CN117917582A - Nuclear reactor control rod position measurement signal channel automatic verification method and device - Google Patents
Nuclear reactor control rod position measurement signal channel automatic verification method and device Download PDFInfo
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- CN117917582A CN117917582A CN202211286384.9A CN202211286384A CN117917582A CN 117917582 A CN117917582 A CN 117917582A CN 202211286384 A CN202211286384 A CN 202211286384A CN 117917582 A CN117917582 A CN 117917582A
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- 238000012795 verification Methods 0.000 title claims abstract description 64
- 238000005259 measurement Methods 0.000 title claims abstract description 36
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- 238000002347 injection Methods 0.000 claims abstract description 18
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- 230000008054 signal transmission Effects 0.000 claims abstract description 4
- 238000006243 chemical reaction Methods 0.000 claims description 7
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- 238000012360 testing method Methods 0.000 claims description 3
- 230000006698 induction Effects 0.000 description 4
- 238000012986 modification Methods 0.000 description 3
- 230000004048 modification Effects 0.000 description 3
- 230000006978 adaptation Effects 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 2
- 230000008878 coupling Effects 0.000 description 2
- 238000010168 coupling process Methods 0.000 description 2
- 238000005859 coupling reaction Methods 0.000 description 2
- 238000012545 processing Methods 0.000 description 2
- 239000006096 absorbing agent Substances 0.000 description 1
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- 230000033228 biological regulation Effects 0.000 description 1
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- 238000007689 inspection Methods 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 239000000696 magnetic material Substances 0.000 description 1
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- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention relates to the field of reactor control, in particular to an automatic verification method and device for a nuclear reactor control rod position measurement signal channel. The automatic verification method comprises the following steps: signal injection is realized through a reserved interface of the field coding module, and the measuring rod position of the physical range after decoding is acquired through a network communication party; and comparing whether the actual measured rod position is the same as the expected measured rod position corresponding to the signal injection by automatic verification software in the upper computer, and judging whether the signal transmission channel is normal. The invention sets two modes: the manual input verification and the one-key complete verification respectively realize the accurate verification of specific rod positions and the quick verification of the full rod position traversal of the established sequence, can automatically judge the verification result, avoid human errors, improve the working efficiency and reduce the labor cost.
Description
Technical Field
The invention relates to the field of reactor control, in particular to an automatic verification method and device for a nuclear reactor control rod position measurement signal channel.
Background
Control rods are commonly used as neutron absorbers in nuclear reactors to control core neutron flux levels. The control rod position detector is used as a special instrument, and detects the height of the control rod in the reactor core by utilizing the induction voltage generated in the measuring coil by the electromagnetic induction principle.
The rod position detection coil mainly comprises 1 primary coil covering the full stroke, 2 auxiliary coils respectively positioned at the upper end and the lower end, and 5 groups of 32 secondary coils (the coils are arranged at intervals of 8 mechanical steps).
The primary coil is excited by alternating current to excite an alternating magnetic field. The auxiliary coil is used as negative feedback of current regulation of the primary coil and is used for stabilizing the current of the primary coil and providing a stable magnetic field for coupling of the secondary coil, so that the induction voltage of the secondary coil only depends on the coupling of the driving rod.
The secondary coil generates an induced voltage in the alternating magnetic field, but the voltage amplitude is close to zero, and the induced voltage of the secondary coil increases sharply (reaches the volt level) when the driving rod made of the magnetic material passes through. And 5 groups of secondary coils are separated, the coils in the same group are reversely connected in series, the induced voltages are mutually offset due to the opposite polarities, and the amplitude of the induced terminal voltage of each group of coils only depends on the top position of the driving rod. The secondary coil end voltage is processed by a rod position encoding module and is converted into a measuring rod position, so that the secondary coil is also called a measuring coil.
The primary coil of the rod position detector is powered by the power supply module, and the auxiliary coil provides negative feedback to reduce the influence of temperature or electromagnetic interference on the induction voltage of the measuring coil.
The induced voltage of the measuring coil is sent to a processing and encoding module, and high-low level signals are generated through rectification, filtering and threshold comparison, namely Gray code signals are sent to a rod position processing cabinet.
The measuring coils are divided into A, B, C, D, E groups, and adjacent coils in the groups are connected in reverse series. Only one measuring coil is arranged in every 8 mechanical steps, so that only one bit in any adjacent codes is different, the gray code distribution is adopted, and the transmission error rate is the lowest.
The induction voltages at the two ends of the coil are filtered, rectified and compared with threshold values by the coding module to form a group of signals characterized in an on-off mode, the signals are collected into binary signals by the input module, and the binary signals are converted into control rod positions of a physical range by software decoding for personnel monitoring and alarm logic.
As the service time increases, the detectors, coding modules, input modules, software, connectors, cables, etc. on the rod position measurement channel may fail. The current verification method is to manually check whether the expected signal is met by manually injecting the signal. As the number of measurement coils increases, the number of signal combinations increases exponentially; with the increase of the number of the detectors, the channel verification times are multiplied, so that the manual verification scheme takes longer time. Meanwhile, because the binary signals of two adjacent measuring rod positions are only different by one position, the probability of human error is high.
Disclosure of Invention
The invention aims to solve the technical problems that: the method and the device for automatically verifying the nuclear reactor control rod position measurement signal channel can automatically judge the verification result, avoid human error, improve the working efficiency and reduce the labor cost.
The invention provides an automatic verification method for a nuclear reactor control rod position measurement signal channel, which comprises the following steps:
The device using the automatic verification method realizes signal injection through a reserved interface of the field coding module, and acquires the measurement rod position decoded into a physical range through a network communication mode;
And comparing whether the actual measured rod position is the same as the expected measured rod position corresponding to the signal injection by automatic verification software in the upper computer, thereby judging whether the signal transmission channel is normal, and displaying and storing a verification result.
Preferably, the upper computer provides a manual input verification mode, specifically:
And manually inputting a physical measuring range bar bit or a binary gray code, verifying whether the physical measuring range bar bit or the binary gray code is the same as the expected measuring bar bit corresponding to the signal injection, and displaying the physical measuring range bar bit or the binary gray code in two forms in a display unit.
Preferably, when the manual input is verified, another bar position can be switched at any time.
Preferably, the upper computer provides an automatic verification mode, specifically:
The multi-channel fast verification of the full-bar bit traversal according to the established sequence.
Preferably, the time interval for switching between adjacent rod bits is set prior to verification, and during verification, the rod bits are observed to continuously change from low to high and from high to low.
The invention provides an automatic verification device for a nuclear reactor control rod position measurement signal channel, which is connected with a coding module through a coding module signal injection interface and is connected with a rod position measurement system through an acquisition interface.
Preferably, the automatic verification device includes:
The base plate is provided with a PLC power module, a PLC controller module, a PLC communication module and a PLC digital quantity output module;
The PLC power module is a PLC controller module, a PLC communication module and a PLC digital quantity output module for supplying power through the bottom plate;
the PLC controller module is connected and communicated with the upper computer by using a network cable, so that the downloading of the software configuration from the upper computer to the PLC is realized, and the test real-time data is uploaded from the PLC to the upper computer;
the PLC communication module is connected and communicated with the rod control system by using a network cable, so that the acquisition and input of the site measurement rod position are realized;
The PLC digital quantity output module is connected to the wiring terminal block by using a PLC prefabricated cable, converted into a hard wiring which passes through a flange of the shell of the verification device, and connected to the rod position coding module by a connector matched with the reserved interface.
Preferably, the PLC power supply module is a 24V power supply module and is directly supplied by an AC-DC conversion power supply module;
The battery and the AC-DC conversion power supply module form an uninterrupted power supply unit.
Preferably, the PLC of the automatic verification device and the rod position measuring system adopt the same model of PLC.
Compared with the prior art, the automatic verification method and the device for the nuclear reactor control rod position measurement signal channel have the following beneficial effects:
(1) Under the condition of not changing the existing equipment and interfaces, the software replaces the manual work, so that the automatic verification of the control rod position measurement signal channel is realized, and the improvement of the working efficiency is realized;
(2) Because the measuring rod position is different from one adjacent signal according to the Gray code coding rule, the software is used for avoiding the human error judgment of manual dialing;
(3) By replacing signal injection and rod position acquisition equipment, software does not need to be changed or subjected to adaptive fine adjustment, and can be compatible with various control rod position measurement systems, and certain expansion capacity is achieved.
Drawings
FIG. 1 shows a control rod position measurement signal path auto-verification flow chart;
FIG. 2 shows a schematic diagram of an automatic verification device;
in the drawing the view of the figure,
1 Is a rod position detector, 2 is a measuring rod position coding module, and 3 is a measuring rod position Gray code acquisition module; 4 is a decoding module; 5 is rod position measurement; 6 is an automatic verification device; 7 is a coding module signal injection interface; 8 is a measuring rod position acquisition interface; 9 is a PLC power module; 10 is a PLC controller module; 11 is a PLC communication module; 12 is a PLC digital quantity output module; 13 is a bottom plate; 14 is an ac-dc conversion power module; 15 is a battery; 16 is a wiring terminal block; and 17 is an upper computer.
Detailed Description
For a further understanding of the present invention, embodiments of the invention are described below in conjunction with the examples, but it should be understood that these descriptions are merely intended to illustrate further features and advantages of the invention, and are not limiting of the invention.
The embodiment of the invention discloses an automatic verification method for a nuclear reactor control rod position measurement signal channel, which comprises the following steps:
The device using the automatic verification method realizes signal injection through a reserved interface of the field coding module, and acquires the measurement rod position decoded into a physical range through a network communication mode;
And comparing whether the actual measured rod position is the same as the expected measured rod position corresponding to the signal injection by automatic verification software of the upper computer, judging whether the signal transmission channel is normal, and displaying and storing a verification result.
There are two modes of authentication: manual input verification and one-key full verification.
The upper computer provides a manual input verification mode, specifically:
And manually inputting a physical measuring range bar bit or a binary gray code, verifying whether the physical measuring range bar bit or the binary gray code is the same as the expected measuring bar bit corresponding to the signal injection, and displaying the physical measuring range bar bit or the binary gray code in two forms in a display unit.
The manual input mode is used for verifying specific rod positions, is mainly suitable for accurately checking the suspected fault channels and rod positions, can provide long-term stable input and is convenient for fault point positioning; can be switched to another rod position at any time, and is convenient for comparison and judgment. The physical measuring range bar bit or binary Gray code can be input selectively according to the requirement. The display unit is displayed in two forms, which is beneficial to comparison.
The upper computer provides an automatic verification mode, specifically:
The multi-channel fast verification of the full-bar bit traversal according to the established sequence.
The automatic verification mode is suitable for preventive inspection, and realizes the rapid verification of multi-channel simultaneous full-bar-bit traversal according to a set sequence. The time interval for switching between adjacent rod positions may be manually set to facilitate observation of the continuous change in rod position from low to high and from high to low by an engineer station.
The hardware is based on a Programmable Logic Controller (PLC), and comprises a processor module, a bottom plate, a power module, an output module, a communication cable and an upper computer, wherein other hardware comprises a connector and a cable which are connected with a reserved interface of the coding module, a power supply unit, a power cable, an uninterrupted power supply unit formed by a battery, a printer and the like.
The output voltage level is determined by actual requirements, and a voltage regulating device is configured; the communication module is adapted to the actual application scene and can collect data from the field rod control system or the DCS.
The embodiment of the invention discloses an automatic verification device for a nuclear reactor control rod position measurement signal channel, which comprises the following components: the rod position detector 1, the measuring rod position coding module 2, the measuring rod position Gray code acquisition module 3, the decoding module 4 and the rod position measuring system 5 are connected in sequence; the automatic verification device 6 is connected with the coding module 2 through the coding module signal injection interface 7, is connected with the rod position measuring system 5 through the acquisition interface 8, and can realize compatibility with various control rod position measuring systems without changing or adaptively fine-tuning by replacing signal injection and rod position acquisition equipment.
In FIG. 1, a measurement rod position is input to an automatic verification device through a measurement rod position acquisition interface; outputting the analog rod position signal to the coding module through the signal injection interface;
the automatic verification device is miniaturized in fig. 2.
In fig. 2, a base plate 13, a PLC power module 9, a PLC controller module 10, a PLC communication module 11, and a PLC digital quantity output module 12 are mounted on the base plate 13;
The PLC power module 9 supplies power to the PLC controller module 10, the PLC communication module 11 and the PLC digital quantity output module 12 through the bottom plate 13;
The PLC controller module 10 is connected and communicated with the upper computer 17 by using a network cable, so that the software configuration is downloaded from the upper computer 17 to the PLC, and the test real-time data is uploaded from the PLC to the upper computer 17;
the PLC communication module 11 is connected and communicated with the rod position measuring system or the DCS by using a network cable, so that the acquisition and input of the on-site measuring rod position are realized;
The PLC of the automatic verification device and the rod position measuring system adopt the same model of PLC, so that the communication compatibility problem is avoided, and the communication is convenient to realize;
The PLC digital quantity output module 12 is connected to the terminal block 16 using PLC prefabricated cables, converted into hard wiring through the flange of the verification device housing, and connected to the rod position encoding module 2 through connectors matching with the reserved interfaces. And setting a voltage amplitude adjusting circuit to match the output voltage with the voltage grade required by the coding module.
Wherein, the PLC power module is a 24V power module and is directly supplied by the AC-DC conversion power module 14;
The 220V AC power for factories is converted into 24V DC power by the AC/DC conversion power module 14, and an uninterruptible power supply unit composed of a battery 15 is configured.
And in the upper computer, based on PLC configuration software, developing automatic verification software for the control rod position measurement signal channel.
The above description of the embodiments is only for aiding in the understanding of the method of the present invention and its core ideas. It should be noted that it will be apparent to those skilled in the art that various modifications and adaptations of the invention can be made without departing from the principles of the invention and these modifications and adaptations are intended to be within the scope of the invention as defined in the following claims.
The previous description of the disclosed embodiments is provided to enable any person skilled in the art to make or use the present invention. Various modifications to these embodiments will be readily apparent to those skilled in the art, and the generic principles defined herein may be applied to other embodiments without departing from the spirit or scope of the invention. Thus, the present invention is not intended to be limited to the embodiments shown herein but is to be accorded the widest scope consistent with the principles and novel features disclosed herein.
Claims (9)
1. The automatic verification method for the nuclear reactor control rod position measurement signal channel is characterized by comprising the following steps of:
The device using the automatic verification method realizes signal injection through a reserved interface of the field coding module, and acquires the measurement rod position decoded into a physical range through a network communication mode;
And comparing whether the actual measured rod position is the same as the expected measured rod position corresponding to the signal injection by automatic verification software in the upper computer, thereby judging whether the signal transmission channel is normal, and displaying and storing a verification result.
2. The method for automatically verifying a nuclear reactor control rod position measurement signal channel according to claim 1, wherein the upper computer provides a manual input verification mode, specifically:
And manually inputting a physical measuring range bar bit or a binary gray code, verifying whether the physical measuring range bar bit or the binary gray code is the same as the expected measuring bar bit corresponding to the signal injection, and displaying the physical measuring range bar bit or the binary gray code in two forms in a display unit.
3. The method for automatically verifying a nuclear reactor control rod position measurement signal path according to claim 2, wherein another rod position is switched at any time when the verification is manually inputted.
4. The method for automatically verifying a nuclear reactor control rod position measurement signal channel according to claim 1, wherein the upper computer provides an automatic verification mode, specifically:
The multi-channel fast verification of the full-bar bit traversal according to the established sequence.
5. The method for automatically verifying a nuclear reactor control rod position measurement signal path according to claim 4, wherein a time interval for switching between adjacent rod positions is set before verification, and wherein a continuous change of rod positions from low to high and from high to low is observed during verification.
6. The automatic verification device of the nuclear reactor control rod position measurement signal channel is characterized in that the automatic verification device is connected with a coding module through a coding module signal injection interface and is connected with a rod position measurement system through an acquisition interface.
7. The nuclear reactor control rod position measurement signal passage automatic verification device of claim 6, wherein the automatic verification device comprises:
The base plate is provided with a PLC power module, a PLC controller module, a PLC communication module and a PLC digital quantity output module;
The PLC power module is a PLC controller module, a PLC communication module and a PLC digital quantity output module for supplying power through the bottom plate;
the PLC controller module is connected and communicated with the upper computer by using a network cable, so that the downloading of the software configuration from the upper computer to the PLC is realized, and the test real-time data is uploaded from the PLC to the upper computer;
the PLC communication module is connected and communicated with the rod control system by using a network cable, so that the acquisition and input of the site measurement rod position are realized;
The PLC digital quantity output module is connected to the wiring terminal block by using a PLC prefabricated cable, converted into a hard wiring which passes through a flange of the shell of the verification device, and connected to the rod position coding module by a connector matched with the reserved interface.
8. The nuclear reactor control rod position measurement signal path automatic verification device of claim 6, wherein the PLC power module is a 24V power module directly supplied by an ac-dc conversion power module;
The battery and the AC-DC conversion power supply module form an uninterrupted power supply unit.
9. The nuclear reactor control rod position measurement signal path automatic verification device of claim 6, wherein the PLC of the automatic verification device is the same model as the rod position measurement system.
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| Application Number | Priority Date | Filing Date | Title |
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| CN202211286384.9A CN117917582A (en) | 2022-10-20 | 2022-10-20 | Nuclear reactor control rod position measurement signal channel automatic verification method and device |
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| CN202211286384.9A CN117917582A (en) | 2022-10-20 | 2022-10-20 | Nuclear reactor control rod position measurement signal channel automatic verification method and device |
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| CN117917582A true CN117917582A (en) | 2024-04-23 |
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| CN202211286384.9A Pending CN117917582A (en) | 2022-10-20 | 2022-10-20 | Nuclear reactor control rod position measurement signal channel automatic verification method and device |
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