CN111341477A - Nuclear power plant safety power supply renovation and maintenance method and device - Google Patents

Nuclear power plant safety power supply renovation and maintenance method and device Download PDF

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Publication number
CN111341477A
CN111341477A CN202010245311.XA CN202010245311A CN111341477A CN 111341477 A CN111341477 A CN 111341477A CN 202010245311 A CN202010245311 A CN 202010245311A CN 111341477 A CN111341477 A CN 111341477A
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China
Prior art keywords
power supply
clamping piece
detected
actual
electrolytic capacitor
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Granted
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CN202010245311.XA
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Chinese (zh)
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CN111341477B (en
Inventor
刘洋
曹才
王正斌
季涛
庞巨荣
周运恒
刘海琪
李广森
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China General Nuclear Power Corp
CGN Power Co Ltd
Daya Bay Nuclear Power Operations and Management Co Ltd
Lingdong Nuclear Power Co Ltd
Guangdong Nuclear Power Joint Venture Co Ltd
Lingao Nuclear Power Co Ltd
Original Assignee
China General Nuclear Power Corp
CGN Power Co Ltd
Daya Bay Nuclear Power Operations and Management Co Ltd
Lingdong Nuclear Power Co Ltd
Guangdong Nuclear Power Joint Venture Co Ltd
Lingao Nuclear Power Co Ltd
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Application filed by China General Nuclear Power Corp, CGN Power Co Ltd, Daya Bay Nuclear Power Operations and Management Co Ltd, Lingdong Nuclear Power Co Ltd, Guangdong Nuclear Power Joint Venture Co Ltd, Lingao Nuclear Power Co Ltd filed Critical China General Nuclear Power Corp
Priority to CN202010245311.XA priority Critical patent/CN111341477B/en
Publication of CN111341477A publication Critical patent/CN111341477A/en
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/04Safety arrangements
    • G21D3/06Safety arrangements responsive to faults within the plant
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01RMEASURING ELECTRIC VARIABLES; MEASURING MAGNETIC VARIABLES
    • G01R31/00Arrangements for testing electric properties; Arrangements for locating electric faults; Arrangements for electrical testing characterised by what is being tested not provided for elsewhere
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01RMEASURING ELECTRIC VARIABLES; MEASURING MAGNETIC VARIABLES
    • G01R31/00Arrangements for testing electric properties; Arrangements for locating electric faults; Arrangements for electrical testing characterised by what is being tested not provided for elsewhere
    • G01R31/40Testing power supplies
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

Abstract

The application belongs to the technical field of nuclear power plant reactor protection systems, and relates to a nuclear power plant safety level power supply renovation maintenance method and a device, by identifying a faulty device of a power supply card to be tested, judging whether the faulty device obstructs normal operation of the power supply card to be tested, if the faulty device obstructs normal operation of the power supply card to be tested, sending a control signal for replacing the faulty device with a new component, detecting whether a replacement completion instruction is received and when the replacement completion instruction is received, whether the power supply clamping piece to be detected normally operates or not is detected, renovation and maintenance of the power supply clamping piece are achieved, the problem that the power supply clamping piece cannot normally operate due to the faults of aging of parts of components, parameter drifting and the like of the power supply clamping piece is avoided, and the problem that safe operation of a nuclear power station is damaged due to the faults of aging of the components, parameter drifting and the like of the power supply clamping piece in the nuclear power station is solved.

Description

Nuclear power plant safety power supply renovation and maintenance method and device
Technical Field
The application belongs to the technical field of reactor protection systems of nuclear power plants, and particularly relates to a nuclear power plant safety-level power supply renovation maintenance method and device.
Background
At present, when a traditional nuclear power plant reactor protection system runs for many years, part of components of a power supply clamping piece have fault trends such as aging and parameter drifting, and when the components have faults such as aging and parameter drifting, the power supply clamping piece is usually tripped, so that the safe running of a nuclear power plant is influenced.
Disclosure of Invention
The application aims to provide a nuclear power plant safety-level power supply renovation and maintenance method and device, and aims to solve the problem that a power supply clamping piece in a nuclear power plant harms safe operation of the nuclear power plant due to faults of component aging, parameter drifting and the like.
A first aspect of an embodiment of the present application provides a nuclear power plant safety-level power supply renovation maintenance method, including:
identifying a fault device of a power supply clamping piece to be detected;
judging whether the fault device obstructs normal operation of the power supply clamping piece to be detected, and if the fault device obstructs normal operation of the power supply clamping piece to be detected, sending a control signal for replacing the fault device with a new component;
detecting whether a replacement completion instruction is received or not, and detecting whether the power supply clamping piece to be detected normally operates or not when the replacement completion instruction is received;
when the power supply card to be tested normally operates, sending a renovation completion instruction;
and when the power card to be tested runs in a fault, sending a fault instruction.
A second aspect of an embodiment of the present application provides a nuclear power plant safety level power renovates maintenance device, includes:
the identification module is used for identifying a fault device of the power supply clamping piece to be detected;
the judging module is used for judging whether the fault device obstructs the normal operation of the power supply clamping piece to be detected, and if the fault device obstructs the normal operation of the power supply clamping piece to be detected, sending a control signal for replacing the fault device with a new component; and
the detection module detects whether a replacement completion instruction is received or not, detects whether the power supply clamping piece to be detected normally operates or not when the replacement completion instruction is received, sends a renovation completion instruction when the power supply clamping piece to be detected normally operates, and sends a fault instruction when the power supply clamping piece to be detected runs in a fault.
A third aspect of an embodiment of the present application provides a nuclear power plant safety-level power supply refurbishment and repair apparatus, including a memory, a processor, and a computer program stored in the memory and executable on the processor, where the processor implements the steps of the method described above when executing the computer program.
A fourth aspect of embodiments of the present application provides a computer-readable storage medium, which stores a computer program, which, when executed by a processor, implements the steps of the method as described above.
Compared with the prior art, the embodiment of the invention has the following beneficial effects: according to the nuclear power plant safety-level power supply renovating and maintaining method, the problem that the nuclear power plant safety operation is damaged by the power supply clamping piece in the nuclear power plant due to faults of aging of parts of components, parameter drifting and the like of the components is solved by identifying the fault component of the power supply clamping piece to be detected, judging whether the fault component obstructs normal operation of the power supply clamping piece to be detected, sending a control signal for replacing the fault component with a new component if the fault component obstructs normal operation of the power supply clamping piece to be detected, detecting whether a replacement completion instruction is received, and detecting whether the power supply clamping piece to be detected normally operates when the replacement completion instruction is received.
Drawings
FIG. 1 is a flowchart illustrating a method for refurbishing a nuclear power plant safety-level power supply according to an embodiment of the present disclosure;
FIG. 2 is a detailed flowchart of step S100 of the nuclear power plant safety-level power supply refurbishment maintenance method shown in FIG. 1;
FIG. 3 is a flowchart illustrating a specific step S110 of the method for refurbishing the safety-level power supply of the nuclear power plant shown in FIG. 1;
FIG. 4 is a flowchart complementary to the specific flowchart of step S110 of the nuclear power plant safety-level power source renovation maintenance method shown in FIG. 3;
FIG. 5 is a detailed flowchart complementary to step S100 of the nuclear power plant safety-level power source retrofit maintenance method shown in FIG. 1;
FIG. 6 is a flowchart illustrating a specific step S200 of the method for refurbishing the safety-level power supply of the nuclear power plant shown in FIG. 1;
FIG. 7 is a flowchart illustrating a specific step S300 of the method for refurbishing the safety-level power supply of the nuclear power plant shown in FIG. 1;
FIG. 8 is a schematic diagram of a nuclear power plant safety-level power source retrofit service device provided in an embodiment of the present application;
fig. 9 is a schematic diagram of a nuclear power plant safety-level power supply renovation maintenance device provided by an embodiment of the invention.
Detailed Description
In order to make the technical problems, technical solutions and advantageous effects to be solved by the present application clearer, the present application is further described in detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the present application and are not intended to limit the present application.
It will be understood that when an element is referred to as being "secured to" or "disposed on" another element, it can be directly on the other element or be indirectly on the other element. When an element is referred to as being "connected to" another element, it can be directly connected to the other element or be indirectly connected to the other element.
It will be understood that the terms "length," "width," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," and the like, refer to an orientation or positional relationship illustrated in the drawings for convenience in describing the present application and to simplify description, and do not indicate or imply that the referenced device or element must have a particular orientation, be constructed and operated in a particular orientation, and thus should not be construed as limiting the present application.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include one or more of that feature. In the description of the present application, "a plurality" means two or more unless specifically limited otherwise.
Fig. 1 shows a specific flowchart of a nuclear power plant safety-level power supply refurbishment and repair method provided by a first aspect of an embodiment of the present application, and for convenience of description, only the parts related to the embodiment are shown, which are detailed as follows:
a nuclear power plant safety level power supply renovation maintenance method comprises the following steps:
step S100: identifying a fault device of a power supply clamping piece to be detected;
it should be understood that the faulty device can be identified by looking up the faulty device from the log database, by theoretical calculation or actual detection, etc.
It is understood that a malfunctioning device includes devices that are aged or about to be aged, devices that have parameter drift, and the like.
Referring to fig. 2, in one embodiment, step S100 includes:
step S110: confirming the actual service life L of an electrolytic capacitor in the component through theoretical calculation;
referring to fig. 3, in an embodiment, the step S110 specifically includes:
step S111: obtaining the service life L of the electrolytic capacitor at the highest service temperature0Ultimate working temperature TmaxRipple current function f (I)rippl) And rated operating voltage UR
It will be appreciated that the lifetime L at the maximum use temperature of an electrolytic capacitor can be obtained by identifying the unique identification code of the electrolytic capacitor0Ultimate working temperature TmaxRipple current function f (I)rippl) And rated operating voltage URAnd so on.
Step S112: collecting actual working environment temperature T of electrolytic capacitora
It should be understood that the actual operating environment temperature T may be collected by a temperature sensor or the likea
Step S113: detecting the actual operating voltage U of the electrolytic capacitora
It should be understood that the actual operating voltage U of the electrolytic capacitor may be collected by a voltage sensor, a sampling resistor, a voltmeter, or the likea
Step S114: according to the service life L of the electrolytic capacitor at the maximum service temperature0Ultimate working temperature TmaxActual working environment temperature TaRipple current function f (I)rippl) Rated operating voltage URAnd the actual operating voltage UaThe actual useful life L of the electrolytic capacitor is calculated. It is understood that L ═ L0*f(T)*f(Irippl) F (U), wherein f (T) 2(Tmax-Ta)/10,f(U)=(UR/Ua)aAnd a is the difference of the empirical coefficients, and is usually 4-7.
Referring to fig. 4, in an embodiment, the step S100 further includes:
step S115: acquiring actual ripple current of the electrolytic capacitor;
it should be understood that the actual ripple current may be obtained by detecting the current waveform of the capacitor.
Step S116: comparing the actual ripple current with the rated ripple current;
it should be understood that the actual ripple current and the rated ripple current can be compared by a graph comparison, a numerical comparison, and the like.
Step S117: if the actual ripple current is less than the rated ripple current, the service life L of the electrolytic capacitor at the highest service temperature is determined0Ultimate working temperature TmaxActual working environment temperature TaRated operating voltage URAnd the actual operating voltage UaCalculating the actual usable life L of the electrolytic capacitor, namely: l ═ L0*f (t) × (u), wherein f (t) ═ 2(Tmax-Ta)/10,f(U)=(UR/Ua)aA is that different values of empirical coefficients are different, and is usually 4-7;
step S118: if the actual ripple current is greater than or equal to the rated ripple current, the service life L of the electrolytic capacitor at the highest service temperature is determined0Ultimate working temperature TmaxActual working environment temperature TaRipple current function, rated operating voltage UaAnd the actual operating voltage URCalculating the actual useful life L of the electrolytic capacitor, i.e. L ═ L0*f(T)*f(Irippl) F (U), wherein f (T) 2(Tmax-Ta)/10,f(U)=(UR/Ua)aAnd a is the difference of the empirical coefficients, and is usually 4-7.
Step S120: comparing the actual service life L with the preset service life, and taking the lowest value of the actual service life L and the preset service life as the target service life;
it should be understood that the preset lifetime may be an average of the historical lifetimes of the electrolytic capacitors.
Step S130: judging whether the electrolytic capacitor is an aged component or not according to the target service life;
it should be understood that when the actual used life of the electrolytic capacitor is not less than the target life, the electrolytic capacitor is judged to be an aged component, and when the actual used life of the electrolytic capacitor is less than the target life, the electrolytic capacitor is judged to be a non-aged component.
Step S140: and if the electrolytic capacitor is an aged component, marking the electrolytic capacitor as a fault component.
Referring to fig. 5, in an embodiment, step S100 further includes:
step S150: detecting actual operation parameters of components of the power supply clamping piece to be detected;
it should be understood that the actual operating parameters of the components may be detected by a circuit board in-line inspection tool, such as an MID fixture. The operating parameters include: voltage, current, frequency, power consumption, etc.
Step S160: judging whether the component has parameter drift or not according to the actual operation parameters and the standard operation parameters of the component;
it should be understood that the one-to-one correspondence comparison and judgment between each actual operation parameter and each standard operation parameter may be performed, when the actual operation parameter of the component is not equal to the standard operation parameter, it is judged that the component has parameter drift, and when the actual operation parameter of the component is consistent with the standard operation parameter, it is judged that the component does not have parameter drift.
Step S170: and if the component has parameter drift, marking the component as a fault component.
Step S200: judging whether the fault device obstructs normal operation of the power supply clamping piece to be tested, and if the fault device obstructs normal operation of the power supply clamping piece to be tested, sending a control signal for replacing the fault device with a new component;
optionally, the control signal is sent to the automatic welding device, and the automatic welding device replaces the faulty component with the corresponding new component after receiving the control signal.
Optionally, the control signal may also be sent to a display screen, and the worker manually replaces the faulty device with a corresponding new component according to an indication of the display screen.
Referring to fig. 9, in one embodiment, step S200 includes:
step S210: simulating the running state of the power supply clamping piece to be tested when the fault device fails through simulation;
it should be understood that through simulation modeling, the operation of the power supply clamping piece is simulated, the parameters of the fault device are adjusted to be fault parameters, and the operation state of the power supply clamping piece to be tested at the moment is detected.
Step S220: detecting whether a power supply clamping piece to be detected works or not;
whether the power supply clamping piece to be detected works can be judged by detecting whether the power supply clamping piece to be detected has output and the like.
Step S230: when the power supply clamping piece does not work, judging that the fault device obstructs the normal operation of the power supply clamping piece to be detected;
step S240: when the power supply clamping piece works, detecting the output waveform of the power supply clamping piece to be detected;
step S250: and comparing the output waveform with the standard output waveform, and judging that the fault device obstructs the normal operation of the power supply clamping piece to be detected when the output waveform is inconsistent with the standard output waveform.
Step S300: detecting whether a replacement completion instruction is received or not, and detecting whether the power supply clamping piece to be detected normally operates or not when the replacement completion instruction is received;
referring to fig. 7, in an embodiment, the detecting whether the power card to be tested normally operates includes:
step S310: detecting whether the parameters of the component after the replacement of the power supply clamping piece to be detected are standard parameters or not;
it should be understood that the parameters of the replaced component may be collected by a voltmeter, an ammeter or other special detecting instrument, and the parameters are compared with the standard parameters, when the parameters are equal to the standard parameters, the replaced component is proved to be normal, and when the parameters are not equal to the standard parameters, the replaced component is proved to be abnormal.
Step S320: judging whether the welding of each component of the circuit board is normal or not through image acquisition;
it is understood that whether the soldering is normal includes whether the soldering surface is blackened, whether it is cold soldered, whether it is continuous soldered, and the like.
Step S330: and detecting whether each working parameter of the power supply card to be detected is a target working parameter.
It should be understood that the various operating parameters of the power supply card to be tested include: power consumption at no load, output waveform at full load, power at full load, output voltage frequency, output voltage effective value, input trip voltage, input maximum overvoltage, etc.
Wherein, the power consumption when detecting the no-load of the power card spare that awaits measuring includes: under the condition that the power supply clamping piece to be tested is in no load, inputting a current to the power supply clamping piece to be tested, and testing the power consumption of the power supply clamping piece to be tested.
The output waveform when detecting full load of the power supply fastener that awaits measuring includes: detecting the output waveform of the power supply clamping piece to be detected when the clamping piece is fully loaded, and judging whether the output waveform is a smooth burr-free square wave.
Detecting the power of the power supply clamping piece to be detected when the power supply clamping piece is fully loaded comprises the following steps: and testing the power of the power supply clamping piece to be tested under the condition that the power supply clamping piece to be tested is fully loaded with the target full-load input current.
Detecting the output voltage frequency of the power supply card to be detected comprises: and detecting the output voltage frequency of the power supply clamping piece to be detected, and judging whether the output voltage frequency is matched with the transformer.
The effective value of the output voltage of the power supply clamping piece to be detected comprises the following steps: collecting the output voltage of the power supply clamping piece to be tested, converting the output voltage effective value according to the output voltage, and judging whether the output voltage effective value is a target value.
Detecting the input trip voltage of the power supply card to be tested includes: detecting whether the input tripping voltage of the power supply clamping piece to be detected is smaller than the tripping voltage of the power supply bus;
detecting the input maximum overvoltage of the power supply clamping piece to be detected comprises: the input voltage is increased to the maximum voltage with large fluctuation of voltage during the charge and discharge test of the storage battery on the power supply bus, whether the power supply clamping piece trips or not is detected, and the abnormity of the power supply clamping piece is judged when the power supply clamping piece trips.
Optionally, detecting whether the power card to be tested normally operates further includes:
the voltage stabilizing circuit test is used for testing the performance of the voltage stabilizing circuit by changing the input voltage;
the method comprises the steps of performing an input voltage step test, and testing whether a power supply clamping piece trips or not by setting the rapid change amplitude of the input voltage;
in a long-term live operation test, the power supply clamping piece does not have abnormity when running with load for one month;
the interlocking starting and tripping test of the two power supply clamping pieces is carried out.
Step S400: when the power supply clamping piece to be tested normally operates, sending a renovation completion instruction;
step S500: and when the power card to be tested runs in a fault, sending a fault instruction.
Optionally, the fault instruction can be sent to the alarm, and when the alarm receives the fault instruction, an alarm is sent out, so that field personnel are reminded to carry out maintenance detection.
Optionally, the fault instruction may also be sent to a mobile terminal such as a mobile phone or a computer through the wireless communication device.
The nuclear power plant safety level power renovation maintenance method of the embodiment of the application is through discerning the trouble device, the judgement of the power fastener that awaits measuring whether the trouble device hinders the normal operating of the power fastener that awaits measuring, if the trouble device hinders the normal operating of the power fastener that awaits measuring sends and is used for with the trouble device replacement is with the control signal of new component, detects whether receive the replacement and accomplishes the instruction and when receiving the replacement and accomplish the instruction, detects whether the power fastener that awaits measuring normally operates, has realized the renovation maintenance to the power fastener, has avoided the power fastener to endanger the problem of nuclear power plant safe operation because of faults such as its partial components and parts are ageing, parameter drift, the power fastener that has solved the nuclear power plant existence harms because of faults such as its components and parts are ageing, parameter drift.
It should be understood that, the sequence numbers of the steps in the foregoing embodiments do not imply an execution sequence, and the execution sequence of each process should be determined by its function and inherent logic, and should not constitute any limitation to the implementation process of the embodiments of the present application.
Referring to fig. 8, a second aspect of the embodiments of the present application provides a nuclear power plant safety level power source refurbishment maintenance apparatus, which is configured to implement the nuclear power plant safety level power source refurbishment maintenance method according to the first aspect of the embodiments of the present application, and includes:
the identification module 10 is used for identifying a fault device of the power supply clamping piece to be detected;
the judging module 20 is used for judging whether the fault device obstructs the normal operation of the power supply clamping piece to be detected, and if the fault device obstructs the normal operation of the power supply clamping piece to be detected, sending a control signal for replacing the fault device with a new component; and
the detection module 30 detects whether a replacement completion instruction is received, detects whether the power supply clamping piece to be detected normally operates when the replacement completion instruction is received, sends a renovation completion instruction when the power supply clamping piece to be detected normally operates, and sends a fault instruction when the power supply clamping piece to be detected runs in a fault.
FIG. 9 is a schematic diagram of a nuclear power plant safety-level power source retrofit service arrangement provided by a third aspect of an embodiment of the present application. As shown in fig. 9, the nuclear power plant safety-level power source retrofit maintenance device 6 of this embodiment includes: a processor 60, a memory 61 and a computer program 62 stored in said memory 61 and executable on said processor 60. The processor 60, when executing the computer program 62, implements the steps in each of the above-described embodiments of the nuclear plant safety-level power retrofit servicing method, such as the steps 101-104 shown in FIG. 1. Alternatively, the processor 60, when executing the computer program 62, implements the functions of the modules/units in the above-described device embodiments, such as the functions of the modules 10 to 30 shown in fig. 8.
Illustratively, the computer program 62 may be partitioned into one or more modules/units that are stored in the memory 61 and executed by the processor 60 to accomplish the present application. The one or more modules/units may be a series of computer program instruction segments capable of performing specific functions for describing the execution of the computer program 62 in the plant safety-level power retrofit service apparatus 6. For example, the computer program 62 may be divided into a synchronization module, a summarization module, an acquisition module, and a return module (a module in a virtual device), and each module specifically functions as follows:
the nuclear power plant safety-level power supply renovation maintenance device 6 can be a desktop computer, a notebook computer, a palm computer, a cloud server and other computing equipment. The nuclear power plant safety-level power retrofit maintenance device may include, but is not limited to, a processor 60 and a memory 61. It will be understood by those skilled in the art that fig. 9 is merely an example of a nuclear plant safety level power retrofit service apparatus 6, and does not constitute a limitation of the nuclear plant safety level power retrofit service apparatus 6, and may include more or fewer components than those shown, or some components in combination, or different components, for example, the nuclear plant safety level power retrofit service apparatus may further include input and output devices, network access devices, buses, etc.
The Processor 60 may be a Central Processing Unit (CPU), other general purpose Processor, a Digital Signal Processor (DSP), an Application Specific Integrated Circuit (ASIC), an off-the-shelf Programmable Gate Array (FPGA) or other Programmable logic device, discrete Gate or transistor logic, discrete hardware components, etc. A general purpose processor may be a microprocessor or the processor may be any conventional processor or the like.
The storage 61 may be an internal storage unit of the nuclear power plant safety power supply retrofit service device 6, such as a hard disk or a memory of the nuclear power plant safety power supply retrofit service device 6. The memory 61 may also be an external storage device of the nuclear power plant safety level power supply retrofit maintenance device 6, such as a plug-in hard disk, a Smart Media Card (SMC), a Secure Digital (SD) Card, a Flash memory Card (Flash Card), and the like, which are equipped on the nuclear power plant safety level power supply retrofit maintenance device 6. Further, the memory 61 may also include both an internal storage unit and an external storage device of the nuclear plant safety-level power retrofit service device 6. The memory 61 is used to store the computer program and other programs and data required for the nuclear plant safety level power retrofit service device. The memory 61 may also be used to temporarily store data that has been output or is to be output.
It will be apparent to those skilled in the art that, for convenience and brevity of description, only the above-mentioned division of the functional units and modules is illustrated, and in practical applications, the above-mentioned function distribution may be performed by different functional units and modules according to needs, that is, the internal structure of the apparatus is divided into different functional units or modules to perform all or part of the above-mentioned functions. Each functional unit and module in the embodiments may be integrated in one processing unit, or each unit may exist alone physically, or two or more units are integrated in one unit, and the integrated unit may be implemented in a form of hardware, or in a form of software functional unit. In addition, specific names of the functional units and modules are only for convenience of distinguishing from each other, and are not used for limiting the protection scope of the present application. The specific working processes of the units and modules in the system may refer to the corresponding processes in the foregoing method embodiments, and are not described herein again.
In the above embodiments, the descriptions of the respective embodiments have respective emphasis, and reference may be made to the related descriptions of other embodiments for parts that are not described or illustrated in a certain embodiment.
Those of ordinary skill in the art will appreciate that the various illustrative elements and algorithm steps described in connection with the embodiments disclosed herein may be implemented as electronic hardware or combinations of computer software and electronic hardware. Whether such functionality is implemented as hardware or software depends upon the particular application and design constraints imposed on the implementation. Skilled artisans may implement the described functionality in varying ways for each particular application, but such implementation decisions should not be interpreted as causing a departure from the scope of the present application.
In the embodiments provided in the present application, it should be understood that the disclosed apparatus and method may be implemented in other ways. For example, the above-described apparatus embodiments are merely illustrative, and for example, the division of the modules or units is only one logical division, and there may be other divisions when actually implemented, for example, a plurality of units or components may be combined or may be integrated into another system, or some features may be omitted, or not executed. In addition, the shown or discussed mutual coupling or direct coupling or communication connection may be an indirect coupling or communication connection through some interfaces, devices or units, and may be in an electrical, mechanical or other form.
The units described as separate parts may or may not be physically separate, and parts displayed as units may or may not be physical units, may be located in one place, or may be distributed on a plurality of network units. Some or all of the units can be selected according to actual needs to achieve the purpose of the solution of the embodiment.
In addition, functional units in the embodiments of the present application may be integrated into one processing unit, or each unit may exist alone physically, or two or more units are integrated into one unit. The integrated unit can be realized in a form of hardware, and can also be realized in a form of a software functional unit.
The integrated modules/units, if implemented in the form of software functional units and sold or used as separate products, may be stored in a computer readable storage medium. Based on such understanding, all or part of the flow in the method of the embodiments described above can be realized by a computer program, which can be stored in a computer-readable storage medium and can realize the steps of the embodiments of the methods described above when the computer program is executed by a processor. . Wherein the computer program comprises computer program code, which may be in the form of source code, object code, an executable file or some intermediate form, etc. The computer-readable medium may include: any entity or device capable of carrying the computer program code, recording medium, usb disk, removable hard disk, magnetic disk, optical disk, computer Memory, Read-Only Memory (ROM), Random Access Memory (RAM), electrical carrier wave signals, telecommunications signals, software distribution medium, and the like. It should be noted that the computer readable medium may contain content that is subject to appropriate increase or decrease as required by legislation and patent practice in jurisdictions, for example, in some jurisdictions, computer readable media does not include electrical carrier signals and telecommunications signals as is required by legislation and patent practice.
The above-mentioned embodiments are only used for illustrating the technical solutions of the present application, and not for limiting the same; although the present application has been described in detail with reference to the foregoing embodiments, it should be understood by those of ordinary skill in the art that: the technical solutions described in the foregoing embodiments may still be modified, or some technical features may be equivalently replaced; such modifications and substitutions do not substantially depart from the spirit and scope of the embodiments of the present application and are intended to be included within the scope of the present application.

Claims (10)

1. A nuclear power plant safety level power supply renovation maintenance method is characterized by comprising the following steps:
identifying a fault device of a power supply clamping piece to be detected;
judging whether the fault device obstructs normal operation of the power supply clamping piece to be detected, and if the fault device obstructs normal operation of the power supply clamping piece to be detected, sending a control signal for replacing the fault device with a new component;
detecting whether a replacement completion instruction is received or not, and detecting whether the power supply clamping piece to be detected normally operates or not when the replacement completion instruction is received;
when the power supply card to be tested normally operates, sending a renovation completion instruction;
and when the power card to be tested runs in a fault, sending a fault instruction.
2. The nuclear power plant safety-level power supply renovation maintenance method of claim 1, wherein the identifying the faulty component of the power supply card to be tested comprises:
confirming the actual service life of the electrolytic capacitor in the power supply clamping piece to be tested through theoretical calculation;
comparing the actual service life with a preset service life, and taking the lowest value of the actual service life and the preset service life as a target service life;
judging whether the electrolytic capacitor is an aged component or not according to the target service life;
and if the electrolytic capacitor is an aged component, marking the electrolytic capacitor as a fault component.
3. The nuclear power plant safety-level power supply renovation maintenance method of claim 1 or 2, wherein the step of identifying the faulty component of the power supply card to be tested comprises the steps of:
detecting actual operation parameters of components of the power supply clamping piece to be detected;
judging whether the component has parameter drift or not according to the actual operation parameters and the standard operation parameters of the component;
and if the component has parameter drift, marking the component as a fault component.
4. The nuclear power plant safety-level power source renovation maintenance method of claim 2, wherein the confirming of the actual usable life of the electrolytic capacitor in the component through theoretical calculation comprises:
obtaining the service life, the limit working temperature, the ripple current function and the rated working voltage of the electrolytic capacitor at the highest service temperature;
collecting the actual working environment temperature of the electrolytic capacitor;
detecting the actual working voltage of the electrolytic capacitor;
and calculating the actual service life of the electrolytic capacitor according to the service life of the electrolytic capacitor at the highest service temperature, the limit working temperature, the actual working environment temperature, the ripple current function, the rated working voltage and the actual working voltage.
5. The nuclear power plant safety-level power source renovation maintenance method of claim 4, wherein the confirming of the actual service life of the electrolytic capacitor in the component through theoretical calculation further comprises:
acquiring actual ripple current of the electrolytic capacitor;
comparing the actual ripple current with the rated ripple current;
if the actual ripple current is smaller than the rated ripple current, calculating the actual service life of the electrolytic capacitor according to the service life of the electrolytic capacitor at the highest service temperature, the limit working temperature, the actual working environment temperature, the rated working voltage and the actual working voltage;
and if the actual ripple current is larger than or equal to the rated ripple current, calculating the actual usable life of the electrolytic capacitor according to the service life of the electrolytic capacitor at the highest service temperature, the limit working temperature, the actual working environment temperature, the ripple current function, the rated working voltage and the actual working voltage.
6. The nuclear power plant safety-level power supply renovation maintenance method of claim 1, 2, 4 or 5, wherein the step of judging whether the fault device obstructs normal operation of the power supply card to be tested comprises the steps of:
simulating the running state of the power supply clamping piece to be tested when the fault device fails through simulation;
detecting whether the power supply clamping piece to be detected works or not;
when the power supply clamping piece does not work, judging that the fault device obstructs the normal operation of the power supply clamping piece to be detected;
when the power supply clamping piece works, detecting the output waveform of the power supply clamping piece to be detected;
and comparing the output waveform with the standard output waveform, and judging that the fault device obstructs the normal operation of the power supply clamping piece to be detected when the output waveform is inconsistent with the standard output waveform.
7. The nuclear power plant safety-level power supply renovation maintenance method of claim 1, 2, 4 or 5, wherein the step of detecting whether the power supply card to be tested normally operates comprises the steps of:
detecting whether the parameters of the component after the replacement of the power supply clamping piece to be detected are standard parameters or not;
judging whether the welding of each component of the circuit board is normal or not through image acquisition;
and detecting whether each working parameter of the power supply card to be detected is a target working parameter.
8. A nuclear power plant safety level power renovates maintenance device which characterized in that includes:
the identification module is used for identifying a fault device of the power supply clamping piece to be detected;
the judging module is used for judging whether the fault device obstructs the normal operation of the power supply clamping piece to be detected, and if the fault device obstructs the normal operation of the power supply clamping piece to be detected, sending a control signal for replacing the fault device with a new component; and
the detection module detects whether a replacement completion instruction is received or not, detects whether the power supply clamping piece to be detected normally operates or not when the replacement completion instruction is received, sends a renovation completion instruction when the power supply clamping piece to be detected normally operates, and sends a fault instruction when the power supply clamping piece to be detected runs in a fault.
9. A nuclear power plant safety-level power retrofit service device comprising a memory, a processor and a computer program stored in the memory and executable on the processor, wherein the processor when executing the computer program implements the steps of the method according to any one of claims 1 to 7.
10. A computer-readable storage medium, in which a computer program is stored which, when being executed by a processor, carries out the steps of the method according to any one of claims 1 to 7.
CN202010245311.XA 2020-03-31 2020-03-31 Nuclear power plant safety power supply renovation and maintenance method and device Active CN111341477B (en)

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