Optimization method and equipment for steam turbine steam bypass participating in nuclear island control logic

The operating status of the steam bypass emission system of the steam turbine is determined by combining multiple preset conditions, which solves the problem of a single fault point in the traditional judgment logic, reduces the risk of reactor jumping, and improves work efficiency.

CN119400473APending Publication Date: 2025-02-07YANGJIANG NUCLEAR POWER
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Patent Information

Application Number
CN202411419052.2
Authority / Receiving Office
CN · China
Patent Type
Applications(China)
Current Assignee / Owner
Filing Date
2024-10-11
Publication Date
2025-02-07

AI Technical Summary

Technical Problem

The conditions for determining whether the traditional steam bypass of the steam bypass participate in the first loop control logic of the reactor are relatively single, which is prone to a single fault point problem, resulting in inconsistent reactor power and turbine load, increasing the risk of jumping the reactor.

Method used

The operating status of the steam bypass emission system of the steam turbine is determined by combining multiple preset conditions, including determining the opening status of the regulating valve and the isolation valve when at least two conditions are triggered, thereby participating in the nuclear island control logic.

Benefits of technology

The defects of a single fault point are eliminated, the risk of reactor jumping, the efficiency of personnel is improved, and the judgment logic of the steam bypass emission system participating in the first-loop control logic of the reactor is effectively optimized.

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Abstract

The invention relates to an optimization method and equipment for a steam turbine steam bypass participating in nuclear island control logic. The method comprises the following steps that when it is determined that a first condition or a second condition is met, it is judged that the steam turbine steam bypass discharge system is in a running state, and the steam turbine steam bypass discharge system participates in nuclear island control logic. The first condition is that the first regulating valve is determined to be opened according to at least two preset conditions, and the first isolating valve is determined to be opened. The second condition is that the second regulating valve is determined to be opened according to at least two preset conditions, and the second isolating valve is determined to be opened. According to the method, the judgment logic of the steam bypass discharge system participating in the primary loop control logic of the reactor is optimized, the defect of a single fault point can be eliminated, and the reactor jump risk is reduced.
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Description

Technical Field

[0001] The invention relates to the technical field of nuclear power steam bypass emission systems, and in particular to an optimization method and device for steam turbine steam bypass participating in nuclear island control logic. Background Art

[0002] The reactor power must follow the changes in the turbine load. When the turbine load drops sharply (such as load rejection, turbine tripping), the reactor power control cannot be as fast as the turbine load change, and there will be an instantaneous inconsistency between the reactor power and the turbine load. At this time, the turbine steam bypass discharge system is put into operation to maintain the power balance between the primary and secondary circuits. When the reactor power is inconsistent with the turbine load, the turbine bypass discharge system provides an "artificial" load for the reactor by discharging excess steam to the condenser and the atmosphere, thereby preventing the temperature and pressure in the nuclear steam supply system (NSSS) from exceeding the protection threshold and ensuring the safety of the power plant.

[0003] Since the steam turbine steam bypass discharge system is equivalent to a user of the reactor primary circuit when it is in operation, it consumes the steam generated by the reactor primary circuit. Therefore, in terms of design, it is necessary to determine whether it needs to participate in the control logic of the reactor primary circuit based on whether it has been put into operation. However, the traditional judgment conditions for determining whether the steam bypass participates in the control logic are relatively simple, which is prone to single point of failure problems. For example, when a device corresponding to the judgment condition fails (such as vibration damage or swing arm jamming), it will directly affect the final power setting value and steam generator water level control, and may eventually lead to isolation of the main feedwater and subsequent reactor tripping. Summary of the invention

[0004] The technical problem to be solved by the present invention is to provide a method and device for optimizing the steam bypass of a turbine participating in the nuclear island control logic, in view of the defect of a single failure point in the judgment logic design of the steam bypass discharge system participating in the primary loop control logic of the reactor.

[0005] The technical solution adopted by the present invention to solve the technical problem is: a method for optimizing the control logic of a steam turbine steam bypass participating in a nuclear island, wherein the steam turbine steam bypass discharge system comprises a first group of valves connected between a discharge main pipe and a temperature and pressure reduction device, wherein the first group of valves comprises a first regulating valve and a first isolation valve connected thereto, a second regulating valve and a second isolation valve connected thereto, and comprises the following steps:

[0006] When it is determined that the first condition or the second condition is met, determining that the steam turbine steam bypass exhaust system is in operation, and making the steam turbine steam bypass exhaust system participate in the nuclear island control logic;

[0007] The first condition is:

[0008] Determining that the first regulating valve is opened according to at least two preset conditions;

[0009] Determining that the first isolation valve is open;

[0010] The second condition is:

[0011] Determining that the second regulating valve is opened according to at least two preset conditions;

[0012] It is determined that the second isolation valve is open.

[0013] Further, in the method for optimizing the control logic of the steam turbine steam bypass participating in the nuclear island according to the present invention, a first closed position limit switch, a first non-closed position limit switch and a first position feedback device are provided on the valve body of the first regulating valve, and the step of determining the opening of the first regulating valve according to at least two preset conditions includes:

[0014] The following conditions are assumed:

[0015] Condition 1: The first off position limit switch triggers a signal indicating that it is in the open state;

[0016] Condition 2: The first non-closed position limit switch triggers a signal indicating that it is in the open state;

[0017] Condition three: the first position feedback device triggers a valve opening feedback signal indicating a valve opening greater than or equal to a preset opening;

[0018] When two or more of the above conditions are met, it is determined that the first regulating valve is in an open state.

[0019] Further, in the method for optimizing the control logic of the steam turbine steam bypass participating in the nuclear island according to the present invention, a second closed position limit switch, a second non-closed position limit switch and a second position feedback device are provided on the valve body of the second regulating valve, and the step of determining the opening of the second regulating valve according to at least two preset conditions includes:

[0020] The following conditions are assumed:

[0021] Condition 4: The second position limit switch triggers a signal indicating that it is in the open state;

[0022] Condition 5: The second non-closed position limit switch triggers a signal indicating that it is in the open state;

[0023] Condition 6: The second position feedback device triggers a valve opening feedback signal indicating that the valve opening is greater than or equal to a preset opening;

[0024] When two or more of the above conditions are met, it is determined that the second regulating valve is in an open state.

[0025] Further, in the method for optimizing the steam turbine steam bypass participating in the nuclear island control logic of the present invention, the signal indicating the open state sent by the first off position limit switch and / or the second off position limit switch is also used to participate in the nuclear island control logic operation; or

[0026] The preset opening degree is 5%.

[0027] Further, in the method for optimizing the control logic of the steam turbine steam bypass participating in the nuclear island according to the present invention, a first open position limit switch is provided on the valve body of the first isolation valve, and the step of determining that the first isolation valve is opened includes:

[0028] When it is detected that the first open position limit switch triggers a signal indicating that the first isolation valve is in the open state, it is determined that the first isolation valve is in the open state.

[0029] Further, in the method for optimizing the control logic of the steam turbine steam bypass participating in the nuclear island according to the present invention, a second open position limit switch is provided on the valve body of the second isolation valve, and the step of determining that the second isolation valve is opened includes:

[0030] When it is detected that the second open position limit switch triggers a signal indicating that the second isolation valve is in the open state, it is determined that the second isolation valve is in the open state.

[0031] Further, in the method for optimizing the steam turbine steam bypass participating in the nuclear island control logic of the present invention, the step of making the steam turbine steam bypass exhaust system participate in the nuclear island control logic includes:

[0032] The relevant valve opening information of the steam turbine steam bypass discharge system is used to participate in the nuclear island main feed water flow control operation and the final power setting value control operation.

[0033] In addition, the present invention also provides an optimization device for a steam turbine steam bypass participating in a nuclear island control logic, wherein the steam turbine steam bypass discharge system comprises a first group of valves connected between a discharge main pipe and a temperature and pressure reduction device, wherein the first group of valves comprises a first regulating valve and a first isolation valve connected thereto, a second regulating valve and a second isolation valve connected thereto, and the optimization device comprises:

[0034] A judgment unit, used for judging that the steam turbine steam bypass exhaust system is in operation when it is determined that the first condition or the second condition is satisfied, and making the steam turbine steam bypass exhaust system participate in the nuclear island control logic;

[0035] A first condition setting unit, used to determine the first regulating valve is opened according to at least two preset conditions; used to determine the first isolation valve is opened;

[0036] The second condition setting unit is used to determine the opening of the second regulating valve according to at least two preset conditions; and is used to determine the opening of the second isolation valve.

[0037] 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 optimization method of the turbine steam bypass participating in the nuclear island control logic as described above.

[0038] 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 method for optimizing the control logic of the nuclear island in which the turbine steam bypass participates by calling the computer program stored in the memory.

[0039] The optimization method and device for the steam turbine steam bypass participating in the nuclear island control logic of the present invention have the following beneficial effects: the present invention optimizes the judgment logic of the steam bypass discharge system participating in the reactor primary loop control logic, can eliminate the defects of a single fault point, and reduce the risk of reactor tripping. At the same time, it can also effectively improve the work efficiency of personnel. BRIEF DESCRIPTION OF THE DRAWINGS

[0040] The present invention will be further described below with reference to the accompanying drawings and embodiments, in which:

[0041] Figure 1 It is a flow chart of a method for optimizing the steam turbine steam bypass participating in the nuclear island control logic provided by an embodiment of the present invention;

[0042] Figure 2 is a schematic structural diagram of a steam turbine steam bypass exhaust system provided by an embodiment of the present invention;

[0043] Figure 3 It is a simplified logic diagram for judging the operation status of a steam turbine steam bypass discharge system provided by an embodiment of the present invention;

[0044] Figure 4 It is a simplified logic diagram for judging the operation status of a steam bypass emission system of a steam turbine in the related technology. DETAILED DESCRIPTION

[0045] 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.

[0046] 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.

[0047] 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.

[0048] It should be understood that although the terms first, second, third, etc. may be used to describe various information or define components in the embodiments of the present invention, such 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. Or these terms are only for the convenience of distinguishing the corresponding components. If not otherwise stated, the above words have no special meaning and therefore cannot be understood as limiting the scope of protection of this application.

[0049] 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.

[0050] In the figure, CEX represents the condensate pump, and 127VL and 125VL represent two air shut-off valves connected between the condensate pump and the temperature and pressure reduction device.

[0051] In one embodiment provided by the present invention, the steam turbine steam bypass discharge system includes a first valve group connected between the discharge main pipe and the temperature and pressure reduction device, and the first valve group includes a first regulating valve and a first isolation valve connected thereto, and a second regulating valve and a second isolation valve connected thereto. That is, the first isolation valve is an upstream isolation valve of the first regulating valve, and the second isolation valve is an upstream isolation valve of the second regulating valve. For example, Figure 2As shown, in the steam turbine steam bypass discharge system (GCT system), two discharge main pipes are led out from both ends of the main steam main pipe (VVP), and then 14 discharge branch pipes are connected from the discharge main pipe. There is a manual isolation valve and a pneumatic control valve on each discharge pipe. According to the regulation requirements, these 14 valves are divided into 4 groups, among which the first group of valves is GCT121VV / GCT117VV / GCT113VV. In the figure, GCT121VV is the first control valve, GCT109VV is the first isolation valve, GCT117VV is the second control valve, and GCT105VV is the second isolation valve. It should be noted that the main steam main pipe is a pipeline connected to the reactor to transport the steam generated by the reactor.

[0052] refer to Figure 1 The method for optimizing the steam turbine steam bypass participating in the nuclear island control logic of this embodiment comprises the following steps:

[0053] When it is determined that the first condition or the second condition is met, it is determined that the steam turbine steam bypass exhaust system is in operation, and the steam turbine steam bypass exhaust system is made to participate in the nuclear island control logic.

[0054] Specifically, the nuclear island control logic (or the nuclear island important control logic) mainly includes the nuclear island main feed water flow control and the final power setting value control. When the steam turbine steam bypass discharge system is in operation, the relevant valve opening information of the steam turbine steam bypass discharge system is used to participate in the nuclear island main feed water flow control calculation and the final power setting value control calculation.

[0055] It can be understood that when the GCT system is not in operation and only the steam turbine is generating electricity, the final power setting value of the unit is set to 30% or the power before the steam turbine trip (the smaller of the two), and the steam generator water level setting value depends on the secondary circuit load represented by the steam turbine power; when the GCT is in operation, the final power setting value of the unit depends on the GCT system opening, and the steam generator water level depends on the steam turbine power and the secondary circuit load represented by the steam turbine system opening.

[0056] The first condition is: determine that the first regulating valve is open according to at least two preset conditions. Determine that the first isolation valve is open. The second condition is: determine that the second regulating valve is open according to at least two preset conditions. Determine that the second isolation valve is open. It should be noted that the preset conditions for determining that the first regulating valve is open and the second regulating valve is open are similar, but not exactly the same. The specific preset conditions will be described in detail below.

[0057] It can be understood that when the steam turbine steam bypass exhaust system is in operation, it is equivalent to a user of the reactor primary circuit and consumes the steam generated by the reactor primary circuit. Therefore, in terms of design, it is necessary to determine whether it needs to participate in the control logic of the reactor primary circuit based on whether it has been put into operation. Figure 2 For example, when GCT121VV and its upstream manual isolation valve are both in the open state, or when GCT117VV and its upstream manual isolation valve are both in the open state, the steam turbine bypass emission system is considered to be in operation. At this time, the steam turbine bypass emission system participates in the operation of the important control logic of the nuclear island, that is, the steam turbine bypass emission system needs to be considered in the operation of the important control logic of the nuclear island.

[0058] In this embodiment, the opening judgment conditions of the two regulating valves for judging whether the steam bypass discharge system of the steam turbine is in operation (in operation) are improved from a single judgment condition to a combination of multiple judgment conditions, which can effectively solve and eliminate the unsafe effects of the original single judgment condition such as reactor tripping when a single fault point occurs in the corresponding equipment. In other words, this embodiment can eliminate the defects of a single fault point and reduce the risk of reactor tripping by optimizing the judgment logic of the steam bypass discharge system participating in the control logic of the reactor primary loop. At the same time, it can also effectively improve the work efficiency of personnel.

[0059] In one embodiment, Figure 3 The schematic diagram of the logic for judging the commissioning status of the steam bypass discharge system of the steam turbine of the present invention is shown. The valve body of the first regulating valve is provided with a first closed position limit switch, a first non-closed position limit switch and a first position feedback device. The method for optimizing the control logic of the steam bypass of the steam turbine in this embodiment, in the step of determining the opening of the first regulating valve according to at least two preset conditions, includes:

[0060] The following conditions are assumed:

[0061] Condition 1: The first position limit switch triggers a signal indicating that it is in the open state. Figure 2 and Figure 3 For example, the first position limit switch is the SM5 limit switch of GCT121VV, and the corresponding SM5 signal is sent. Preferably, the signal indicating the open state sent by the first position limit switch is also used to participate in the nuclear island control logic operation.

[0062] Condition 2: The first non-closed position limit switch triggers a signal indicating that it is in the open state. Figure 2 and Figure 3 For example, the first non-closing position limit switch is the SM6 limit switch of GCT121VV, and the corresponding SM6 signal is emitted.

[0063] Condition 3: The first position feedback device triggers a valve opening feedback signal that is greater than or equal to the preset opening. Figure 2 and Figure 3 For example, the first position feedback device is GCT121VVP. Optionally, the preset opening degree may be 5%.

[0064] When two or more of the above conditions are met, it is determined that the first regulating valve is in an open state.

[0065] It should be noted that, in the present invention, both the closed position limit switch and the non-closed position limit switch are installed in the closed position of the valve. The closed position limit switch (or the closed indicating limit switch) refers to the limit switch connected to the normally open node, and the non-closed position limit switch (or the open indicating limit switch) refers to the limit switch connected to the normally closed node. Specifically, Figure 3 As shown in the figure, the signal sent by the closed position limit switch is the SM5 signal. When the SM5 signal is 0, it indicates that the valve is in the open state, and when the SM5 signal is 1, it indicates that the valve is in the closed state. The signal sent by the non-closed position limit switch is the SM6 signal. When the SM6 signal is 0, it indicates that the valve is in the closed state, and when the SM6 signal is 1, it indicates that the valve is in the open state. The difference between the SM6 signal and the SM5 signal is that the SM6 signal is only used to display the alarm and does not participate in the important control logic operation of the nuclear island, while the SM5 signal is also used to participate in the important control logic operation of the nuclear island.

[0066] Figure 4 A simplified logic diagram for judging the operation status of a steam bypass exhaust system of a steam turbine in the related art is shown.

[0067] In the figure, the state of the SM5 signal (close indication switch signal) of GCT121 / 117VV is used as a single condition to determine whether the valve is open. If it is 0, it means the valve is open, if it is 1.

[0068] The present invention mainly aims at the improvement of software. Corresponding equipment is already available in hardware and no additional equipment is needed. For example, the valve bodies of the regulating valve and the isolation valve are provided with corresponding limit switches. Therefore, the scheme of the present invention does not need to make relevant improvements in hardware, further reducing the implementation cost and further improving the feasibility of the scheme.

[0069] In this embodiment, the SM5 signal (closed indicating switch signal), SM6 signal (valve in non-closed position indicating switch) and valve opening feedback signal of the GCT121VV valve are used as judgment signals for judging whether the GCT121VV valve is open. When the SM5 signal (closed indicating switch signal) of the GCT121VV is 0, SM6 (valve in non-closed position indicating switch) is 1 and the GCT121VVP (valve opening feedback signal) is ≥5% opening, as long as two of the above three signals are satisfied, it means that the GCT121VV valve is in an open state. If it is determined that the corresponding upstream isolation valve GCT109VV is also in an open state, the GCT system participates in the main water supply flow control and the final power setting value control, otherwise it does not participate in the above control.

[0070] This embodiment optimizes the opening judgment conditions of the two regulating valves that judge whether the steam bypass discharge system of the steam turbine is in operation (in operation), and improves it from a single judgment condition to a combination of multiple judgment conditions, which can effectively solve and eliminate the unsafe effects such as reactor tripping when a single failure point occurs in the corresponding equipment under the original single judgment condition. In other words, this embodiment solves the problem that when the SM5 limit switch of GCT121VV or GCT117VV is damaged due to vibration or the swing arm is stuck, it will directly affect the accuracy of the important control logic of the nuclear island, and ultimately lead to the isolation of the main feed water and subsequent reactor tripping. The single failure point problem is effectively avoided by the combination of multiple judgment conditions. It can also reduce the risk of damage to the magnetic strip on the feedback device.

[0071] In one embodiment, a second closed position limit switch, a second non-closed position limit switch and a second position feedback device are provided on the valve body of the second regulating valve. The method for optimizing the control logic of the steam bypass of the steam turbine participating in the nuclear island in this embodiment, in the step of determining the opening of the second regulating valve according to at least two preset conditions, includes:

[0072] The following conditions are assumed:

[0073] Condition 4: The second position limit switch triggers a signal indicating that it is in the open state. Figure 2 and Figure 3 For example, the second position limit switch is the SM5 limit switch of GCT117VV, and the corresponding SM5 signal is sent. Preferably, the signal indicating the open state sent by the second position limit switch is also used to participate in the nuclear island control logic operation.

[0074] Condition 5: The second non-closed position limit switch triggers a signal indicating that it is in the open state. Figure 2 and Figure 3 For example, the second non-closing position limit switch is the SM6 limit switch of GCT117VV, and the corresponding SM6 signal is emitted.

[0075] Condition 6: The second position feedback device triggers a valve opening feedback signal that is greater than or equal to the preset opening. Figure 2 and Figure 3 For example, the second position feedback device is GCT117VVP. Optionally, the preset opening degree may be 5%.

[0076] When two or more of the above conditions are met, it is determined that the second regulating valve is in the open state.

[0077] In this embodiment, the GCT117VV valve SM5 signal (closed indication switch signal), SM6 (valve is in a non-closed position indication switch, used to indicate the switch state of the valve) and the valve opening feedback signal (the signal is sent by the valve position feedback device) are used together as judgment signals for judging whether the GCT117VV valve is open.

[0078] Optionally, a first open position limit switch is provided on the valve body of the first isolation valve, and the step of determining whether the first isolation valve is opened includes:

[0079] When it is detected that the first open position limit switch triggers a signal indicating that the first isolation valve is in the open state, it is determined that the first isolation valve is in the open state.

[0080] like Figure 3 As shown, when it is determined that the first regulating valve is in the open state, if the SM3 signal (open indication switch signal) of the corresponding upstream isolation valve GCT109VV is 1 signal, the GCT system participates in the main water supply flow control and the final power setting value control, otherwise it does not participate in the above control.

[0081] Optionally, a second open position limit switch is provided on the valve body of the second isolation valve, and the step of determining whether the second isolation valve is opened includes:

[0082] When it is detected that the second open position limit switch triggers a signal indicating that the second isolation valve is in the open state, it is determined that the second isolation valve is in the open state.

[0083] like Figure 3 As shown, when it is determined that the second regulating valve is in the open state, if the SM3 signal (open indication switch signal) of the corresponding upstream isolation valve GCT105VV is 1 signal, the GCT system participates in the main water supply flow control and the final power setting value control, otherwise it does not participate in the above control.

[0084] In another preferred embodiment of the present invention, the steam turbine steam bypass participating in the optimization device of the nuclear island control logic of this embodiment comprises:

[0085] The judgment unit is used to determine that the steam turbine steam bypass exhaust system is in operation when it is determined that the first condition or the second condition is met, and to make the steam turbine steam bypass exhaust system participate in the nuclear island control logic.

[0086] The first condition setting unit is used to determine the opening of the first regulating valve according to at least two preset conditions. It is used to determine the opening of the first isolation valve.

[0087] The second condition setting unit is used to determine the opening of the second regulating valve according to at least two preset conditions. It is used to determine the opening of the second isolation valve.

[0088] This embodiment optimizes the judgment logic of the steam bypass discharge system participating in the primary loop control logic of the reactor, can eliminate the defects of single fault points, and reduce the risk of reactor trip. At the same time, it can also effectively improve the work efficiency of personnel.

[0089] As Figure 2 shown, the steam bypass discharge system of the steam turbine mainly includes four groups of valves, namely the first group of valves, the second group of valves, the third group of valves and the fourth group of valves. The four groups of valves will not be opened simultaneously, but are opened in sequence according to specific steam discharge requirements. First, the first group of valves is opened, then the second group of valves is opened, then the third group of valves, and finally the fourth group of valves. When the first group of valves is opened, they are opened one by one. First, GCT121VV is opened. After GCT121VV is fully opened, GCT117VV is opened. After GCT117VV is fully opened, GCT113VV is opened. Since there is a sequence in the operation process of GCT, the opening of some valves in the first group of valves is considered as the system being put into operation.

[0090] The specific opening principle of the corresponding valves of the GCT system is as follows: Under normal circumstances, a secondary loop temperature T2 is calculated from the secondary loop load and compared with the primary loop coolant temperature T1. During normal operation of the unit, T1 = T2 and GCT is not put into operation. When the steam turbine quickly reduces load or trips, when T2 decreases and T2 < T1, at this time, the difference between T2 and T1 will control the opening of the 4 groups of valves of GCT. The greater the difference, the more valve groups will be opened. The pneumatic regulating valves downstream of each branch pipe can adjust the opening degree arbitrarily and are adjusted according to the temperature difference between T1 and T2.

[0091] It should be noted that in the present invention, only the single faults of GCT121VV and GCT117VV SM5 are proposed because only SM5 participates in the logic on the valves of GCT121VV and GCT117VV (participates in judging whether the valves are opened, and then judges whether the GCT system is put into operation, and then judges the setting method of the final power setting value and the steam generator water level setting value). The SM3 of the valves of GCT121VV and GCT117VV does not participate in the logic judgment, so the single faults of SM3 of the valves of GCT121VV and GCT117VV are not considered. In addition, the single faults of GCT109VV and GCT105VV SM3 are not considered in this solution mainly because the vibration of GCT109VV and GCT105VV SM3 is small and there has never been a problem of swing arm jamming, so the single fault problem does not need to be considered.

[0092] In another preferred embodiment of the present invention, the computer-readable storage medium of this embodiment stores a computer program, and the computer program is suitable for being loaded by a processor to execute the steps of the optimization method of the steam bypass of the steam turbine participating in the nuclear island control logic as described in the above embodiment.

[0093] This embodiment optimizes the judgment logic of the steam bypass discharge system participating in the control logic of the reactor primary loop, which can eliminate the defects of a single fault point and reduce the risk of reactor tripping. At the same time, it can also effectively improve the work efficiency of personnel.

[0094] In another preferred embodiment of the present invention, 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 method for optimizing the control logic of the nuclear island participating in the steam bypass of the turbine as in the above embodiment by calling the computer program stored in the memory.

[0095] This embodiment optimizes the judgment logic of the steam bypass discharge system participating in the control logic of the reactor primary loop, which can eliminate the defects of a single fault point and reduce the risk of reactor tripping. At the same time, it can also effectively improve the work efficiency of personnel.

[0096] 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.

[0097] 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.

[0098] 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.

[0099] 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.

[0100] 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 method for optimizing the control logic of a steam turbine steam bypass participating in a nuclear island, wherein the steam turbine steam bypass discharge system comprises a first set of valves connected between a discharge main pipe and a temperature and pressure reduction device, wherein the first set of valves comprises a first regulating valve and a first isolation valve connected thereto, a second regulating valve and a second isolation valve connected thereto, wherein: The following steps are involved: When it is determined that the first condition or the second condition is met, determining that the steam turbine steam bypass exhaust system is in operation, and making the steam turbine steam bypass exhaust system participate in the nuclear island control logic; The first condition is: Determining that the first regulating valve is opened according to at least two preset conditions; Determining that the first isolation valve is open; The second condition is: Determining that the second regulating valve is opened according to at least two preset conditions; It is determined that the second isolation valve is open.

2. The method for optimizing the control logic of the steam turbine steam bypass participating in the nuclear island according to claim 1, characterized in that: The valve body of the first regulating valve is provided with a first closed position limit switch, a first non-closed position limit switch and a first position feedback device. The step of determining that the first regulating valve is opened according to at least two preset conditions includes: The following conditions are assumed: Condition 1: The first off position limit switch triggers a signal indicating that it is in the open state; Condition 2: The first non-closed position limit switch triggers a signal indicating that it is in the open state; Condition three: the first position feedback device triggers a valve opening feedback signal indicating a valve opening greater than or equal to a preset opening; When two or more of the above conditions are met, it is determined that the first regulating valve is in an open state.

3. The method for optimizing the control logic of the steam turbine steam bypass participating in the nuclear island according to claim 1, characterized in that: The valve body of the second regulating valve is provided with a second closed position limit switch, a second non-closed position limit switch and a second position feedback device. The step of determining the opening of the second regulating valve according to at least two preset conditions includes: The following conditions are assumed: Condition 4: The second position limit switch triggers a signal indicating that it is in the open state; Condition 5: The second non-closed position limit switch triggers a signal indicating that it is in the open state; Condition 6: The second position feedback device triggers a valve opening feedback signal indicating that the valve opening is greater than or equal to a preset opening; When two or more of the above conditions are met, it is determined that the second regulating valve is in an open state.

4. The method for optimizing the control logic of the steam turbine steam bypass participating in the nuclear island according to claim 2 or 3, characterized in that: The signal indicating the open state sent by the first closing position limit switch and / or the second closing position limit switch is also used to participate in the nuclear island control logic operation; or The preset opening degree is 5%.

5. The method for optimizing the control logic of the steam turbine steam bypass participating in the nuclear island according to claim 1, characterized in that: A first open position limit switch is provided on the valve body of the first isolation valve. The step of determining that the first isolation valve is opened includes: When it is detected that the first open position limit switch triggers a signal indicating that the first isolation valve is in the open state, it is determined that the first isolation valve is in the open state.

6. The method for optimizing the control logic of the steam turbine steam bypass participating in the nuclear island according to claim 1, characterized in that: A second open position limit switch is provided on the valve body of the second isolation valve. The step of determining that the second isolation valve is opened includes: When it is detected that the second open position limit switch triggers a signal indicating that the second isolation valve is in the open state, it is determined that the second isolation valve is in the open state.

7. The method for optimizing the control logic of the steam turbine steam bypass participating in the nuclear island according to claim 1, characterized in that: The step of enabling the steam turbine steam bypass exhaust system to participate in the nuclear island control logic includes: The relevant valve opening information of the steam turbine steam bypass discharge system is used to participate in the nuclear island main feed water flow control operation and the final power setting value control operation.

8. A steam turbine steam bypass optimization device for participating in nuclear island control logic, wherein the steam turbine steam bypass discharge system comprises a first set of valves connected between the discharge main pipe and the temperature and pressure reduction device, wherein the first set of valves comprises a first regulating valve and a first isolation valve connected thereto, a second regulating valve and a second isolation valve connected thereto, wherein: include: A judgment unit, used for judging that the steam turbine steam bypass exhaust system is in operation when it is determined that the first condition or the second condition is satisfied, and making the steam turbine steam bypass exhaust system participate in the nuclear island control logic; A first condition setting unit, used for determining that the first regulating valve is opened according to at least two preset conditions; Used to determine that the first isolation valve is open; A second condition setting unit, used for determining the opening of the second regulating valve according to at least two preset conditions; Used to determine that the second isolation valve is open.

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 method for optimizing the steam turbine steam bypass participating in the nuclear island control logic as described in any one of claims 1 to 7.

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 method for optimizing the steam bypass of a turbine participating in the control logic of a nuclear island as described in any one of claims 1 to 7 by calling the computer program stored in the memory.