Nuclear power unit vibration analysis and judgment method and device, electronic equipment and medium

Abstract

The invention relates to the technical field of vibration detection, in particular to a nuclear power unit vibration analysis and judgment method and device, electronic equipment and a medium. According to the nuclear power unit vibration analysis and judgment method and device, the electronic equipment and the medium provided by the invention, related data can be analyzed and judged after the vibration monitoring parameters, the vibration signals and the flow and temperature of the main loop of the nuclear power plant are obtained, so that whether the vibration source is the vibration of a main pump or other structures of the nuclear power unit except the main pump is determined; therefore, the vibration source can be quickly determined, so that maintainers can take measures to eliminate the vibration of the main pump in time.

Description

Technical Field

[0001] The present invention relates to the field of vibration detection technology, and in particular to a method, device, electronic equipment and medium for analyzing and judging vibration of a nuclear power unit. Background Art

[0002] The main pump of a nuclear power plant is an important nuclear-grade equipment in the primary circuit system of a pressurized water reactor nuclear power unit. As the "heart" of a nuclear power plant, it is used to drive the reactor coolant to circulate in the primary circuit of the nuclear power plant, continuously transfer the heat generated in the reactor core to the secondary side feed water of the steam generator, and ensure that an appropriate flow of coolant flows through the reactor core to cool the reactor core.

[0003] However, during operation, the nuclear power unit including the main pump will have a high vibration alarm. The vibration of the nuclear power unit will also cause the main pump to vibrate, which will seriously affect the long-term safe and stable operation of the main pump. However, the main pump vibration monitoring method in the existing technology is only to install a vibration measuring probe on the main pump body. It is impossible to systematically and comprehensively determine whether the main pump vibration is its own vibration or the main pump vibration caused by other structures, which is not conducive to taking measures to eliminate the main pump vibration.

[0004] Therefore, there is an urgent need for a nuclear power unit vibration analysis and judgment method to solve the above technical problems. Summary of the invention

[0005] The purpose of the present invention is to provide a method, device, electronic equipment and medium for analyzing and judging vibration of a nuclear power unit, which can determine whether the vibration source is a main pump or other structures of the nuclear power unit.

[0006] To achieve this object, the present invention adopts the following technical solutions:

[0007] In a first aspect, a method for analyzing and judging vibration of a nuclear power unit is provided, comprising the following steps:

[0008] S101, obtaining vibration monitoring parameters. If the vibration monitoring parameters are not within the preset parameter range, step S102 is executed, wherein the vibration monitoring parameters include the flow at the cold pipe section and hot pipe section bend of the main circuit of the nuclear power plant, the main pump, the steam generator, and the reactor pressure vessel, the temperature of the cold pipe section and hot pipe section of the main circuit of the nuclear power plant, the deformation displacement of the passive residual heat removal heat exchanger pipeline, the steam generator and the main pump support, the pressure of the cold pipe section of the main circuit of the nuclear power plant, the hot pipe section of the main circuit of the nuclear power plant and the lower chamber of the steam generator, the displacement of the cold pipe section of the main circuit of the nuclear power plant, the hot pipe section of the main circuit of the nuclear power plant, the pipe connected to the main pump and the position of the support bracket;

[0009] S102, obtaining a vibration signal and determining whether the vibration is vibration of the main pump itself according to the vibration signal;

[0010] S103, obtaining the flow rate and temperature of the main circuit of the nuclear power plant, and inputting the flow rate and temperature of the main circuit of the nuclear power plant into the three-dimensional model of the reactor for simulation calculation, and judging whether the current main circuit of the nuclear power plant will cause main pump vibration through simulation calculation;

[0011] S104. Determine, based on the comparison result, whether the vibration source is the main pump or an external vibration source, and then control the main pump to be shut down for maintenance or control the external vibration source to be shut down for maintenance.

[0012] As a preferred technical solution for the vibration analysis and judgment method of the above-mentioned nuclear power unit, if the vibration monitoring parameters are within the preset parameter range, the vibration source is the main pump.

[0013] As an optimal technical solution for the vibration analysis and judgment method of the above-mentioned nuclear power unit, if the vibration monitoring parameters are not within the preset parameter range, the main pump support structure is checked, and the main pump support structure includes a fastening nut, a lock nut, a cotter pin, a stop washer, a pin connection support and a damper.

[0014] As a preferred technical solution of the vibration analysis and judgment method of the nuclear power unit, judging whether the vibration is the vibration of the main pump itself according to the vibration signal includes:

[0015] Conducting spectrum analysis on vibration monitoring parameters that are not within the preset parameter range to identify the main contribution frequency of the vibration and then determine the cause of the vibration, wherein the main contribution frequency is the frequency with the largest amplitude among the obtained vibration frequencies; and / or,

[0016] Use vibration time-frequency diagram and waterfall diagram to check the change of vibration amplitude and vibration frequency over time to determine the relationship between vibration and speed;

[0017] Obtain the main pump electrical quantity parameters and hydraulic component parameters, and detect the main pump electrical quantity parameters and hydraulic component parameters. The hydraulic component parameters at least include the main pump thrust bearing water temperature and the flywheel chamber water temperature. The electrical quantity parameters at least include the main pump current and power parameters. Check whether the obtained electrical quantity parameters and hydraulic component parameters are beyond the specified range.

[0018] As an optimal technical solution for the above-mentioned nuclear power unit vibration analysis and judgment method, the vibration signal is obtained by acceleration sensors arranged in the cold pipe section of the main circuit of the nuclear power plant, the hot pipe section of the main circuit of the nuclear power plant, the lower chamber of the steam generator, the main pump and the reactor pressure vessel.

[0019] As a preferred technical solution of the vibration analysis and judgment method of the nuclear power unit, the pressure pulsation time history data of the pump outlet monitoring point is taken for FFT spectrum analysis to lock the vibration source from the spectrum; or,

[0020] The vibration frequency of the main circuit without the support of the upper damper of the steam generator is obtained based on the knocking test to obtain the current natural frequency, and the relationship between the vibration frequency and the current natural frequency is obtained to determine the vibration source.

[0021] As a preferred technical solution of the above-mentioned nuclear power unit vibration analysis and judgment method, obtaining the relationship between the vibration frequency and the current natural frequency to determine the vibration source includes:

[0022] If the absolute value of the difference between the current vibration frequency and the natural frequency is within the preset range, it is related to the current speed of the main pump;

[0023] If the absolute value of the difference between the current vibration frequency and the natural frequency is not within the preset range, it is irrelevant to the current rotation speed of the main pump.

[0024] In a second aspect, a nuclear power unit vibration analysis and judgment device is provided, which is used to execute the method described in any of the above schemes, including:

[0025] The first acquisition comparison module is used to obtain vibration monitoring parameters and compare whether the vibration monitoring parameters are within a preset parameter range, wherein the vibration monitoring parameters include the flow at the bends of the cold pipe section and the hot pipe section of the main circuit of the nuclear power plant, the main pump, the steam generator, and the reactor pressure vessel, the temperature of the cold pipe section and the hot pipe section of the main circuit of the nuclear power plant, the deformation displacement of the passive residual heat removal heat exchanger pipeline, the steam generator and the main pump support, the pressure of the cold pipe section of the main circuit of the nuclear power plant, the hot pipe section of the main circuit of the nuclear power plant and the lower chamber of the steam generator, the displacement of the cold pipe section of the main circuit of the nuclear power plant, the hot pipe section of the main circuit of the nuclear power plant, the pipe connected to the main pump and the support and hanger position;

[0026] The second acquisition and comparison module is used to obtain the vibration signal and determine whether the vibration is the vibration of the main pump itself according to the vibration signal;

[0027] The third acquisition comparison module is used to obtain the flow rate and temperature of the main circuit of the nuclear power plant, and input the flow rate and temperature of the main circuit of the nuclear power plant into the reactor three-dimensional model for simulation calculation, and judge whether the current main circuit of the nuclear power plant will cause the main pump vibration through simulation calculation;

[0028] The execution module is used to determine whether the vibration source is the main pump or the external vibration source according to the comparison result, and then control the main pump to be shut down for maintenance or control the external vibration source to be shut down for maintenance.

[0029] According to a third aspect, an electronic device is provided, including:

[0030] at least one processor; and a memory in communication with at least one of the processors; wherein,

[0031] The memory stores instructions that can be executed by at least one of the processors, and the instructions are executed by at least one of the processors to enable the at least one processor to execute the method described in any of the above solutions.

[0032] According to a fourth aspect, a computer-readable storage medium is provided, wherein the computer instructions are used to cause the computer to execute the method according to any of the above-mentioned schemes.

[0033] The present invention has at least the following beneficial effects:

[0034] The nuclear power unit vibration analysis and judgment method, device, electronic equipment and medium provided by the present invention can analyze and judge the relevant data after obtaining vibration monitoring parameters, vibration signals and the flow and temperature of the main circuit of the nuclear power plant, and then determine whether the vibration source is the main pump or the vibration of other structures of the nuclear power unit except the main pump, and then quickly determine the vibration source so that maintenance personnel can take measures to eliminate the vibration of the main pump in time. BRIEF DESCRIPTION OF THE DRAWINGS

[0035] In order to more clearly illustrate the technical solutions in the embodiments of the present invention, the following briefly introduces the drawings required for use in the description of the embodiments of the present invention. Obviously, the drawings described below are only some embodiments of the present invention. For ordinary technicians in this field, other drawings can be obtained based on the contents of the embodiments of the present invention and these drawings without paying any creative work.

[0036] Figure 1 A block diagram of a nuclear power unit provided by an embodiment of the present invention;

[0037] Figure 2 A flow chart of a method for analyzing and determining vibration of a nuclear power unit provided by an embodiment of the present invention;

[0038] Figure 3 A block diagram of a nuclear power unit vibration analysis and judgment device provided by an embodiment of the present invention;

[0039] Figure 4 A block diagram of an electronic device provided in accordance with an embodiment of the present invention.

[0040] In the figure:

[0041] 200, device; 201, memory; 202, processor;

[0042] 301, first acquisition and comparison module; 302, second acquisition and comparison module; 303, third acquisition and comparison module; 304, execution module. DETAILED DESCRIPTION

[0043] The present invention will be further described in detail below in conjunction with the accompanying drawings and embodiments. It is to be understood that the specific embodiments described herein are only used to explain the present invention, rather than to limit the present invention. It should also be noted that, for ease of description, only parts related to the present invention, rather than all structures, are shown in the accompanying drawings.

[0044] In the description of the present invention, unless otherwise clearly specified and limited, the terms "connected", "connected", and "fixed" should be understood in a broad sense, for example, it can be a fixed connection, a detachable connection, or an integral connection; it can be a mechanical connection or an electrical connection; it can be a direct connection or an indirect connection through an intermediate medium, it can be the internal connection of two elements or the interaction relationship between two elements. For ordinary technicians in this field, the specific meanings of the above terms in the present invention can be understood according to specific circumstances.

[0045] In the present invention, unless otherwise clearly specified and limited, a first feature being "above" or "below" a second feature may include that the first and second features are in direct contact, or may include that the first and second features are not in direct contact but are in contact through another feature between them. Moreover, a first feature being "above", "above" and "above" a second feature includes that the first feature is directly above and obliquely above the second feature, or simply indicates that the first feature is higher in level than the second feature. A first feature being "below", "below" and "below" a second feature includes that the first feature is directly below and obliquely below the second feature, or simply indicates that the first feature is lower in level than the second feature.

[0046] In the description of this embodiment, the terms "upper", "lower", "right", etc., directions or positional relationships are based on the directions or positional relationships shown in the drawings, and are only for the convenience of description and simplification of operation, rather than indicating or implying that the device or element referred to must have a specific direction, be constructed and operated in a specific direction, and therefore cannot be understood as limiting the present invention. In addition, the terms "first" and "second" are only used to distinguish in the description and have no special meaning.

[0047] The present invention provides a vibration analysis and judgment method for a nuclear power unit, which can judge whether the vibration source is a main pump or other structures of the nuclear power unit, so as to find the vibration source more quickly and improve the maintenance efficiency.

[0048] like Figure 1As shown, the main circuit of the nuclear power plant at least includes a reactor pressure vessel 1, a steam generator 2 and a main pump 3, and the main pump 3 is hooked at the bottom of the steam generator 2, wherein the reactor pressure vessel 1 is connected to the steam generator 2 through a hot pipe section 5, and the reactor pressure vessel 1 is connected to the main pump 3 through a cold pipe section 4. A displacement sensor and an acceleration sensor are arranged on the main pump 3, a displacement sensor, a temperature sensor, an acceleration sensor and a pressure pulsation sensor are arranged on the hot pipe section 5, and a displacement sensor, a temperature sensor, an acceleration sensor and a pressure pulsation sensor are arranged on the cold pipe section 4. A differential pressure transmitter is arranged at least at the interface of the cold pipe section 4, the interface of the hot pipe section 5, the interface of the steam generator 2, the interface of the main pump 3, and the interface of the reactor pressure vessel 1, and the differential pressure transmitter calculates the flow rate after detecting the pressure difference at the interface.

[0049] like Figure 2 As shown, the nuclear power unit vibration analysis and judgment method provided by the present invention comprises the following steps:

[0050] S101, obtaining vibration monitoring parameters. If the vibration monitoring parameters are not within the preset parameter range, step S102 is executed. The vibration monitoring parameters include the flow at the bends of the cold pipe section and the hot pipe section 5 of the main circuit of the nuclear power plant, the main pump 3, the steam generator 2, and the reactor pressure vessel 1, the temperature of the cold pipe section 4 and the hot pipe section 5 of the main circuit of the nuclear power plant, the deformation displacement of the passive residual heat removal heat exchanger pipeline, the steam generator 2 and the support of the main pump 3, the pressure of the cold pipe section 4 of the main circuit of the nuclear power plant, the hot pipe section 5 of the main circuit of the nuclear power plant and the lower chamber of the steam generator 2, and the displacement of the cold pipe section 4 of the main circuit of the nuclear power plant, the hot pipe section 5 of the main circuit of the nuclear power plant, and the pipe connected to the main pump 3 and the position of the support bracket;

[0051] S102, obtaining a vibration signal and determining whether the vibration is the vibration of the main pump 3 itself according to the vibration signal;

[0052] S103, obtaining the flow rate and temperature of the main circuit of the nuclear power plant, and inputting the flow rate and temperature of the main circuit of the nuclear power plant into the three-dimensional model of the reactor for simulation calculation, and judging whether the current main circuit of the nuclear power plant will cause the vibration of the main pump 3 through the simulation calculation;

[0053] After the vibration source is preliminarily determined in steps S101 and S102, simulation is used to determine whether the preliminary determination is correct, thereby achieving the purpose of verifying whether the vibration source is accurately determined. In addition, simulation technology can be used to determine whether the vibration of the primary circuit flow field causes the main pump to vibrate, and then the primary circuit can be repaired.

[0054] S104. Determine, based on the comparison result, whether the vibration source is the main pump 3 or an external vibration source, and then shut down the main pump 3 for maintenance or shut down the external vibration source for maintenance.

[0055] The nuclear power unit vibration analysis and judgment method provided by the present invention can analyze and judge the relevant data after obtaining the vibration monitoring parameters, vibration signals and the flow and temperature of the main circuit of the nuclear power plant, and then determine whether the vibration source is the main pump 3 or the vibration of other structures of the nuclear power unit except the main pump 3, and then quickly determine the vibration source so that maintenance personnel can take measures to eliminate the main pump vibration in time.

[0056] In some embodiments, if the vibration monitoring parameter is within the preset parameter range, the vibration source is the main pump 3. At this time, the main pump 3 is the maintenance object, so the vibration source can be quickly determined so that the maintenance personnel can take measures to solve the vibration problem of the main pump 3.

[0057] When the vibration monitoring parameters are not within the preset parameter range, the main pump support structure is inspected, and the main pump support structure includes a fastening nut, a lock nut, a cotter pin, a stop washer, a pin joint support and a damper. The specific composition of the main pump support structure is the prior art and will not be described in detail here. The inspection of the main pump support structure mainly includes: recording the torque value of the fastening nut; checking whether the lock nut is loose / loose and whether it fits tightly with the fastening nut; checking whether the cotter pin and the stop washer are installed intact; checking whether there is obvious torsion or jamming at the pin connection; recording the stroke of the damper, and obtaining the torque value, the looseness of the lock nut, the lock nut and the fastening nut. By inspecting the main pump support structure to determine whether the vibration of the main pump 3 is caused by the main pump support structure, the vibration source of the main pump can be quickly determined and the maintenance work can be completed.

[0058] For example, vibration monitoring parameters can be obtained through the data acquisition device. After the above vibration monitoring parameters are collected, the collected pressure signals are transmitted to the main pump vibration monitoring and analysis system for real-time collection and recording. The data acquisition device consists of a terminal junction box and a NI multi-channel high-speed and high-precision data acquisition device, a UPS power supply, and a data transmission display system (the EDS power supply is connected to the UPS to provide an uninterruptible power supply for the data acquisition system. When the data acquisition system loses power, the UPS can provide 2 hours of power for the DAQ). It has the functions of real-time data display of the measurement channel, trend display and recording, alarm display and output, historical data storage and retrieval, and remote data reading and parameter configuration via Ethernet and networking with the host computer. It is configured as a 100Mbps fast Ethernet, and the real-time information of the data acquisition recorder is collected and recorded simultaneously through the time synchronization system.

[0059] In some embodiments, judging whether the vibration is the vibration of the main pump 3 itself according to the vibration signal includes:

[0060] Conduct spectrum analysis on vibration monitoring parameters that are not within the preset parameter range to lock the main contribution frequency of vibration, and then determine the cause of vibration, wherein the main contribution frequency is the frequency with the largest amplitude among the obtained vibration frequencies; and / or, use vibration time-frequency diagram and waterfall diagram to check the change of vibration amplitude and vibration frequency over time, which is used to determine the relationship between vibration and rotation speed; if the analysis shows that the vibration frequency is an integer multiple of the rotation frequency of the main pump 3, it means that the vibration source may be the main pump 3. Further combine the main pump electrical quantity parameters and hydraulic component parameters obtained, and detect the main pump electrical quantity parameters and hydraulic component parameters, the hydraulic component parameters at least include the main pump thrust bearing water temperature and the flywheel cavity water temperature, and the electrical quantity parameters at least include the main pump current and power parameters, and check whether the obtained electrical quantity parameters and hydraulic component parameters exceed the limited range. Any of the above three determination methods can lock the cause of vibration to determine the cause of the vibration of the main pump or the cause of the vibration of the nuclear power unit other than the main pump 3. Each signal is obtained by using the main pump 3 and various sensors arranged on the primary circuit (pressure pulsation sensor, wire-type displacement sensor, acceleration sensor, temperature sensor, differential pressure transmitter, strain gauge).

[0061] Different vibration frequencies correspond to different components of the main pump 3 that generate vibrations, so the components of the main pump 3 can be locked according to the obtained vibration frequency. That is, the purpose of conducting spectrum analysis on the signal of excessive vibration is to determine whether it is caused by the outside world or by itself, and the specific location causing the vibration can also be determined according to the judgment result.

[0062] It should be noted that when any of the electrical quantity parameters and hydraulic component parameters detected are out of range, the main pump 3 is shut down and repaired. In this way, the cause of the vibration of the main pump 3 can be accurately obtained based on the specific electrical quantity parameters and hydraulic component parameters of the main pump, so as to quickly lock the faulty component for maintenance.

[0063] In some embodiments, the vibration signal is obtained by the acceleration sensors arranged in the cold pipe section of the main circuit of the nuclear power plant, the hot pipe section 5 of the main circuit of the nuclear power plant, the lower chamber of the steam generator, the main pump 3 and the reactor pressure vessel 1. As the number of acceleration sensors increases, vibration signals at different points can be collected, and the vibration source can be quickly locked by analyzing the signals at different points to save detection time.

[0064] In some embodiments, the pressure pulsation time history data at the pump outlet monitoring point is taken for FFT spectrum analysis to locate the vibration source from the spectrum; or,

[0065] The vibration frequency of the main circuit without the support of the upper damper of the steam generator 2 is obtained based on the knocking test to obtain the current natural frequency, and the relationship between the vibration frequency and the current natural frequency is obtained to determine the vibration source.

[0066] In some embodiments, obtaining a relationship between the vibration frequency and the current natural frequency to determine the vibration source includes:

[0067] If the absolute value of the difference between the current vibration frequency and the natural frequency is within the preset range, it means that the current vibration is caused by system resonance, which may be related to the current speed of the main pump 3; if the absolute value of the difference between the current vibration frequency and the natural frequency is not within the preset range, it means that the current vibration is not caused by system vibration and has nothing to do with the current speed of the main pump 3.

[0068] The embodiment of the present invention also provides a nuclear power unit vibration analysis and judgment device, which is used to execute the method provided by the present invention, such as Figure 3 As shown, the device includes a first acquisition and comparison module 301, a second acquisition and comparison module 302, a third acquisition and comparison module 303 and an execution module 304, wherein the first acquisition and comparison module 301 is used to obtain vibration monitoring parameters and compare whether the vibration monitoring parameters are within a preset parameter range, and the vibration monitoring parameters include the flow of the cold pipe section 4 and the hot pipe section bend of the main circuit of the nuclear power plant, the main pump 3, the steam generator 2, and the reactor pressure vessel 1, the temperature of the cold pipe section 4 and the hot pipe section 5 of the main circuit of the nuclear power plant, the deformation displacement of the passive residual heat removal heat exchanger pipeline, the steam generator 2 and the main pump 3 support, the cold pipe section 4 of the main circuit of the nuclear power plant, the hot pipe section 5 of the main circuit of the nuclear power plant and the steam generator under The pressure in the chamber, the cold pipe section 4 of the main circuit of the nuclear power plant, the hot pipe section 5 of the main circuit of the nuclear power plant, the displacement of the pipeline connected to the main pump and the support bracket position; the second acquisition comparison module 302 is used to obtain the vibration signal and determine whether the vibration is the vibration of the main pump 3 itself according to the vibration signal; the third acquisition comparison module 303 is used to obtain the flow and temperature of the main circuit of the nuclear power plant, and input the flow and temperature of the main circuit of the nuclear power plant into the reactor three-dimensional model for simulation calculation, and determine whether the current main circuit of the nuclear power plant will cause the main pump 3 to vibrate through simulation calculation. The execution module 304 is used to determine whether the vibration source is the main pump 3 or an external vibration source according to the comparison result, and then control the main pump 3 to be shut down for maintenance or control the external vibration source to be shut down for maintenance.

[0069] The nuclear power unit vibration analysis and judgment device provided by the present invention can analyze and judge the relevant data after obtaining the vibration monitoring parameters, vibration signals and the flow and temperature of the main circuit of the nuclear power plant, and then determine whether the vibration source is the main pump 3 or the vibration of other structures of the nuclear power unit except the main pump 3, and then quickly determine the vibration source so that maintenance personnel can take measures to eliminate the vibration of the main pump in time.

[0070] To achieve the above embodiments, the present application also provides an electronic device and a computer-readable storage medium.

[0071] Figure 4A schematic block diagram of an example electronic device that can be used to implement an embodiment of the present application is shown. The electronic device is intended to represent various forms of digital computers, such as laptop computers, desktop computers, workbenches, personal digital assistants, servers, blade servers, mainframe computers, and other suitable computers. The electronic device can also represent various forms of mobile devices, such as personal digital processing, cellular phones, smart phones, wearable devices, and other similar computing devices. The components shown herein, their connections and relationships, and their functions are merely examples and are not intended to limit the implementation of the present application described and / or required herein.

[0072] like Figure 4 As shown, the device 200 includes a memory 201, a processor 202, and a computer program stored in the memory 201 and executable on the processor 202. When the processor 202 executes the program instructions, the vibration analysis and judgment method for a nuclear power unit provided in the above embodiment is implemented.

[0073] An embodiment of the present application provides a computer-readable storage medium on which a computer program is stored. When the program is executed by the processor 202, the vibration analysis and judgment method of the nuclear power unit provided in the above embodiment is implemented.

[0074] Various implementations of the systems and techniques described above herein can be implemented in digital electronic circuit systems, integrated circuit systems, field programmable gate arrays (FPGAs), application specific integrated circuits (ASICs), application specific standard products (ASSPs), systems on chips (SOCs), load programmable logic devices (CPLDs), computer hardware, firmware, software, and / or combinations thereof. These various implementations can include: being implemented in one or more computer programs that can be executed and / or interpreted on a programmable system including at least one programmable processor, which can be a special purpose or general purpose programmable processor that can receive data and instructions from a storage system, at least one input device, and at least one output device, and transmit data and instructions to the storage system, the at least one input device, and the at least one output device.

[0075] The program code for implementing the method itself can be written in any combination of one or more programming languages. These program codes can be provided to a processor or controller of a general-purpose computer, a special-purpose computer or other programmable data processing device, so that the program code, when executed by the processor or controller, enables the functions / operations specified in the flow chart and / or block diagram to be implemented. The program code can be executed entirely on the machine, partially on the machine, partially on the machine as a stand-alone software package and partially on a remote machine, or entirely on a remote machine or server.

[0076] In the context of the present application, a machine-readable medium may be a tangible medium that may contain or store a program for use by or in conjunction with an instruction execution system, device, or equipment. A machine-readable medium may be a machine-readable signal medium or a machine-readable storage medium. A machine-readable medium may include, but is not limited to, an electronic, magnetic, optical, electromagnetic, infrared, or semiconductor system, device, or equipment, or any suitable combination of the foregoing. A more specific example of a machine-readable storage medium may include an electrical connection based on one or more lines, a portable computer disk, a hard disk, a random access memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM or flash memory), an optical fiber, a portable compact disk read-only memory (CD-ROM), an optical storage device, a magnetic storage device, or any suitable combination of the foregoing.

[0077] To provide interaction with a user, the systems and techniques described herein can be implemented on a computer having: a display device (e.g., a CRT (cathode ray tube) or LCD (liquid crystal display) monitor) for displaying information to the user; and a keyboard and pointing device (e.g., a mouse or trackball) through which the user can provide input to the computer. Other types of devices can also be used to provide interaction with the user; for example, the feedback provided to the user can be any form of sensory feedback (e.g., visual feedback, auditory feedback, or tactile feedback); and input from the user can be received in any form (including acoustic input, voice input, or tactile input).

[0078] The systems and techniques described herein can be implemented in a computing system that includes backend components (e.g., as a data server), or a computing system that includes middleware components (e.g., an application server), or a computing system that includes frontend components (e.g., a user computer with a graphical user interface or a grid browser through which a user can interact with implementations of the systems and techniques described herein), or a computing system that includes any combination of such backend components, middleware components, or frontend components. The components of the system can be interconnected by any form or medium of digital data communication (e.g., a communication grid). Examples of communication grids include: a local area network (LAN), a wide area network (WAN), the Internet, and a blockchain grid.

[0079] A computer system may include a client and a server. The client and the server are generally remote from each other and usually interact through a communication grid. The relationship between the client and the server is generated by computer programs running on the corresponding computers and having a client-server relationship with each other. The server may be a cloud server, also known as a cloud computing server or a cloud host, which is a host product in the cloud computing service system to solve the defects of difficult management and weak business scalability in traditional physical hosts and VPS services ("Virtual Private Server", or "VPS" for short). The server may also be a server for a distributed system, or a server combined with a blockchain.

[0080] In addition, the above are only preferred embodiments of the present invention and the technical principles used. Those skilled in the art will understand that the present invention is not limited to the specific embodiments described herein, and that various obvious changes, readjustments and substitutions can be made by those skilled in the art without departing from the scope of protection of the present invention. Therefore, although the present invention has been described in more detail through the above embodiments, the present invention is not limited to the above embodiments, and may include more other equivalent embodiments without departing from the concept of the present invention, and the scope of the present invention is determined by the scope of the appended claims.

Claims

1. A method for analyzing and judging vibration of a nuclear power unit, characterized in that: The steps include: S101, obtaining vibration monitoring parameters. If the vibration monitoring parameters are not within the preset parameter range, step S102 is executed, wherein the vibration monitoring parameters include the flow at the cold pipe section and hot pipe section bend of the main circuit of the nuclear power plant, the main pump, the steam generator, and the reactor pressure vessel, the temperature of the cold pipe section and hot pipe section of the main circuit of the nuclear power plant, the deformation displacement of the passive residual heat removal heat exchanger pipeline, the steam generator and the main pump support, the pressure of the cold pipe section of the main circuit of the nuclear power plant, the hot pipe section of the main circuit of the nuclear power plant and the lower chamber of the steam generator, the displacement of the cold pipe section of the main circuit of the nuclear power plant, the hot pipe section of the main circuit of the nuclear power plant, the pipe connected to the main pump and the position of the support bracket; S102, obtaining a vibration signal and determining whether the vibration is vibration of the main pump itself according to the vibration signal; S103, obtaining the flow rate and temperature of the main circuit of the nuclear power plant, and inputting the flow rate and temperature of the main circuit of the nuclear power plant into the three-dimensional model of the reactor for simulation calculation, and judging whether the current main circuit of the nuclear power plant will cause main pump vibration through simulation calculation; S104. Determine, based on the comparison result, whether the vibration source is the main pump or an external vibration source, and then control the main pump to be shut down for maintenance or control the external vibration source to be shut down for maintenance.

2. The nuclear power unit vibration analysis and judgment method according to claim 1, characterized in that: If the vibration monitoring parameters are within the preset parameter range, the vibration source is the main pump.

3. The nuclear power unit vibration analysis and judgment method according to claim 1, characterized in that: If the vibration monitoring parameters are not within the preset parameter range, the main pump support structure is checked, and the main pump support structure includes a fastening nut, a lock nut, a cotter pin, a retaining washer, a pin connection support and a damper.

4. The nuclear power unit vibration analysis and judgment method according to claim 1, characterized in that: Judging whether the vibration is the vibration of the main pump itself based on the vibration signal includes: Conduct spectrum analysis on vibration monitoring parameters that are not within the preset parameter range to identify the main contribution frequency of the vibration and then determine the cause of the vibration, where the main contribution frequency is the frequency with the largest amplitude among the obtained vibration frequencies; or Use vibration time-frequency graphs and waterfall graphs to check how the vibration amplitude and frequency change over time to determine the relationship between vibration and speed; or, Obtain the main pump electrical quantity parameters and hydraulic component parameters, and detect the main pump electrical quantity parameters and hydraulic component parameters. The hydraulic component parameters at least include the main pump thrust bearing water temperature and the flywheel chamber water temperature. The electrical quantity parameters at least include the main pump current and power parameters. Check whether the obtained electrical quantity parameters and hydraulic component parameters are beyond the specified range.

5. The nuclear power unit vibration analysis and judgment method according to claim 1, characterized in that: The vibration signal is obtained by acceleration sensors arranged in the cold pipe section of the main circuit of the nuclear power plant, the hot pipe section of the main circuit of the nuclear power plant, the lower chamber of the steam generator, the main pump and the reactor pressure vessel.

6. The nuclear power unit vibration analysis and judgment method according to claim 1, characterized in that: Take the pressure pulsation time history data of the pump outlet monitoring point for FFT spectrum analysis to lock the vibration source from the spectrum; or, The vibration frequency of the main circuit without the support of the upper damper of the steam generator is obtained based on the knocking test to obtain the current natural frequency, and the relationship between the vibration frequency and the current natural frequency is obtained to determine the vibration source.

7. The method for analyzing and judging vibration of a nuclear power unit according to claim 1, characterized in that: Obtain the relationship between the vibration frequency and the current natural frequency to determine the vibration source including: If the absolute value of the difference between the current vibration frequency and the natural frequency is within the preset range, it is related to the current speed of the main pump; If the absolute value of the difference between the current vibration frequency and the natural frequency is not within the preset range, it is irrelevant to the current rotation speed of the main pump.

8. A vibration analysis and judgment device for a nuclear power unit, characterized in that: Used to perform the method according to any one of claims 1 to 7, comprising: The first acquisition comparison module is used to obtain vibration monitoring parameters and compare whether the vibration monitoring parameters are within a preset parameter range, wherein the vibration monitoring parameters include the flow at the bends of the cold pipe section and the hot pipe section of the main circuit of the nuclear power plant, the main pump, the steam generator, and the reactor pressure vessel, the temperature of the cold pipe section and the hot pipe section of the main circuit of the nuclear power plant, the deformation displacement of the passive residual heat removal heat exchanger pipeline, the steam generator and the main pump support, the pressure of the cold pipe section of the main circuit of the nuclear power plant, the hot pipe section of the main circuit of the nuclear power plant and the lower chamber of the steam generator, the displacement of the cold pipe section of the main circuit of the nuclear power plant, the hot pipe section of the main circuit of the nuclear power plant, the pipe connected to the main pump and the support and hanger position; The second acquisition and comparison module is used to obtain the vibration signal and determine whether the vibration is the vibration of the main pump itself according to the vibration signal; The third acquisition comparison module is used to obtain the flow rate and temperature of the main circuit of the nuclear power plant, and input the flow rate and temperature of the main circuit of the nuclear power plant into the reactor three-dimensional model for simulation calculation, and judge whether the current main circuit of the nuclear power plant will cause the main pump vibration through simulation calculation; The execution module is used to determine whether the vibration source is the main pump or the external vibration source according to the comparison result, and then control the main pump to be shut down for maintenance or control the external vibration source to be shut down for maintenance.

9. Electronic equipment, including: at least one processor; and a memory communicatively connected to at least one of the processors; characterized in that, The memory stores instructions that can be executed by at least one of the processors, and the instructions are executed by at least one of the processors to enable the at least one processor to perform the method according to any one of claims 1 to 7.

10. A computer-readable storage medium, characterized in that The computer instructions are used to cause the computer to execute the method according to any one of claims 1-7.

Images