Method for controlling pressure of bypass system of steam turbine under emergency shutdown condition of sodium-cooled fast reactor

Abstract

The invention particularly relates to a steam turbine bypass system pressure control method under the emergency shutdown condition of a sodium-cooled fast reactor. The method comprises the steps that an automatic pressure reduction input signal of a steam turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor is generated; generating and outputting a main steam header pressure set value according to an automatic pressure reduction input signal of a steam turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor; according to the difference value between the main steam header pressure measurement value and the output main steam header pressure set value, a bypass valve position set value is calculated, and a bypass valve position control signal is generated and output to a bypass valve; and the bypass valve adjusts the valve position according to the output bypass valve position control signal. The invention further relates to a steam turbine bypass system pressure control device under the emergency shutdown working condition of the sodium-cooled fast reactor, computer equipment and storage equipment. Automatic pressure reduction of the steam turbine bypass system under the emergency shutdown working condition of the sodium-cooled fast reactor is achieved.

Description

Technical Field

[0001] The present invention relates to the technical field of pressure control of a steam turbine bypass system under an emergency shutdown condition of a sodium-cooled fast reactor, and in particular to a method, device, computer equipment and storage device for pressure control of a steam turbine bypass system under an emergency shutdown condition of a sodium-cooled fast reactor. Background Art

[0002] The steam turbine bypass system of a sodium-cooled fast reactor is different from that of a pressurized water reactor. It adopts the "machine-follow-the-pile" operation mode and has a 100% bypass discharge capacity. After the emergency shutdown of a sodium-cooled fast reactor, the operator needs to manually control the pressure of the main steam header to drop from 13MPa to 8MPa. This operation mode has the following problems:

[0003] 1. After the emergency shutdown of the sodium-cooled fast reactor, the operator has many control tasks for the unit and is very busy. The main steam header pressure reduction process needs to be carried out slowly and continuously, and the main steam header pressure reduction rate is 0.5MPa / min. The main steam header pressure reduction takes too long. This causes the main steam header pressure reduction to be carried out simultaneously with other important control tasks of the unit, increasing the burden and control risk of the operator, and it is very likely to lead to an escalation of the accident due to inaccurate control process or sudden major failure of a system.

[0004] 2. The main steam manifold pressure is a key factor affecting the steam superheat at the steam generator outlet. The higher the main steam manifold pressure, the higher the steam saturation temperature at the steam generator outlet, and the lower the steam superheat at the steam generator outlet. When the steam superheat at the steam generator outlet drops to a certain value, it will cause the steam generator to be isolated and then the double loop to be cut off, causing the accident to expand. During the emergency shutdown of the sodium-cooled fast reactor, the heat generation of the sodium-cooled fast reactor will decrease sharply, and the temperature of the main steam manifold will drop, causing the steam superheat at the steam generator outlet to decrease. Therefore, it is necessary to timely reduce the main steam manifold pressure and the steam saturation temperature at the steam generator outlet to ensure the steam superheat at the steam generator outlet. Manual control of the main steam manifold pressure has the problems of untimely control and low control accuracy. Summary of the invention

[0005] The purpose of the present invention is to provide a method, device, calculation and equipment and storage device for controlling the pressure of a steam turbine bypass system under an emergency shutdown condition of a sodium-cooled fast reactor, so as to realize automatic pressure control of the steam turbine bypass system under an emergency shutdown condition of a sodium-cooled fast reactor.

[0006] In order to achieve the above object, the present invention provides the following technical solutions:

[0007] A method for controlling the pressure of a steam turbine bypass system under an emergency shutdown condition of a sodium-cooled fast reactor comprises the following steps:

[0008] Generate automatic pressure reduction input signal for steam turbine bypass system under emergency shutdown condition of sodium-cooled fast reactor;

[0009] According to the automatic pressure reduction input signal of the turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor, the main steam header pressure setting value is generated and output;

[0010] Calculate the bypass valve total valve position setting value according to the difference between the main steam header pressure measurement value and the output main steam header pressure setting value; calculate the bypass valve position setting value according to the bypass valve total valve position setting value, generate the bypass valve position control signal and output it to the bypass valve;

[0011] The bypass valve adjusts the valve position according to the output bypass valve position control signal.

[0012] As one of the achievable methods, an automatic pressure reduction input signal for the steam turbine bypass system under the emergency shutdown condition of a sodium-cooled fast reactor is generated by satisfying any of the following two conditions:

[0013] (1) The main steam header pressure setting value is higher than 8MPa, and there is a sodium-cooled fast reactor emergency shutdown pulse signal;

[0014] (2) The main steam header pressure setting value is higher than 8 MPa, and the operator inputs the automatic pressure reduction start-up command of the turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor.

[0015] As one of the feasible methods, according to the automatic pressure reduction input signal of the turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor, the main steam header pressure setting value is generated, including the following steps:

[0016] When the automatic pressure reduction signal of the turbine bypass system exists for 0.5s under the emergency shutdown condition of the sodium-cooled fast reactor, the main steam header pressure target value is automatically set to 8MPa;

[0017] When the automatic pressure reduction input signal of the turbine bypass system exists under the emergency shutdown condition of the sodium-cooled fast reactor, the change rate of the main steam header pressure set value to the main steam header pressure target value is automatically set to 0.00833MPa / s.

[0018] As one of the feasible ways, when the turbine trip signal is within 0.5s or the turbine bypass system automatic pressure reduction input signal is within 0.5s under the emergency shutdown condition of the sodium-cooled fast reactor, the output main steam header pressure setting value is directly the smaller of the main steam header pressure setting value and 13MPa.

[0019] As one of the achievable ways, the method for controlling the automatic pressure reduction of the steam turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor also includes: generating an automatic pressure reduction removal signal of the steam turbine bypass under the emergency shutdown condition of the sodium-cooled fast reactor;

[0020] If any of the following three conditions is met, an automatic pressure reduction cut-off signal for the steam turbine bypass system under emergency shutdown conditions of a sodium-cooled fast reactor is generated:

[0021] (1) The bypass valve control mode is manual control mode;

[0022] (2) The operator inputs the automatic pressure reduction and removal command of the turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor;

[0023] (3) Under the emergency shutdown condition of the sodium-cooled fast reactor, when the automatic pressure reduction signal of the turbine bypass system exists and the main steam header pressure setting value drops to (7.9-8.1) MPa, it will open after a 3s delay and then close after a 2s delay.

[0024] As one of the possible ways, when any of the following two conditions are met, the valve position setting value of the bypass valve that limits the output is increased to prevent the pressure of the turbine bypass system from oscillating:

[0025] (1) The turbine trip signal is within 0.5s or the turbine bypass system automatic pressure reduction input signal is within 0.5s under the emergency shutdown condition of the sodium-cooled fast reactor;

[0026] (2) There is no turbine trip signal, the bypass valve position setting value is less than 0, and the measured value of the main steam header pressure is less than the set value;

[0027] (3) The turbine speed is less than 100 rpm, the bypass valve position is less than 0, and the measured value of the main steam header pressure is less than the set value.

[0028] As one of the achievable ways, when there is a fault signal of all the pressure transmitters of the main steam header, the lock generates a bypass valve position control signal according to the calculated bypass valve position setting value, and uses the bypass valve position setting value input by the operator to generate the bypass valve position control signal to control the bypass valve position;

[0029] When there is a signal that all the pressure transmitters in the main steam header have failed, the bypass valve position control signal generated according to the calculated bypass valve position setting value is unlocked, and the bypass valve position control signal generated by the calculated bypass valve position setting value is used again to control the bypass valve.

[0030] As one of the feasible ways, a plurality of bypass valves connected in parallel are provided in the turbine bypass system, and the plurality of bypass valves are put into regulation at the same time;

[0031] According to the total valve position setting value of the bypass valve, the valve position setting value of the bypass valve is calculated based on the equation function f(x);

[0032] f(x)=[min(nx-(n-1)×100,100); max(nx-(n-1)×100,0)];

[0033] Wherein, f(x) is the bypass valve position setting value, the minimum bypass valve position setting value is the smaller value between nx-(n-1)×100 and 100, the maximum bypass valve position setting value is the larger value between nx-(n-1)×100 and 0, x is the total bypass valve position setting value, and n is the number of bypass valves.

[0034] In order to achieve the above object, the present invention also provides a pressure control device for a steam turbine bypass system under emergency shutdown conditions of a sodium-cooled fast reactor, comprising:

[0035] An automatic pressure reduction input signal generation module is used to generate an automatic pressure reduction input signal for the steam turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor and output it to the pressure setting value generation module;

[0036] An automatic pressure reduction cut-off signal generation module is used to generate an automatic pressure reduction cut-off signal for the steam turbine bypass under emergency shutdown conditions of a sodium-cooled fast reactor;

[0037] A pressure setting value generation module is used to generate a main steam header pressure setting value according to an automatic pressure reduction input signal of a steam turbine bypass system under an emergency shutdown condition of a sodium-cooled fast reactor, and output the value to a valve position control signal generation module;

[0038] An increase limiting module, used for limiting the increase of the bypass valve position setting value output by the pressure setting value generating module;

[0039] A valve position control signal generating module is used to calculate the total valve position setting value of the bypass valve according to the difference between the main steam header pressure measurement value and the main steam header pressure setting value; calculate the bypass valve position setting value according to the bypass valve total valve position setting value, generate a bypass valve position control signal and output it to the bypass valve;

[0040] The locking module is used to lock or unlock the valve position control signal generating module to generate the bypass valve position control signal according to the calculated bypass valve position setting value; the bypass valve position control signal is generated by the bypass valve position setting value manually input by the operator;

[0041] The bypass valve adjusts the valve position according to the output bypass valve position control signal.

[0042] In order to achieve the above-mentioned purpose, the present invention also provides a computer device, including a memory and a processor, wherein the memory stores computer-readable instructions, and when the processor executes the computer-readable instructions, the steps of the turbine bypass system pressure control method under the emergency shutdown condition of the sodium-cooled fast reactor are implemented.

[0043] In order to achieve the above-mentioned purpose, the present invention also provides a computer-readable storage medium, on which computer-readable instructions are stored. When the computer-readable instructions are executed, the steps of the turbine bypass system pressure control method under the emergency shutdown condition of the sodium-cooled fast reactor are implemented.

[0044] Beneficial technical effects of the present invention:

[0045] The method, device, computer equipment and storage device for controlling the pressure of a turbine bypass system under an emergency shutdown condition of a sodium-cooled fast reactor of the present invention automatically set a set value and a target value of the pressure of a main steam header after an emergency shutdown of the sodium-cooled fast reactor, and limit the rate of change from the set value of the pressure of the main steam header to the target value, so that the set value of the pressure of the main steam header is gradually approached to the target value. When the set value of the pressure of the main steam header reaches the target value, the pressure reduction operation of the main steam header is completed, and the automatic pressure reduction of the main steam header is realized, thereby avoiding the uncertainty disturbance introduced by the operator's manual pressure reduction operation of the main steam header, reducing the burden of the operator in the process of reducing the pressure of the main steam header after the emergency shutdown of the sodium-cooled fast reactor, increasing the steam superheat at the outlet of the steam generator, avoiding the single-loop / dual-loop removal of the secondary circuit due to the low superheat of the steam at the outlet of the steam generator, thereby avoiding the expansion of the accident, and preparing for the water-steam conversion operation of the steam generator. BRIEF DESCRIPTION OF THE DRAWINGS

[0046] Figure 1 It is a flow chart of an embodiment of a method for controlling the pressure of a steam turbine bypass system under emergency shutdown conditions of a sodium-cooled fast reactor according to the present invention;

[0047] Figure 2 It is a schematic structural view of an embodiment of a pressure control device for a steam turbine bypass system under emergency shutdown conditions of a sodium-cooled fast reactor according to the present invention;

[0048] Figure 3 The figure is a schematic structural view of an embodiment of a computer device of the present invention. DETAILED DESCRIPTION

[0049] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as commonly understood by technicians in the technical field to which this application belongs; the terms used in the specification of the application are only for the purpose of describing specific embodiments and are not intended to limit this application; the terms "including" and "having" and any variations thereof in the specification and claims of this application and the above-mentioned figure descriptions are intended to cover non-exclusive inclusions.

[0050] Reference to "embodiments" herein means that a particular feature, structure, or characteristic described in conjunction with the embodiments may be included in at least one embodiment of the present application. The appearance of the phrase in various locations in the specification does not necessarily refer to the same embodiment, nor is it an independent or alternative embodiment that is mutually exclusive with other embodiments. It is explicitly and implicitly understood by those skilled in the art that the embodiments described herein may be combined with other embodiments.

[0051] The technical solution of the present invention is clearly and completely described below in conjunction with the accompanying drawings and specific embodiments.

[0052] refer to Figure 1 , a flow chart of an embodiment of a method for controlling the pressure of a steam turbine bypass system under an emergency shutdown condition of a sodium-cooled fast reactor is shown, wherein the method for controlling the pressure of a steam turbine bypass system under an emergency shutdown condition of a sodium-cooled fast reactor comprises the following steps:

[0053] Generate automatic pressure reduction input signal for steam turbine bypass system under emergency shutdown condition of sodium-cooled fast reactor;

[0054] According to the automatic pressure reduction input signal of the turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor, the main steam header pressure setting value is generated and output;

[0055] Calculate the bypass valve total valve position setting value according to the difference between the main steam header pressure measurement value and the output main steam header pressure setting value; calculate the bypass valve position setting value according to the bypass valve total valve position setting value, generate the bypass valve position control signal and output it to the bypass valve;

[0056] The bypass valve adjusts the valve position according to the output bypass valve position control signal.

[0057] In this embodiment, as one of the achievable methods, any one of the following two conditions is met to generate an automatic pressure reduction input signal for the steam turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor:

[0058] (1) The main steam header pressure setting value is higher than 8MPa, and there is a sodium-cooled fast reactor emergency shutdown pulse signal;

[0059] (2) The main steam header pressure setting value is higher than 8 MPa, and the operator inputs the automatic pressure reduction start-up command of the turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor.

[0060] In this embodiment, as one of the achievable methods, according to the automatic pressure reduction input signal of the turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor, the main steam header pressure setting value is generated, including the following steps:

[0061] When the automatic pressure reduction signal of the turbine bypass system exists for 0.5s under the emergency shutdown condition of the sodium-cooled fast reactor, the main steam header pressure target value is automatically set to 8MPa;

[0062] When the automatic pressure reduction input signal of the turbine bypass system exists under the emergency shutdown condition of the sodium-cooled fast reactor, the change rate of the main steam header pressure set value to the main steam header pressure target value is automatically set to 0.00833MPa / s.

[0063] In this embodiment, as one of the feasible ways, when the turbine trip signal is within 0.5s or the turbine bypass system automatic pressure reduction input signal is within 0.5s under the emergency shutdown condition of the sodium-cooled fast reactor, the output main steam manifold pressure setting value is directly the smaller of the main steam manifold pressure setting value and 13MPa.

[0064] In this embodiment, as one of the achievable methods, when there is no automatic pressure reduction input signal of the turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor, the main steam header pressure target value is set according to the following method:

[0065] When the main steam header target value is automatically set by internal setting, the main steam header pressure target value is automatically set to 13.7MPa;

[0066] When the main steam header target value is automatically set by external setting, the main steam header pressure target value input by the operator will be used as the automatically set main steam header pressure target value;

[0067] When the main steam header target value is set manually, the main steam pressure target value follows the main steam pressure set value when the automatic pressure reduction input signal of the turbine bypass system lasts for 0.5s or the turbine trip pulse signal lasts for 0.5s under the emergency shutdown condition of the sodium-cooled fast reactor; when the bypass valve is in manual control mode, the main steam header pressure target value follows the main steam header pressure measurement value;

[0068] When there is no automatic pressure reduction signal for the turbine bypass system under emergency shutdown conditions of a sodium-cooled fast reactor, the rate of change from the target value of the main steam header pressure to the set value is infinite, that is, the target value of the main steam header pressure is equal to the set value.

[0069] In this embodiment, as one of the achievable ways, the method for controlling the automatic pressure reduction of the steam turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor further includes: generating a steam turbine bypass automatic pressure reduction removal signal under the emergency shutdown condition of the sodium-cooled fast reactor;

[0070] If any of the following three conditions is met, an automatic pressure reduction cut-off signal for the steam turbine bypass system under emergency shutdown conditions of a sodium-cooled fast reactor is generated:

[0071] (1) The bypass valve control mode is manual control mode;

[0072] (2) The operator inputs the automatic pressure reduction and removal command of the turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor;

[0073] (3) Under the emergency shutdown condition of the sodium-cooled fast reactor, when the automatic pressure reduction signal of the turbine bypass system exists and the main steam header pressure setting value drops to (7.9-8.1) MPa, it will open after a 3s delay and then close after a 2s delay.

[0074] In this embodiment, as one of the achievable methods, when any of the following two conditions is met, the valve position setting value of the bypass valve limiting the output is increased to prevent the pressure of the turbine bypass system from oscillating:

[0075] (1) The turbine trip signal is within 0.5s or the turbine bypass system automatic pressure reduction input signal is within 0.5s under the emergency shutdown condition of the sodium-cooled fast reactor;

[0076] (2) There is no turbine trip signal, the bypass valve position setting value is less than 0, and the measured value of the main steam header pressure is less than the set value;

[0077] (3) The turbine speed is less than 100 rpm, the bypass valve position is less than 0, and the measured value of the main steam header pressure is less than the set value.

[0078] In this embodiment, as one of the achievable ways, when there is a fault signal of all the pressure transmitters of the main steam header, the lock generates a bypass valve position control signal according to the calculated bypass valve position setting value, and uses the bypass valve position setting value input by the operator to generate the bypass valve position control signal to control the bypass valve position;

[0079] When there is a signal that all the pressure transmitters in the main steam header have failed, the bypass valve position control signal generated according to the calculated bypass valve position setting value is unlocked, and the bypass valve position control signal generated by the calculated bypass valve position setting value is used again to control the bypass valve.

[0080] In this embodiment, as one of the achievable methods, a plurality of bypass valves connected in parallel are provided in the turbine bypass system, and the plurality of bypass valves are put into regulation at the same time;

[0081] According to the total valve position setting value of the bypass valve, the valve position setting value of the bypass valve is calculated based on the equation function f(x);

[0082] f(x)=[min(nx-(n-1)×100,100); max(nx-(n-1)×100,0)];

[0083] Wherein, f(x) is the bypass valve position setting value, the minimum bypass valve position setting value is the smaller value between nx-(n-1)×100 and 100, the maximum bypass valve position setting value is the larger value between nx-(n-1)×100 and 0, x is the total bypass valve position setting value, and n is the number of bypass valves.

[0084] refer to Figure 2 As an implementation of the above method, the present invention provides an embodiment of a pressure control device for a steam turbine bypass system under an emergency shutdown condition of a sodium-cooled fast reactor. The embodiment of the device corresponds to the embodiment of the pressure control method for a steam turbine bypass system under an emergency shutdown condition of a sodium-cooled fast reactor. The device can be specifically applied to various electronic devices.

[0085] The pressure control device for the steam turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor described in this embodiment includes:

[0086] An automatic pressure reduction input signal generation module is used to generate an automatic pressure reduction input signal for the steam turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor and output it to the pressure setting value generation module;

[0087] An automatic pressure reduction cut-off signal generation module is used to generate an automatic pressure reduction cut-off signal for the steam turbine bypass under emergency shutdown conditions of a sodium-cooled fast reactor;

[0088] A pressure setting value generation module is used to generate a main steam header pressure setting value according to an automatic pressure reduction input signal of a steam turbine bypass system under an emergency shutdown condition of a sodium-cooled fast reactor, and output the value to a valve position control signal generation module;

[0089] An increase limiting module, used for limiting the increase of the bypass valve position setting value output by the pressure setting value generating module;

[0090] A valve position control signal generating module is used to calculate the total valve position setting value of the bypass valve according to the difference between the main steam header pressure measurement value and the main steam header pressure setting value; calculate the bypass valve position setting value according to the bypass valve total valve position setting value, generate a bypass valve position control signal and output it to the bypass valve;

[0091] The locking module is used to lock or unlock the valve position control signal generating module to generate the bypass valve position control signal according to the calculated bypass valve position setting value; the bypass valve position control signal is generated by the bypass valve position setting value manually input by the operator;

[0092] The bypass valve adjusts the valve position according to the output bypass valve position control signal.

[0093] As an implementation of the above method, the present invention provides an embodiment of a computer device, and the computer device embodiment corresponds to the embodiment of the above method for controlling the pressure of a turbine bypass system under emergency shutdown conditions of a sodium-cooled fast reactor.

[0094] See also Figure 3 The computer device described in this embodiment includes a memory, a processor and a network interface that are interconnected and communicated through a system bus. It should be noted that the figure only shows a computer device with a memory, a processor and a network interface, but it should be understood that it is not required to implement all the components shown, and more or fewer components can be implemented instead. Among them, those skilled in the art can understand that the computer device here is a device that can automatically perform numerical calculations and / or information processing according to pre-set or stored instructions, and its hardware includes but is not limited to microprocessors, application-specific integrated circuits, programmable gate arrays, digital processors, embedded devices, etc.

[0095] The computer device may be a computing device such as a desktop computer, a notebook, a PDA, a cloud server, etc. The computer device may interact with a user through a keyboard, a mouse, a remote controller, a touch pad, or a voice control device.

[0096] The memory includes at least one type of readable storage medium, and the readable storage medium includes flash memory, hard disk, multimedia card, card-type memory, random access memory, static random access memory, read-only memory, electrically erasable programmable read-only memory, programmable read-only memory, magnetic memory, disk, optical disk, etc. In some embodiments, the memory may be an internal storage unit of the computer device, such as a hard disk or memory of the computer device. In other embodiments, the memory may also be an external storage device of the computer device, such as a plug-in hard disk, smart memory card, secure digital card, flash memory card, etc. equipped on the computer device. Of course, the memory may also include both the internal storage unit of the computer device and its external storage device. In this embodiment, the memory is generally used to store the operating system and various application software installed on the computer device, such as the computer-readable instructions of the pressure control method of the turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor. In addition, the memory may also be used to temporarily store various types of data that have been output or are to be output.

[0097] In some embodiments, the processor may be a central processing unit, a controller, a microcontroller, a microprocessor, or other data processing chip. The processor is generally used to control the overall operation of the computer device. In this embodiment, the processor is used to run the computer-readable instructions stored in the memory or process data, such as running the computer-readable instructions of the steam turbine bypass system pressure control method under the emergency shutdown condition of the sodium-cooled fast reactor.

[0098] The network interface may include a wireless network interface or a wired network interface, which is generally used to establish a communication connection between the computer device and other electronic devices.

[0099] The pressure control method, device, computer equipment and storage device of the sodium-cooled fast reactor turbine bypass system of the present embodiment automatically sets the set value and target value of the main steam header pressure after the sodium-cooled fast reactor is shut down in an emergency, and limits the rate of change of the pressure set value of the main steam header to the target value, so that the set value of the main steam header pressure slowly and automatically approaches the target value. When the set value of the main steam header pressure reaches the target value, the main steam header pressure reduction operation is completed, and the main steam header is automatically reduced. The uncertainty disturbance introduced by the operator's manual pressure reduction operation of the main steam header is avoided, and the operator's burden in the main steam header pressure reduction process after the sodium-cooled fast reactor is shut down in an emergency is reduced, and the superheat of the steam at the outlet of the steam generator is increased, and the single-loop / dual-loop removal of the secondary circuit due to the low superheat of the steam at the outlet of the steam generator is avoided, thereby avoiding the expansion of the accident, and preparing for the water-steam conversion operation of the steam generator.

[0100] The above-mentioned embodiments only express several implementation methods of the present invention, and the description thereof is relatively specific and detailed, but it cannot be understood as limiting the scope of the patent of the present invention. It should be pointed out that, for ordinary technicians in this field, several variations and improvements can be made without departing from the concept of the present invention, which all belong to the protection scope of the present invention. Therefore, the protection scope of the patent of the present invention shall be subject to the attached claims.

Claims

1. A method for controlling the pressure of a steam turbine bypass system under emergency shutdown conditions of a sodium-cooled fast reactor, characterized in that: The steps include: Generate automatic pressure reduction input signal for steam turbine bypass system under emergency shutdown condition of sodium-cooled fast reactor; According to the automatic pressure reduction input signal of the turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor, the main steam header pressure setting value is generated and output; Calculate the bypass valve total valve position setting value according to the difference between the main steam header pressure measurement value and the output main steam header pressure setting value; calculate the bypass valve position setting value according to the bypass valve total valve position setting value, generate the bypass valve position control signal and output it to the bypass valve; The bypass valve adjusts the valve position according to the output bypass valve position control signal.

2. The method for controlling the pressure of a steam turbine bypass system under emergency shutdown conditions of a sodium-cooled fast reactor according to claim 1, characterized in that: If any of the following two conditions is met, the automatic pressure reduction signal for the steam turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor is generated: (1) The main steam header pressure setting value is higher than 8MPa, and there is an emergency shutdown signal for the sodium-cooled fast reactor; (2) The main steam header pressure setting value is higher than 8 MPa, and the operator inputs the automatic pressure reduction command for the turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor.

3. The method for controlling the pressure of a steam turbine bypass system under emergency shutdown conditions of a sodium-cooled fast reactor according to claim 1, characterized in that: According to the automatic pressure reduction input signal of the turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor, the main steam header pressure setting value is generated, including the following steps: When the automatic pressure reduction signal of the turbine bypass system exists for 0.5s under the emergency shutdown condition of the sodium-cooled fast reactor, the main steam header pressure target value is automatically set to 8MPa; When the automatic pressure reduction input signal of the turbine bypass system exists under the emergency shutdown condition of the sodium-cooled fast reactor, the change rate of the main steam header pressure set value to the main steam header pressure target value is automatically set to 0.00833MPa / s.

4. The method for controlling the pressure of a steam turbine bypass system under emergency shutdown conditions of a sodium-cooled fast reactor according to claim 3, characterized in that: When the turbine trip signal is within 0.5s or the turbine bypass system automatic pressure reduction input signal is within 0.5s under the sodium-cooled fast reactor emergency shutdown condition, the output main steam header pressure setting value is directly the smaller of the main steam header pressure setting value and 13MPa.

5. The method for controlling the pressure of a steam turbine bypass system under emergency shutdown conditions of a sodium-cooled fast reactor according to claim 1, characterized in that: The method for automatically reducing the pressure of a steam turbine bypass system under an emergency shutdown condition of a sodium-cooled fast reactor also includes: generating an automatic pressure reduction cut-off signal for the steam turbine bypass under an emergency shutdown condition of a sodium-cooled fast reactor; If any of the following three conditions is met, an automatic pressure reduction cut-off signal for the steam turbine bypass system under emergency shutdown conditions of a sodium-cooled fast reactor is generated: (1) The bypass valve control mode is manual control mode; (2) The operator inputs the automatic pressure reduction and removal command of the turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor; (3) Under the emergency shutdown condition of the sodium-cooled fast reactor, when the automatic pressure reduction signal of the turbine bypass system exists and the main steam header pressure setting value drops to (7.9-8.1) MPa, it will open after a 3s delay and then close after a 2s delay.

6. The method for controlling the pressure of a steam turbine bypass system under emergency shutdown conditions of a sodium-cooled fast reactor according to claim 1, characterized in that: When any of the following two conditions are met, the bypass valve position setting value that limits the output increases to prevent the turbine bypass system pressure from oscillating: (1) The turbine trip signal is within 0.5s or the turbine bypass system automatic pressure reduction input signal is within 0.5s under the emergency shutdown condition of the sodium-cooled fast reactor; (2) There is no turbine trip signal, the bypass valve position setting value is less than 0, and the measured value of the main steam header pressure is less than the set value; (3) The turbine speed is less than 100 rpm, the bypass valve position is less than 0, and the measured value of the main steam header pressure is less than the set value.

7. The method for controlling the pressure of a steam turbine bypass system under emergency shutdown conditions of a sodium-cooled fast reactor according to claim 1, characterized in that: When there are fault signals of all the pressure transmitters of the main steam header, the lock generates a bypass valve position control signal according to the calculated bypass valve position setting value, and uses the bypass valve position setting value input by the operator to generate a bypass valve position control signal to control the bypass valve position; When there is a signal that all the pressure transmitters in the main steam header have failed, the bypass valve position control signal generated according to the calculated bypass valve position setting value is unlocked, and the bypass valve position control signal generated by the calculated bypass valve position setting value is used again to control the bypass valve.

8. The method for controlling the pressure of a steam turbine bypass system under emergency shutdown conditions of a sodium-cooled fast reactor according to claim 1, characterized in that: The turbine bypass system is equipped with multiple bypass valves connected in parallel, and multiple bypass valves are put into regulation at the same time; According to the total valve position setting value of the bypass valve, the valve position setting value of the bypass valve is calculated based on the equation function f(x); f(x)=[min(nx-(n-1)×100,100); max(nx-(n-1)×100,0)]; Wherein, f(x) is the bypass valve position setting value, the minimum bypass valve position setting value is the smaller value between nx-(n-1)×100 and 100, the maximum bypass valve position setting value is the larger value between nx-(n-1)×100 and 0, x is the total bypass valve position setting value, and n is the number of bypass valves.

9. A pressure control device for a steam turbine bypass system under emergency shutdown conditions of a sodium-cooled fast reactor, characterized in that: include: An automatic pressure reduction input signal generation module is used to generate an automatic pressure reduction input signal for the steam turbine bypass system under the emergency shutdown condition of the sodium-cooled fast reactor and output it to the pressure setting value generation module; An automatic pressure reduction cut-off signal generation module is used to generate an automatic pressure reduction cut-off signal for the steam turbine bypass under emergency shutdown conditions of a sodium-cooled fast reactor; A pressure setting value generation module is used to generate a main steam header pressure setting value according to an automatic pressure reduction input signal of a steam turbine bypass system under an emergency shutdown condition of a sodium-cooled fast reactor, and output the value to a valve position control signal generation module; An increase limiting module, used for limiting the increase of the bypass valve position setting value output by the pressure setting value generating module; A valve position control signal generating module is used to calculate the total valve position setting value of the bypass valve according to the difference between the main steam header pressure measurement value and the main steam header pressure setting value; calculate the bypass valve position setting value according to the bypass valve total valve position setting value, generate a bypass valve position control signal and output it to the bypass valve; The locking module is used to lock or unlock the valve position control signal generating module to generate the bypass valve position control signal according to the calculated bypass valve position setting value; the bypass valve position control signal is generated by the bypass valve position setting value manually input by the operator; The bypass valve adjusts the valve position according to the output bypass valve position control signal.

10. A computer device comprising a memory and a processor, wherein the memory stores computer-readable instructions, wherein: When the processor executes the computer-readable instructions, the steps of the method for controlling the pressure of a turbine bypass system under emergency shutdown conditions of a sodium-cooled fast reactor according to any one of claims 1 to 8 are implemented.

11. A computer-readable storage medium having computer-readable instructions stored thereon, characterized in that: When the computer-readable instructions are executed, the steps of the method for controlling the pressure of a turbine bypass system under emergency shutdown conditions of a sodium-cooled fast reactor as described in any one of claims 1 to 8 are implemented.

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