detail with reference to the accompanying drawings.

[0044] In the following description, specific details such as specific system structures, technologies, etc. are provided for the purpose of illustration rather than limitation, so as to provide a thorough understanding of the embodiments of the present invention. However, it should be clear to those skilled in the art that the present invention may be implemented in other embodiments without these specific details. In other cases, detailed descriptions of well-known systems, devices, circuits, and methods are omitted to prevent unnecessary details from obstructing the description of the present invention.

[0045] In order to facilitate the understanding of the present invention, the present invention will be described more fully below, and the present invention can be implemented in many different forms and is not limited to the embodiments described herein. On the contrary, the purpose of providing these embodiments is to make the disclosure of the present invention more thorough and comprehensive.

[0046] It should be understood that although the terms first, second, third, etc. may be used to describe various information in the embodiments of the present invention, these information should not be limited to these terms. These terms are only used to distinguish the same type of information from each other. It is not necessarily required or implied that there is any such actual relationship or order between these entities or operations. In this article, steam engine refers to steam turbine.

[0047] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as those commonly understood by those skilled in the art of the present invention. The terms used in the specification of the present invention herein are only for the purpose of describing specific embodiments and are not intended to limit the present invention.

[0048] In one embodiment provided by the present invention, reference Figure 1 The nuclear power plant reactor-machine coordinated control method of this embodiment includes the following steps:

[0049] S1. Determine a first load from the load corresponding to the steam flow instruction and the turbine load setting value according to a first preset condition. It can be understood that the first preset condition may include at least one condition, such as one condition or two conditions.

[0050] Preferably, the first preset condition includes: Condition 1: The output of the pressure controller is less than the output of the load controller. Condition 2: Detecting a rapid drop in the load of the steam turbine. It should be noted that rapid drop in load refers to a rapid drop in the load of the steam turbine under abnormal operating conditions, which is divided into many operating conditions, such as load shedding due to shutdown of the feedwater pump and load shedding due to high water temperature of the generator. Detecting a rapid drop in the load of the steam turbine can be determined by monitoring whether the load of the steam turbine drops suddenly to a preset load value at a certain moment, or by monitoring whether the load of the steam turbine has dropped by a preset load amount within a preset time period.

[0051] If it is determined that any of the above conditions is met, the load corresponding to the steam flow instruction is used as the first load. If not, the steam turbine load setting value is used as the first load.

[0052] S2. Determine the second load from the load corresponding to the regulating stage pressure instruction and the maximum load value according to the second preset condition. It can be understood that the maximum load is a fixed value, which is the maximum load allowed by the unit, and is preferably 1200MW by default.

[0053] Specifically, in step S2, it is determined whether the pressure controller output is less than the load controller output. If so, the load corresponding to the regulating stage pressure instruction is used as the second load. If not, the maximum load value is used as the second load.

[0054] S3. Compare the first load and the second load, and obtain the minimum value as the minimum load.

[0055] S4. Generate a corresponding reactor power instruction according to the minimum load. Alternatively, the determined minimum load may be used as the reactor power instruction. It is understandable that the minimum load value is selected as the reactor power instruction because the reactor control needs to prevent overpower the most. During normal operation, the reactor power is 100%, and the overpower limit is 102%. Therefore, the idea of ​​all reactor power control designs is to maintain the reactor power balance without overpowering.

[0056] It should be noted that after the unit's real power decreases due to reduced efficiency, the actual power of the unit begins to decrease, the load controller has a positive deviation, the steam demand output by the controller slowly increases, and the turbine valve slowly opens. At this time, due to the reduction in the efficiency of the secondary circuit, in order to maintain the stability of the secondary circuit power, the power of the primary circuit begins to rise, the turbine regulating stage pressure rises, for example, slowly increases from 6.0MPa to 6.1MPa, and the output of the pressure controller slowly decreases (eliminating the integral deviation).

[0057] In related technologies, such as Figure 5 As shown in the figure, when the output of the pressure controller is less than the output of the load controller, the load corresponding to the regulating stage pressure instruction is usually sent to the small selection module as the second load, and the steam turbine load setting value is sent to the small selection module as the first load. At this time, in the reactor power control logic, the steam turbine load setting value after the signal small selection is used as the reactor power instruction. At this time, due to the reduced efficiency, the heat consumption corresponding to the load setting value is less than the actual consumption. Therefore, the heat provided by the reactor instruction is less than the actual steam turbine consumption, which will cause the reactor power imbalance and cause the core temperature to fluctuate. The temperature control rod may exceed the adjustment range, affecting nuclear safety and failing to meet the needs of automatic control.

[0058] After repeated investigations, research, data analysis and theoretical calculations, it was found that the steam temperature before the regulating stage of a nuclear power steam turbine remains basically stable at different efficiencies. Stable temperature also means that the enthalpy value is relatively stable. Therefore, when the efficiency changes, the steam flow rate can more accurately reflect the heat consumed by the steam turbine. This leads to the solution of the present invention.

[0059] refer to Figure 4 , when the output of the pressure controller is less than the output of the load controller, the switch at the top of the figure is switched to the load corresponding to the steam flow command. At this time, the steam turbine load setting value no longer participates in the small selection, but the load corresponding to the steam flow command and the load corresponding to the output of the pressure controller participate in the small selection. That is, at this time, the load corresponding to the steam flow command is used as the first load of the small selection module, and the load corresponding to the regulating stage pressure command is used as the second load of the small selection module. After the two are compared in the small selection module, the minimum value is selected for output. Although the efficiency is reduced at this time, the load corresponding to the steam flow command and the load corresponding to the regulating stage pressure command can both truthfully reflect the actual steam consumption of the steam turbine, so the reactor power command obtained by the small selection of the two is more reasonable. This embodiment can not cause imbalance in the reactor power, will not cause core temperature fluctuations, and will not affect nuclear safety when the efficiency of the steam turbine changes.

[0060] In one of the alternative embodiments, reference Figure 2 The nuclear power plant reactor-machine coordinated control method of this embodiment further includes, before step S1:

[0061] S0. Obtain the load corresponding to the steam flow command, the turbine load setting value, the load corresponding to the regulating stage pressure command, and the maximum load value.

[0062] In this embodiment, the relevant loads required in the logic judgment process are first obtained, and then the logic judgment is performed. This embodiment can maintain the power balance of the reactor machine when the efficiency of the conventional island is reduced.

[0063] It should be noted that in the present invention, the pressure controller is used to control the regulating stage pressure, and the regulating stage pressure is linearly related to the steam flow of the steam turbine. The load controller is used to control the load, and the reactor power matches the energy consumed by the steam turbine. The pressure controller is usually a PID regulator, which is used to adjust the regulating stage pressure of the steam turbine within a range. Therefore, when the regulated quantity increases, the output of the PID regulating stage will decrease to prevent the regulated quantity from further increasing. Under normal circumstances, the thermal efficiency is normal, the nuclear island power command tracks the steam turbine load command, and the reactor power is matched.

[0064] Figure 4 In the figure, the dotted line is the switch quantity, and the solid line is the analog quantity. The arrow refers to the signal transmission scheme. The current position of the switch shown in the figure is the state where the dotted signal is 0. If it is 1, it will switch to another path.

[0065] In another embodiment provided by the present invention, reference Figure 3 The nuclear power plant reactor-machine coordination control device of this embodiment includes:

[0066] The first determination unit is used to determine the first load from the load corresponding to the steam flow instruction and the steam turbine load setting value according to the first preset condition.

[0067] Specifically, the first preset condition includes: Condition 1: The output of the pressure controller is less than the output of the load controller. Condition 2: Detecting a rapid drop in the load of the steam turbine. It should be noted that rapid drop in load refers to a rapid drop in the load of the steam turbine under abnormal operating conditions, which is divided into many operating conditions, such as load shedding due to shutdown of the feedwater pump and load shedding due to high water temperature of the generator. Detecting a rapid drop in the load of the steam turbine can be determined by monitoring whether the load of the steam turbine drops suddenly to a preset load value at a certain moment, or by monitoring whether the load of the steam turbine has dropped by a preset load amount within a preset time period.

[0068] If it is determined that any of the above conditions is met, the load corresponding to the steam flow instruction is used as the first load. If not, the steam turbine load setting value is used as the first load.

[0069] The second determination unit is used to determine the second load from the load corresponding to the regulating stage pressure instruction and the maximum load value according to the second preset condition. Specifically, it is determined whether the pressure controller output is less than the load controller output. If so, the load corresponding to the regulating stage pressure instruction is used as the second load. If not, the maximum load value is used as the second load.

[0070] The comparison unit is used to compare the first load and the second load, and obtain the minimum value therebetween as the minimum load.

[0071] The generating unit is used to generate the corresponding reactor power instruction according to the minimum load. Alternatively, the determined minimum load can also be used as the reactor power instruction. It can be understood that the minimum load value is selected as the reactor power instruction because the reactor control needs to prevent overpower the most. For example, the reactor power is 100% during normal operation, and the overpower limit is 102%. Therefore, the idea of ​​all reactor power control designs is to maintain the reactor power balance without overpowering.

[0072] It should be noted that after the unit's real power decreases due to reduced efficiency, the actual power of the unit begins to decrease, the load controller has a positive deviation, the steam demand output by the controller slowly increases, and the turbine valve slowly opens. At this time, due to the reduction in the efficiency of the secondary circuit, in order to maintain the stability of the secondary circuit power, the power of the primary circuit begins to rise, the turbine regulating stage pressure rises, for example, slowly increases from 6.0MPa to 6.1MPa, and the output of the pressure controller slowly decreases (eliminating the integral deviation).

[0073] This embodiment can prevent the power of the reactor from being unbalanced, the temperature of the reactor core from fluctuating, and nuclear safety from being affected when the efficiency of the steam turbine changes.

[0074] In one of the optional embodiments, the nuclear power plant reactor-machine coordination control device of this embodiment further includes:

[0075] The acquisition unit is used to acquire the load corresponding to the steam flow instruction, the steam turbine load setting value, the load corresponding to the regulating stage pressure instruction, and the maximum load value. In this embodiment, the relevant loads required in the logic judgment process are first acquired, and then the logic judgment is performed. This embodiment can still maintain the power balance of the reactor when the efficiency of the conventional island is reduced.

[0076] In another preferred embodiment, the computer-readable storage medium of this embodiment stores a computer program, and the computer program is suitable for loading by a processor to execute the steps of the nuclear power plant reactor-machine coordinated control method of the above embodiment.

[0077] This embodiment can avoid causing an imbalance in reactor power under the condition where the thermal efficiency of the conventional island is reduced, and can effectively reduce the impact on reactor temperature control and nuclear safety.

[0078] In another preferred embodiment, the computer device of this embodiment includes a memory and a processor, the memory stores a computer program, and the processor executes the steps of the nuclear power plant reactor coordination control method of the above embodiment by calling the computer program stored in the memory.

[0079] This embodiment can avoid causing an imbalance in reactor power under the condition where the thermal efficiency of the conventional island is reduced, and can effectively reduce the impact on reactor temperature control and nuclear safety.

[0080] The computer-readable storage medium of the present invention can be any computer-readable storage medium that can store program codes, such as a USB flash drive, a mobile hard disk, a read-only memory (ROM), a magnetic disk, or an optical disk.

[0081] The processor of the present invention is used to provide computing and control capabilities to support the operation of the entire device. It should be understood that in the embodiments of the present application, the processor may be a central processing unit (CPU), and the processor may also be other general-purpose processors, digital signal processors (DSP), application-specific integrated circuits (ASIC), field-programmable gate arrays (FPGA) or other programmable logic devices, discrete gates or transistor logic devices, discrete hardware components, etc. Among them, the general-purpose processor may be a microprocessor or the processor may also be any conventional processor, etc.

[0082] 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.

[0083] 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.

[0084] It can be understood that the above embodiments only express the preferred implementation modes of the present invention, and the descriptions thereof are relatively specific and detailed, but they cannot be understood as limiting the patent scope of the present invention. It should be pointed out that, for ordinary technicians in this field, the above technical features can be freely combined without departing from the concept of the present invention, and several deformations and improvements can be made, which all belong to the protection scope of the present invention. Therefore, all equivalent changes and modifications made to the scope of the claims of the present invention should belong to the coverage of the claims of the present invention.

Claims

1. A nuclear power plant reactor-machine coordinated control method, characterized in that: The following steps are involved: S1. Determine a first load from a load corresponding to a steam flow instruction and a turbine load setting value according to a first preset condition; S2. Determine a second load from the load corresponding to the regulating stage pressure instruction and the maximum load value according to a second preset condition; S3, comparing the first load and the second load, and obtaining the minimum value thereof as the minimum load; S4. Generate a corresponding reactor power instruction according to the minimum load.

2. The nuclear power plant reactor-machine coordinated control method according to claim 1, characterized in that: Step S1 includes: The first preset condition includes: Condition 1: The output of the pressure controller is less than the output of the load controller; Condition 2: Detect the rapid drop in load on the turbine; If it is determined that any of the above conditions is met, the load corresponding to the steam flow instruction is used as the first load; if not, the steam turbine load setting value is used as the first load.

3. The nuclear power plant reactor-machine coordinated control method according to claim 1, characterized in that: Step S2 includes: Determine whether the pressure controller output is less than the load controller output; If yes, the load corresponding to the regulating stage pressure instruction is used as the second load; If not, the maximum load value is used as the second load.

4. The nuclear power plant reactor-machine coordinated control method according to claim 1, characterized in that: Before step S1, the method further includes: S0. Obtain the load corresponding to the steam flow command, the turbine load setting value, the load corresponding to the regulating stage pressure command, and the maximum load value.

5. A nuclear power plant reactor-machine coordination control device, characterized in that: include: A first determining unit, configured to determine a first load from a load corresponding to a steam flow instruction and a steam turbine load setting value according to a first preset condition; A second determining unit, configured to determine a second load from a load corresponding to the regulating stage pressure instruction and a maximum load value according to a second preset condition; A comparing unit, configured to compare the first load and the second load, and obtain a minimum value thereof as a minimum load; A generating unit is used to generate a corresponding reactor power instruction according to the minimum load.

6. The nuclear power plant reactor-machine coordinated control device according to claim 5, characterized in that: The first preset condition includes: Condition 1: The output of the pressure controller is less than the output of the load controller; Condition 2: Detect the rapid drop in load on the turbine; The first determination unit is used for: if it is determined that any of the above conditions is met, then the load corresponding to the steam flow instruction is used as the first load; if not, then the steam turbine load setting value is used as the first load.

7. The nuclear power plant reactor-machine coordinated control device according to claim 5, characterized in that: The second determining unit is used for: Determine whether the pressure controller output is less than the load controller output; if so, use the load corresponding to the regulating stage pressure instruction as the second load; if not, use the maximum load value as the second load.

8. The nuclear power plant reactor-machine coordinated control device according to claim 5, characterized in that: Also includes: The acquisition unit is used to obtain the load corresponding to the steam flow instruction, the steam turbine load setting value, the load corresponding to the regulating stage pressure instruction, and the maximum load value.

9. A computer-readable storage medium, characterized in that: The computer-readable storage medium stores a computer program, and the computer program is suitable for being loaded by a processor to execute the steps of the nuclear power plant reactor coordinated control method as described in any one of claims 1 to 4.

10. A computer 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 nuclear power plant reactor machine coordinated control method as described in any one of claims 1 to 4 by calling the computer program stored in the memory.

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