CN116773083A - Offline verification method and system for nuclear power plant transmitter - Google Patents

Offline verification method and system for nuclear power plant transmitter Download PDF

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Publication number
CN116773083A
CN116773083A CN202310602382.4A CN202310602382A CN116773083A CN 116773083 A CN116773083 A CN 116773083A CN 202310602382 A CN202310602382 A CN 202310602382A CN 116773083 A CN116773083 A CN 116773083A
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China
Prior art keywords
signal
verification
sensor
nuclear
transmitter
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CN202310602382.4A
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Chinese (zh)
Inventor
蒋永强
邹志励
向绍斌
刘瑞峡
郝俊飞
刘世银
吴超
陈辉
简立鸿
李靖
余洋
张运龙
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Guangxi Fangchenggang Nuclear Power Co Ltd
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Guangxi Fangchenggang Nuclear Power Co Ltd
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Priority to CN202310602382.4A priority Critical patent/CN116773083A/en
Publication of CN116773083A publication Critical patent/CN116773083A/en
Pending legal-status Critical Current

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    • GPHYSICS
    • G01MEASURING; TESTING
    • G01LMEASURING FORCE, STRESS, TORQUE, WORK, MECHANICAL POWER, MECHANICAL EFFICIENCY, OR FLUID PRESSURE
    • G01L27/00Testing or calibrating of apparatus for measuring fluid pressure
    • G01L27/002Calibrating, i.e. establishing true relation between transducer output value and value to be measured, zeroing, linearising or span error determination
    • G01L27/005Apparatus for calibrating pressure sensors

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  • Chemical & Material Sciences (AREA)
  • Analytical Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • General Physics & Mathematics (AREA)
  • Measuring Fluid Pressure (AREA)

Abstract

The invention discloses a method and a system for offline verification of a nuclear power plant transmitter, which are suitable for a nuclear pressure transmitter, wherein the nuclear pressure transmitter comprises a sensor and a processing clamping piece, and the method comprises the following steps: s10, generating a flow direction control signal for controlling the flow direction of signals between the sensor and the processing clamp during verification according to the verification item, and a pressure-feeding control signal for controlling the magnitude of test pressure input to the sensor during verification; and S20, during verification, obtaining a measurement signal output by the processing clamping piece, and verifying the tested nuclear pressure transmitter according to the measurement signal and the verification item. By implementing the invention, workers can perform offline verification on the nuclear pressure transmitter in the places with complete equipment and good verification conditions, and the invention has positive effects of improving the verification efficiency, reducing the labor cost, the verification complexity and the radiation dosage and is beneficial to performance detection on the nuclear pressure transmitter which is not installed on the site.

Description

Offline verification method and system for nuclear power plant transmitter
Technical Field
The invention relates to the technical field of nuclear pressure transmitters, in particular to an offline verification method and system for a nuclear power plant transmitter.
Background
In a nuclear power plant, a nuclear pressure transmitter is mainly used for measuring important parameters such as liquid level, pressure, flow and the like, and is a basis for controlling and monitoring an important process system of the nuclear power plant, wherein a 6000-series transmitter of Lawslaisi in France is widely used. The 6000 series transmitter is different from other common transmitters in structure and comprises a sensor and a processing clamping piece which are arranged separately, wherein the sensor is positioned in a nuclear island, and the processing clamping piece is positioned in an electric factory building.
At present, the 6000 series transmitter is installed separately with the sensor and the processing clamping piece, so that the sensor and the processing clamping piece are required to be installed on site and then can be checked, the performance of the sensor cannot be determined before the sensor is applied to a site system, the performance of the processing clamping piece cannot be determined and adjusted, and the transmitter cannot be copied to determine the test performance. In the field verification, different staff are required to conduct pressure setting on the sensor and measurement and adjustment of electrical parameters of the clamping piece, and the defects of difficult communication, low verification efficiency, high labor cost and the like exist.
Disclosure of Invention
The invention aims to provide a method and a system for offline verification of a nuclear power plant transmitter.
The technical scheme adopted for solving the technical problems is as follows: an off-line verification method for a nuclear power plant transmitter is constructed, and is suitable for a nuclear pressure transmitter, wherein the nuclear pressure transmitter comprises a sensor and a processing clamping piece, and the method comprises the following steps:
s10, generating a flow direction control signal for controlling the flow direction of signals between the sensor and the processing clamping piece during verification according to the verification item, and a pressure supply control signal for controlling the magnitude of test pressure input to the sensor during verification;
and S20, during verification, acquiring a measurement signal output by the processing clamping piece, and verifying the tested nuclear pressure transmitter according to the measurement signal and a verification item.
Preferably, the verification item includes at least one of potentiometer calibration, linear testing, and card verification.
Preferably, the S10 includes: if the verification item is corrected by the potentiometer, generating a first flow direction control signal for controlling interaction of the sensor and the processing clamp, and generating a first pressure-supply control signal according to a set correction requirement; wherein the potentiometer correction comprises zero point correction and measuring range point correction;
in S20, verifying the measured nuclear level pressure transmitter based on the measurement signal and the verification term includes: the position of the correction potentiometer in the processing clamping piece is adjusted so that the measured nuclear pressure transmitter meets the requirements of zero and measuring range points; the correction potentiometer comprises a zero potentiometer and a measuring range point potentiometer.
Preferably, the S20 further includes: after the tested nuclear pressure transmitter is verified to be qualified, acquiring and recording an alternating current signal output by a sensor of the tested nuclear pressure transmitter when a test point is set, and taking the alternating current signal as a historical alternating current signal of a corresponding sensor;
the S10 further includes: if the verification item is the card verification, generating a second flow direction control signal for controlling the disconnection interaction of the sensor and the processing card;
in S20, verifying the measured nuclear level pressure transmitter according to the measurement signal and the verification item further includes: the method comprises the steps of obtaining a historical alternating current signal of a sensor of a processing clamp to be replaced, inputting an analog alternating current signal for simulating the historical alternating current signal into the processing clamp, and further enabling the processing clamp to meet the replacement requirement of the processing clamp to be replaced by adjusting the position of a correction potentiometer in the processing clamp.
Preferably, the S20 further includes:
if the position of the correction potentiometer cannot be adjusted to enable the measured nuclear pressure transmitter to meet the related requirements, judging that the measured nuclear pressure transmitter does not meet the requirements.
Preferably, the step S10 further includes: if the verification item is the linear test, generating a first flow direction control signal for controlling interaction of the sensor and the processing card, and sequentially generating a corresponding second pressure supply control signal according to a preset test point list; the preset test point list comprises a plurality of test voltage supply values and measurement reference values corresponding to each test voltage supply value; each of the test voltage supply values is used for setting a value of the second voltage supply control signal;
in S20, verifying the measured nuclear level pressure transmitter according to the measurement signal and the verification item further includes: and comparing the obtained measurement signal with the corresponding measurement reference value after outputting the second pressure-supplying control signal each time so as to judge whether the tested nuclear pressure transmitter meets the linearity requirement.
Preferably, in S10, the method further includes:
and controlling the signal flow direction between the sensor and the processing clamping piece through a preset signal management unit, inputting the test pressure to the sensor through a pressure supply unit, and collecting the measurement signal output by the processing clamping piece through a signal measurement unit.
The invention also constructs an offline verification system of a nuclear power plant transmitter, which is suitable for a nuclear pressure transmitter, wherein the nuclear pressure transmitter comprises a sensor and a processing clamping piece, and the system comprises:
the pressure supply unit is used for inputting test pressure to the sensor according to a pressure supply control signal during verification;
the signal measuring unit is used for collecting the measuring signal output by the processing clamping piece;
the signal management unit is used for controlling the signal flow direction between the sensor and the processing clamping piece according to the flow direction control signal during verification; and
the main control unit is used for generating the pressure supply control signal and the flow direction control signal according to the verification item, and verifying the tested nuclear pressure transmitter according to the acquired measurement signal and the verification item during verification.
Preferably, the signal measurement unit is further used for collecting an alternating current signal output by the sensor;
the offline verification system of the nuclear power plant transmitter further comprises a signal simulation unit and a database;
the signal simulation unit is connected with the signal management unit and is used for simulating the output signal of the sensor;
the database is used for storing the alternating current signals collected when the sensor is checked to be qualified in the past;
the main control unit also obtains a historical alternating current signal of the sensor of the to-be-replaced processing card through the database, and controls the signal simulation unit to output a simulation alternating current signal to the sensor of the to-be-replaced processing card according to the historical alternating current signal so as to perform card verification.
Preferably, the signal management unit includes: the device comprises a sensor interface, a change-over switch, a clamping piece interface, a measuring unit interface and an analog unit interface;
the first end, the second end and the third end of the sensor interface are sequentially connected with the first excitation signal input end, the alternating current signal output end and the second excitation signal input end of the sensor, the second end of the sensor interface is also connected with the input end of the change-over switch, the output end of the change-over switch is connected with the second end of the clamping piece interface, and the first end and the third end of the sensor interface are also connected with the first end and the third end of the clamping piece interface;
the control end of the change-over switch is connected with the main control unit so as to control the on-off of the change-over switch according to the flow direction control signal;
the first, second, third, fourth and fifth ends of the clamping piece interface are sequentially connected with the first excitation signal output end, the alternating current signal input end, the second excitation signal output end, the first measurement signal output end and the second measurement signal output end of the processing clamping piece, and the second, fourth and fifth ends of the clamping piece interface are also connected with the first, third and fourth ends of the measurement unit interface;
the first end and the second end of the measuring unit interface are connected with the first measuring port of the signal measuring unit, the second end of the measuring unit interface is grounded, and the third end and the fourth end of the measuring unit interface are connected with the second measuring port of the signal measuring unit;
the first end of the analog unit interface is connected with the second end of the clamping piece interface, the second end of the analog unit interface is grounded, and the first end and the second end of the analog unit interface are also connected with the signal analog unit.
By implementing the technical scheme of the invention, a flow direction control signal for controlling the flow direction of signals between the sensor and the processing clamping piece during verification and a pressure supply control signal for controlling the magnitude of test pressure input to the sensor during verification can be generated according to the verification item, so as to prepare for corresponding verification items; during verification, the tested nuclear pressure transmitter is verified according to the verification items and the acquired measurement signals output by the processing clamping pieces; by implementing the invention, workers can carry out offline verification on the nuclear pressure transmitter in the places with complete equipment and good verification conditions, remote communication steps are omitted, positive effects on improving verification efficiency, reducing labor cost, verification complexity and radiation dosage are achieved, performance detection on the nuclear pressure transmitter which is not installed on site is facilitated, and the condition of the transmitter when installed on site is ensured to meet application requirements.
Drawings
The invention will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is a flow chart of a method for offline verification of a nuclear power plant transmitter in some embodiments of the invention;
FIG. 2 is a schematic diagram of an offline verification system for a nuclear power plant transmitter in accordance with some embodiments of the present invention;
fig. 3 is a schematic diagram of a signal management unit according to some embodiments of the invention.
Detailed Description
For a clearer understanding of technical features, objects and effects of the present invention, a detailed description of embodiments of the present invention will be made with reference to the accompanying drawings.
It should be noted that the flow diagrams depicted in the figures are merely exemplary and do not necessarily include all of the elements and operations/steps, nor are they necessarily performed in the order described. For example, some operations/steps may be decomposed, and some operations/steps may be combined or partially combined, so that the order of actual execution may be changed according to actual situations.
The block diagrams depicted in the figures are merely functional entities and do not necessarily correspond to physically separate entities. That is, the functional entities may be implemented in software, or in one or more hardware modules or integrated circuits, or in different networks and/or processor devices and/or microcontroller devices.
Referring to FIG. 1, a flow chart of a method for offline verification of a nuclear power plant transmitter for offline verification of a nuclear pressure transmitter that is not installed in an industrial site, wherein the nuclear pressure transmitter includes a sensor and a process clamp, in accordance with some embodiments of the present invention, is shown. The method comprises the following steps:
s10, generating a flow direction control signal for controlling the flow direction of signals between the sensor and the processing clamp during verification according to the verification item, and a pressure-feeding control signal for controlling the magnitude of test pressure input to the sensor during verification;
and S20, during verification, obtaining a measurement signal output by the processing clamping piece, and verifying the tested nuclear pressure transmitter according to the measurement signal and the verification item.
In this embodiment, a flow direction control signal for controlling the flow direction of a signal between the sensor and the process card at the time of verification and a pressure-supply control signal for controlling the magnitude of test pressure input to the sensor at the time of verification are generated in accordance with the verification items, in preparation for performing the corresponding verification items; during verification, the tested nuclear pressure transmitter is verified according to the verification items and the acquired measurement signals output by the processing clamping pieces; by implementing the invention, workers can carry out offline verification on the nuclear pressure transmitter in the places with complete equipment and good verification conditions, remote communication steps are omitted, positive effects on improving verification efficiency, reducing labor cost, verification complexity and radiation dosage are achieved, performance detection on the nuclear pressure transmitter which is not installed on site is facilitated, and the condition of the transmitter when installed on site is ensured to meet application requirements.
In an alternative embodiment, the verification items include at least one of potentiometer calibration, linear testing, and card verification. The potentiometer correction comprises zero point correction and measuring range point correction.
The purpose of zero point correction is to correct that the test pressure input by the sensor is zero, and the measurement signal output by the processing clamp is also characterized as the minimum value of the measuring range.
The purpose of the measuring range point correction is that when the test pressure input by the correction sensor is the measurable upper limit value, the measuring signal output by the processing clamping piece is also characterized as the maximum value of the measuring range.
The purpose of the linearity test is to test whether the test pressure and the measurement signal of the nuclear pressure transmitter meet the linearity requirements.
The purpose of the card check is to verify whether the processing card is in accordance with the application requirements after being matched with a certain sensor installed on the site. When the processing clamping piece in a certain nuclear-grade pressure transmitter fails and the sensor is normal, the clamping piece is verified for the new processing clamping piece, and after the matching of the processing clamping piece and the sensor of the nuclear-grade pressure transmitter is confirmed, the application requirements are met, so that the processing clamping piece can be replaced into the nuclear-grade pressure transmitter without online verification of the transmitter, and the maintenance efficiency is greatly improved.
In some embodiments, in step S10, further comprising: the signal flow direction between the sensor and the processing clamping piece is controlled through a preset signal management unit, the test pressure is input to the sensor through a preset pressure supply unit, and the measurement signal output by the processing clamping piece is acquired through a signal measurement unit.
Specifically, the signal management unit controls the on-off of a line between the alternating current signal output end of the sensor and the alternating current signal input end of the processing clamping piece according to the flow direction control signal, so as to control whether the processing clamping piece receives the alternating current signal output by the sensor. The pressure supply unit is used for inputting pressure to the tested sensor and controlling the pressure according to a pressure supply control signal; it is easily understood that the pressure supply unit may be a hydraulic pressure supply device commonly used in the art. The signal measuring unit may be a current and voltage acquisition device commonly used in the prior art.
In an alternative embodiment, step S10 includes: if the verification item is potentiometer correction, generating a first flow direction control signal for controlling interaction of the sensor and the processing clamp, and generating a first pressure supply control signal according to a set correction requirement;
in step S20, verifying the nuclear pressure transmitter under test based on the measurement signal and the verification term includes: the position of the correction potentiometer in the processing clamping piece is adjusted so that the measured nuclear pressure transmitter meets the requirements of zero and measuring range points; the correction potentiometer comprises a zero potentiometer and a measuring range point potentiometer.
In this embodiment, a first flow direction control signal (input to the signal management unit) is first generated, so that a switch in the signal management unit for controlling on-off of the ac signal output end of the sensor and the ac signal input end of the processing card is closed; then, zero point correction and span point correction are sequentially performed. Taking a common 6000 series transmitter as an example, the zero point correction process is as follows: firstly, generating a zero pressure signal (input to a pressure supply unit) to input zero test pressure (0) to a sensor, and then acquiring and displaying a measurement signal output by a processing clamping piece, wherein a worker can adjust the position of a zero potentiometer to enable the value of the measurement signal to meet the requirements of zero and a measuring range point (the measurement signal is displayed as 4 mA); the measuring range point correction process comprises the following steps: firstly, a measuring range point pressure signal is generated (input to a pressure supply unit) so as to input measuring range point test pressure (the maximum value of the measuring pressure of the transmitter) to the sensor, and then, a measuring signal output by the processing clamping piece is acquired and displayed, so that a worker can adjust the position of the measuring range point potentiometer to enable the value of the measuring signal to meet the zero point and the measuring range point requirement (the measuring signal is displayed as 20 mA).
In an alternative embodiment, step S20 further includes: and after the tested nuclear pressure transmitter is verified to be qualified, acquiring and recording an alternating current signal output by a sensor of the tested nuclear pressure transmitter when a test point is set, and taking the alternating current signal as a historical alternating current signal of a corresponding sensor. The set test point can be acquired through the signal processing unit, and specifically comprises a zero alternating current signal and a range point alternating current signal which are respectively output when the sensor performs zero point correction and range point correction, and a plurality of alternating current signal values which are correspondingly output when the sensor test pressure is a test pressure value in a linear test (corresponding to each test pressure value one by one). The purpose of recording the set test points is to prepare for card verification. In addition, a database for storing historical alternating current signals of the respective sensors may also be established.
In a specific embodiment, step S10 further includes: if the verification item is card verification, generating a second flow direction control signal for controlling the disconnection and interaction of the sensor and the processing card;
in S20, verifying the measured nuclear level pressure transmitter from the measurement signal and the verification term further includes: the method comprises the steps of obtaining a historical alternating current signal of a sensor of a processing clamp to be replaced, inputting an analog alternating current signal for simulating the historical alternating current signal to the processing clamp, and further enabling the processing clamp to meet the replacement requirement of the processing clamp to be replaced by adjusting the position of a correction potentiometer in the processing clamp.
In this embodiment, first, a second flow direction control signal is generated (input to the signal management unit), so that the switch for controlling the on-off of the ac signal output end of the sensor and the ac signal input end of the processing card in the signal management unit is disconnected, and the ac signal input end of the processing card is prevented from being influenced by external equipment; and then, acquiring analog alternating current signals corresponding to the sensors, sequentially inputting the analog alternating current signals to the processing clamping piece, further carrying out potentiometer correction and linear test on the processing clamping piece, and judging whether the processing clamping piece meets the replacement requirement of the processing clamping piece to be replaced or not if the measurement signals output by the processing clamping piece are respectively in the error range of the measurement signals output when corresponding verification items are carried out before the processing clamping piece to be replaced is failed.
In an alternative embodiment, step S20 further includes: if the measured nuclear pressure transmitter meets the related requirements by adjusting the position of the correction potentiometer, the measured nuclear pressure transmitter is judged to be not in accordance with the requirements. The embodiment is mainly aimed at calibration items which need to be adjusted and calibrated to the potentiometer, such as potentiometer calibration and clamping piece calibration, and the implementation of the embodiment can facilitate the staff to calibrate the corresponding sensor and the processing clamping piece. It should be noted that, determining that the measured nuclear pressure transmitter does not meet the requirements does not mean that both the sensor and the processing clamp in the measured nuclear pressure transmitter are faulty, which may be caused by one of the faults, for example, in the clamp verification, the sensor in the measured nuclear pressure transmitter is actually normal, but the measured processing clamp cannot meet the replacement requirements of the processing clamp to be replaced, and therefore, the measured processing clamp is determined to be not meet the requirements.
In an alternative embodiment, step S10 further includes: if the check item is a linear test, generating a first flow direction control signal for controlling interaction of the sensor and the processing card, and sequentially generating a corresponding second pressure supply control signal according to a preset test point list; the preset test point list comprises a plurality of test voltage supply values and measurement reference values corresponding to each test voltage supply value; each test voltage supply value is used for setting the value of the second voltage supply control signal;
in step S20, verifying the nuclear pressure transmitter under test based on the measurement signal and the verification term further includes: and comparing the obtained measurement signal with a corresponding measurement reference value after outputting the second pressure-supply control signal each time so as to judge whether the tested nuclear pressure transmitter meets the linearity requirement.
In this embodiment, first, a first flow direction control signal (input to the signal management unit) is generated, so that a switch for controlling on-off of an ac signal output end of the sensor and an ac signal input end of the processing card in the signal management unit is closed; then, sequentially acquiring test pressure-giving values in a preset test point list, so as to generate corresponding second pressure-giving control signals (input to a pressure-giving unit) according to the test pressure-giving values, and inputting corresponding linear test point pressures to the sensor, so that measuring signals respectively output by the processing clamping pieces when the sensor inputs each test pressure-giving value can be acquired; and comparing the measurement signals with corresponding measurement reference values in a preset test point list, and if the linearity of the measurement signals accords with an error range, judging that the measured nuclear pressure transmitter accords with the linearity requirement.
As shown in fig. 2, the present invention further provides an offline verification system for a nuclear power plant transmitter, which is suitable for a nuclear pressure transmitter, and the nuclear pressure transmitter includes a sensor 8 and a processing card 9, and the system includes:
the pressure supply unit 1 is used for inputting a test pressure to the sensor 8 according to a pressure supply control signal during verification;
the signal measuring unit 2 is used for collecting and processing the measuring signal output by the clamping piece 9;
a signal management unit 3 for controlling the signal flow direction between the sensor 8 and the processing card 9 according to the flow direction control signal at the time of verification; and
and the main control unit 4 is used for generating a pressure-supply control signal and a flow direction control signal according to the verification item, and verifying the tested nuclear pressure transmitter according to the acquired measurement signal and the verification item during verification.
In an alternative embodiment, the signal measuring unit 2 is also used for acquiring an ac signal output by the sensor 8. Further, in one embodiment, as shown in FIG. 3, the nuclear power plant transmitter offline verification system further includes a signal simulation unit 5 and a database 6. The signal simulation unit 5 is connected to the signal management unit 3, and is used for simulating the output signal of the sensor 8. The database 6 is used for storing the alternating current signals collected when the conventional verification sensor 8 is qualified. Correspondingly, the main control unit 4 also acquires a historical alternating current signal of the sensor 8 of the processing card to be replaced through the database 6, and controls the signal simulation unit 5 to output a simulation alternating current signal to the sensor 8 of the processing card to be replaced according to the historical alternating current signal so as to perform card verification.
In an alternative embodiment, as shown in fig. 3, the signal management unit 3 comprises: a sensor interface 31, a switch 32, a clamp interface 33, a measurement unit interface 34 and an analog unit interface 35.
Specifically, the first, second and third ends of the sensor interface 31 are sequentially connected with the first excitation signal input end, the alternating current signal output end and the second excitation signal input end of the sensor 8, the second end of the sensor interface 31 is also connected with the input end of the switch 32, the output end of the switch 32 is connected with the second end of the clamping piece interface 33, and the first and third ends of the sensor interface 31 are also connected with the first end and the third end of the clamping piece interface 33; the control end of the switch 32 is connected with the main control unit 4 (not shown) to control the on-off of the switch 32 according to the flow direction control signal; the first, second, third, fourth and fifth ends of the clamp interface 33 are sequentially connected with the first excitation signal output end, the alternating current signal input end, the second excitation signal output end, the first measurement signal output end and the second measurement signal output end of the processing clamp 9, and the second, fourth and fifth ends of the clamp interface 33 are further connected with the first, third and fourth ends of the measurement unit interface 34; the first and second ends of the measurement unit interface 34 are connected with the first measurement port of the signal measurement unit 2, the second end of the measurement unit interface 34 is grounded, and the third and fourth ends of the measurement unit interface 34 are connected with the second measurement port of the signal measurement unit 2; the first end of the analog unit interface 35 is connected to the second end of the card interface 33, the second end of the analog unit interface 35 is grounded, and the first and second ends of the analog unit interface 35 are also connected to the signal analog unit 5.
Specifically, the first measurement port of the signal measurement unit 2 is used for collecting the alternating current signal output by the sensor, and the second measurement port of the signal measurement unit 2 is used for collecting the measurement signal output by the processing clamp.
In an alternative embodiment, as shown in fig. 3, the signal management unit 3 further comprises a power supply unit 7 for supplying power to the processing card 9. The input end of the power supply unit 7 is connected with the mains supply, and the output end of the power supply unit 7 is connected with the power supply end of the clamping piece interface 33.
In the present specification, each embodiment is described in a progressive manner, and each embodiment is mainly described in a different point from other embodiments, and identical and similar parts between the embodiments are all enough to refer to each other. For the device disclosed in the embodiment, since it corresponds to the method disclosed in the embodiment, the description is relatively simple, and the relevant points refer to the description of the method section.
Those of skill would further appreciate that the various illustrative elements and algorithm steps described in connection with the embodiments disclosed herein may be implemented as electronic hardware, computer software, or combinations of both, and that the various illustrative elements and steps are described above generally in terms of functionality in order to clearly illustrate the interchangeability of hardware and software. Whether such functionality is implemented as hardware or software depends upon the particular application and design constraints imposed on the solution. 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 invention.
The steps of a method or algorithm described in connection with the embodiments disclosed herein may be embodied directly in hardware, in a software module executed by a processor, or in a combination of the two. The software modules may be disposed in Random Access Memory (RAM), memory, read Only Memory (ROM), electrically programmable ROM, electrically erasable programmable ROM, registers, hard disk, a removable disk, a CD-ROM, or any other form of storage medium known in the art.
It is to be understood that the above examples only represent preferred embodiments of the present invention, which are described in more detail and are not to be construed as limiting the scope of the invention; it should be noted that, for a person skilled in the art, the above technical features can be freely combined, and several variations and modifications can be made without departing from the scope of the invention; therefore, all changes and modifications that come within the meaning and range of equivalency of the claims are to be embraced within their scope.

Claims (10)

1. The utility model provides a nuclear power plant's changer off-line verification method, is applicable to nuclear level pressure transmitter, nuclear level pressure transmitter includes sensor and processing fastener, and its characterized in that, this method includes following steps:
s10, generating a flow direction control signal for controlling the flow direction of signals between the sensor and the processing clamping piece during verification according to the verification item, and a pressure supply control signal for controlling the magnitude of test pressure input to the sensor during verification;
and S20, during verification, acquiring a measurement signal output by the processing clamping piece, and verifying the tested nuclear pressure transmitter according to the measurement signal and a verification item.
2. The nuclear power plant transmitter offline verification method of claim 1, wherein the verification items include at least one of potentiometer calibration, linearity testing, and clamp verification.
3. The nuclear power plant transmitter offline verification method of claim 2, wherein S10 comprises: if the verification item is corrected by the potentiometer, generating a first flow direction control signal for controlling interaction of the sensor and the processing clamp, and generating a first pressure-supply control signal according to a set correction requirement; wherein the potentiometer correction comprises zero point correction and measuring range point correction;
in S20, verifying the measured nuclear level pressure transmitter based on the measurement signal and the verification term includes: the position of the correction potentiometer in the processing clamping piece is adjusted so that the measured nuclear pressure transmitter meets the requirements of zero and measuring range points; the correction potentiometer comprises a zero potentiometer and a measuring range point potentiometer.
4. The nuclear power plant transmitter offline verification method of claim 2, wherein S20 further comprises: after the tested nuclear pressure transmitter is verified to be qualified, acquiring and recording an alternating current signal output by a sensor of the tested nuclear pressure transmitter when a test point is set, and taking the alternating current signal as a historical alternating current signal of a corresponding sensor;
the S10 further includes: if the verification item is the card verification, generating a second flow direction control signal for controlling the disconnection interaction of the sensor and the processing card;
in S20, verifying the measured nuclear level pressure transmitter according to the measurement signal and the verification item further includes: the method comprises the steps of obtaining a historical alternating current signal of a sensor of a processing clamp to be replaced, inputting an analog alternating current signal for simulating the historical alternating current signal into the processing clamp, and further enabling the processing clamp to meet the replacement requirement of the processing clamp to be replaced by adjusting the position of a correction potentiometer in the processing clamp.
5. The nuclear power plant transmitter offline verification method according to claim 3 or 4, wherein S20 further comprises:
if the position of the correction potentiometer cannot be adjusted to enable the measured nuclear pressure transmitter to meet the related requirements, judging that the measured nuclear pressure transmitter does not meet the requirements.
6. The nuclear power plant transmitter offline verification method according to claim 2 or 3, wherein S10 further comprises: if the verification item is the linear test, generating the first flow direction control signal, and sequentially generating a corresponding second pressure supply control signal according to a preset test point list; the preset test point list comprises a plurality of test voltage supply values and measurement reference values corresponding to each test voltage supply value; each of the test voltage supply values is used for setting a value of the second voltage supply control signal;
in S20, verifying the measured nuclear level pressure transmitter according to the measurement signal and the verification item further includes: and comparing the obtained measurement signal with the corresponding measurement reference value after outputting the second pressure-supplying control signal each time so as to judge whether the tested nuclear pressure transmitter meets the linearity requirement.
7. The method for offline verification of a nuclear power plant transmitter according to claim 6, further comprising, in S10:
and controlling the signal flow direction between the sensor and the processing clamping piece through a preset signal management unit, inputting the test pressure to the sensor through a pressure supply unit, and collecting the measurement signal output by the processing clamping piece through a signal measurement unit.
8. An off-line verification system for a nuclear power plant transmitter, which is applicable to a nuclear pressure transmitter, wherein the nuclear pressure transmitter comprises a sensor (8) and a processing clamp (9), and is characterized in that the system comprises:
the pressure supply unit (1) is used for inputting a test pressure to the sensor (8) according to a pressure supply control signal during verification;
the signal measuring unit (2) is used for collecting the measuring signal output by the processing clamping piece (9);
the signal management unit (3) is used for controlling the signal flow direction between the sensor (8) and the processing clamping piece (9) according to the flow direction control signal during verification; and
and the main control unit (4) is used for generating the pressure-supply control signal and the flow direction control signal according to the verification item, and verifying the tested nuclear pressure transmitter according to the acquired measurement signal and the verification item during verification.
9. The nuclear power plant transmitter offline verification system according to claim 8, characterized in that said signal measurement unit (2) is further configured to collect an ac signal output by said sensor (8);
the offline verification system of the nuclear power plant transmitter further comprises a signal simulation unit (5) and a database (6);
the signal simulation unit (5) is connected with the signal management unit (3) and is used for simulating the output signal of the sensor (8);
the database (6) is used for storing the alternating current signals collected when the sensor (8) is checked to be qualified in the past;
the main control unit (4) also obtains a historical alternating current signal of the sensor (8) of the card to be replaced through the database (6), and controls the signal simulation unit (5) to output a simulation alternating current signal to the sensor (8) of the card to be replaced according to the historical alternating current signal so as to perform card verification.
10. The nuclear power plant transmitter offline verification system according to claim 8, characterized in that the signal management unit (3) comprises: a sensor interface (31), a change-over switch (32), a clamping piece interface (33), a measuring unit interface (34) and an analog unit interface (35);
the first, second and third ends of the sensor interface (31) are sequentially connected with the first excitation signal input end, the alternating current signal output end and the second excitation signal input end of the sensor (8), the second end of the sensor interface (31) is also connected with the input end of the change-over switch (32), the output end of the change-over switch (32) is connected with the second end of the clamping piece interface (33), and the first end and the third end of the sensor interface (31) are also connected with the first end and the third end of the clamping piece interface (33);
the control end of the change-over switch (32) is connected with the main control unit (4) so as to control the on-off of the change-over switch (32) according to the flow direction control signal;
the first, second, third, fourth and fifth ends of the clamping piece interface (33) are sequentially connected with the first excitation signal output end, the alternating current signal input end, the second excitation signal output end, the first measurement signal output end and the second measurement signal output end of the processing clamping piece (9), and the second, fourth and fifth ends of the clamping piece interface (33) are also connected with the first, third and fourth ends of the measurement unit interface (34);
the first and second ends of the measuring unit interface (34) are connected with the first measuring port of the signal measuring unit (2), the second end of the measuring unit interface (34) is grounded, and the third and fourth ends of the measuring unit interface (34) are connected with the second measuring port of the signal measuring unit (2);
the first end of the analog unit interface (35) is connected with the second end of the clamping piece interface (33), the second end of the analog unit interface (35) is grounded, and the first end and the second end of the analog unit interface (35) are also connected with the signal analog unit (5).
CN202310602382.4A 2023-05-25 2023-05-25 Offline verification method and system for nuclear power plant transmitter Pending CN116773083A (en)

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CN202310602382.4A CN116773083A (en) 2023-05-25 2023-05-25 Offline verification method and system for nuclear power plant transmitter

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Application Number Priority Date Filing Date Title
CN202310602382.4A CN116773083A (en) 2023-05-25 2023-05-25 Offline verification method and system for nuclear power plant transmitter

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CN116773083A true CN116773083A (en) 2023-09-19

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