CN114864124A - Measurement system, method and medium for nuclear safety level pressure transmitter identification test - Google Patents
Measurement system, method and medium for nuclear safety level pressure transmitter identification test Download PDFInfo
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Abstract
The invention discloses a measuring system, a measuring method, a measuring medium and an electronic device for an identification test of a nuclear safety level pressure transmitter, which comprise a signal acquisition module, a pressure source, a control system and a working power supply, wherein the signal acquisition module is used for acquiring output signals of a plurality of nuclear safety level pressure transmitters, the output end of the pressure source is communicated with the pressure input ends of the plurality of nuclear safety level pressure transmitters, the signal end of the control system is electrically connected with the signal output end of a signal acquisition device and the signal input end of the pressure source, and the working power supply is electrically connected with the pressure source, the control system and the nuclear safety level pressure transmitter and supplies power for the nuclear safety level pressure transmitter; the invention controls the pressure source to output pressure to the plurality of nuclear safety level pressure transmitters through the control system, then acquires the output conditions of the plurality of nuclear safety level pressure transmitters through the signal acquisition module, and then realizes the measurement of state detection, basic deviation measurement and response time measurement of the nuclear safety level pressure transmitters by adopting a measurement method of a nuclear safety level pressure transmitter identification test.
Description
Technical Field
The invention relates to the field of nuclear industry, in particular to a measuring system, a method and a medium for a nuclear safety level pressure transmitter identification test.
Background
The nuclear safety level pressure transmitter is used for measuring thermal parameters such as pressure, liquid level and flow of the nuclear power station during normal operation, and particularly can provide important thermal parameters for a nuclear power station protection system and a post-accident monitoring system under and after an accident condition, and has very important effect on safe and reliable operation of the nuclear power station as the safety protection strategy under the accident condition can be realized.
The identification test of the nuclear safety level pressure transmitter comprises four types of tests, namely a benchmark test, a limit parameter test, a durability test, an accident and a post-accident performance test.
The basic deviation and response time measurement is included in the benchmark test, and at least three nuclear safety level pressure transmitters with the same model and specification are required to be used as a prototype for testing.
Basic deviations of the output results of the nuclear safety level pressure transmitter need to be monitored continuously during the endurance test, the accident and the post-accident performance test, and the basic deviations and the response time generally need to be measured after the tests are finished.
At present, the measurement of basic deviation and response time can be realized by simultaneously carrying out the simultaneous operation of a plurality of nuclear safety level pressure transmitters, but the output of the transmitters is read out through a plurality of ammeters, the measurement results of the basic deviation and the response time are obtained by analyzing and calculating after data is arranged by measurement personnel, the measurement efficiency is low, and the automation degree is low.
In the process of durability test, accident and post-accident performance test, a fixed time point is selected, the output result of the nuclear safety pressure transmitter is obtained by measuring the voltage values of the standard resistors connected in series in the loop one by one, and continuous monitoring is not realized.
Disclosure of Invention
The invention aims to solve the technical problems that in the identification test of the nuclear safety level pressure transmitter at the present stage, the acquisition efficiency of basic deviation and response time is low, continuous monitoring cannot be realized, and measurement personnel need to perform manual calculation.
The invention is realized by the following technical scheme:
a measurement system for a nuclear safety level pressure transmitter qualification test, comprising:
the signal acquisition module is used for acquiring output signals of the nuclear safety level pressure transmitters;
a pressure source having an output in communication with pressure inputs of the plurality of nuclear safety level pressure transmitters;
the signal end of the control system is electrically connected with the signal output end of the signal collector and the signal input end of the pressure source;
a working power supply electrically connected with the pressure source, the control system and the nuclear safety level pressure transmitter.
Specifically, the signal acquisition module includes:
the sampling resistors are respectively connected in series on a plurality of nuclear safety level pressure transmitters and a power supply loop of the working power supply;
the signal selection circuit is used for sequentially conducting a plurality of input ports with an output port at certain time intervals, and a plurality of input ends of the signal selection circuit are respectively and electrically connected with the non-grounding ends of the plurality of sampling resistors;
the input end of the FPGA is electrically connected with the output end of the signal selection circuit through a digital-to-analog conversion circuit, the output end of the FPGA is electrically connected with the input end of the control system, and the control end of the FPGA is electrically connected with the signal selection circuit and the control end of the digital-to-analog conversion circuit.
A method of measuring a nuclear safety level pressure transmitter qualification test for continuous monitoring of conditions during the nuclear safety level pressure transmitter test, the method being based on a measurement system of the nuclear safety level pressure transmitter qualification test described above, the method comprising:
a1, setting state continuous monitoring parameters including pressure source output pressure and deviation alarm threshold;
a2, sending a pressure source output pressure value to the pressure source by the control system, and waiting for the pressure source to return to an output state;
a3, after receiving the output state returned by the pressure source, controlling a signal acquisition module to sequentially read the output signals of a plurality of nuclear safety level pressure transmitters;
a4, calculating an output deviation according to the output signal of the nuclear safety level pressure transmitter and the output pressure of the pressure source;
and A5, comparing the output deviation with a deviation alarm threshold value, and outputting an alarm signal if the output deviation reaches the alarm threshold value.
A method of measuring a nuclear safety level pressure transmitter qualification test for basic deviation measurement during the nuclear safety level pressure transmitter test, the method being based on a measurement system of the nuclear safety level pressure transmitter qualification test described above, the method comprising:
b1, setting basic deviation measurement parameters including test points and cycle times, wherein the test points are a plurality of pressure values within the range of the nuclear safety level pressure transmitter;
b2, the control system sends one of the test points to the pressure source and waits for the pressure source to return to an output state;
b3, after receiving the output state returned by the pressure source, controlling the signal acquisition module to sequentially read the output signals of the plurality of nuclear safety level pressure transmitters, and then circularly reading for a plurality of times according to the set cycle times;
b4, obtaining the measured deviation of the test point;
b5, obtaining the measured deviations of the other test points according to the steps B2-B4 in sequence;
and B6, obtaining basic deviation, return difference, end group consistency deviation and repeatability deviation according to the measured deviation of a plurality of test points.
Preferably, the pressure values of the test points comprise a minimum pressure value, a maximum pressure value and a plurality of sequentially increased pressure values of the range of the nuclear safety level pressure transmitter, and the pressure value difference of two adjacent test points is equal;
step B5 includes two measurement strokes, the first measurement stroke is an up stroke in which the pressure values are sequentially increased, and the second measurement stroke is a down stroke in which the pressure values are sequentially decreased.
Specifically, the calculation formula of the measured deviation is as follows:
δ i ＝(I i -I 0 )/I w ×100％
in the formula, delta i -the deviation is measured at the ith cycle of a test point and a trip;
I i -the test point output current for the ith time;
I 0 -the test point standard output current;
I w the output range is the difference between the upper and lower limits of the output current.
Specifically, the base deviation is the maximum deviation of any measured deviation from the ideal deviation when the input pressure value is increased or decreased in any one cycle reading;
the return difference is the maximum deviation of the adjacent up stroke output and down stroke output in any cycle on the same test point;
the end group consistency deviation is the maximum deviation of the measured deviation curve and the end group straight line;
the repeatability deviation delta R The calculation formula of (2) is as follows:
wherein i is the cycle number set in the step B1;
δ 1 ，δ 2 ......δ i -the deviation is measured from the ith cycle of the same stroke.
A method of measuring a nuclear safety level pressure transmitter qualification test for response time measurement during the nuclear safety level pressure transmitter test, the method being based on a measurement system of the nuclear safety level pressure transmitter qualification test described above, the method comprising:
c1, setting response time parameters including the measuring range and the response time percentage of the nuclear safety level pressure transmitter;
c2, the control system sends the pressure value of the maximum range of the nuclear safety level pressure transmitter to the pressure source and waits for the pressure source to return to an output state;
c3, after receiving the output state returned by the pressure source, the control system sends a pressure relief instruction to the pressure source and starts timing;
c4, the control signal acquisition module reads the output signals of the nuclear safety level pressure transmitters in sequence;
c5, after the output signals of the plurality of nuclear safety level pressure transmitters return to zero, ending timing;
c6, obtaining the response time, wherein the response time is the time required for the output signal to drop from 100% to the set response time percentage.
A computer-readable storage medium, in which a computer program is stored which, when being executed by a processor, carries out the steps of a method of measurement of a nuclear safety class pressure transmitter qualification test as described above.
An electronic device, comprising: at least one processor; and the number of the first and second groups,
a memory communicatively coupled to the at least one processor; wherein the content of the first and second substances,
the memory stores instructions executable by the at least one processor to cause the at least one processor to implement the steps of a method of measurement for a nuclear safety class pressure transmitter qualification test as described above.
Compared with the prior art, the invention has the following advantages and beneficial effects:
the invention realizes the basic setting for the state detection, the basic deviation measurement and the response time measurement of the nuclear safety level pressure transmitter by arranging a measuring system, controlling the pressure source to output pressure to the plurality of nuclear safety level pressure transmitters through the control system and then acquiring the output conditions of the plurality of nuclear safety level pressure transmitters through the signal acquisition module;
and then, the real-time state detection, the basic deviation measurement and the influence time measurement of a plurality of nuclear safety level pressure transmitters in the identification test are realized by adopting the measurement method of the nuclear safety level pressure transmitter identification test.
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The accompanying drawings, which are included to provide a further understanding of the invention and are incorporated in and constitute a part of this specification, illustrate exemplary embodiments of the invention and together with the description serve to explain the principles of the invention.
FIG. 1 is a block diagram of a measurement system for a nuclear safety level pressure transmitter qualification test according to the present invention.
Fig. 2 is a block diagram of the control system, the signal acquisition platform and the working power supply according to the present invention.
FIG. 3 is a flow chart of a measurement method of a nuclear safety level pressure transmitter qualification test according to the present invention.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention will be further described in detail with reference to the accompanying drawings and embodiments. It is to be understood that the specific embodiments described herein are for purposes of illustration only and are not to be construed as limitations of the invention.
It should be noted that, for convenience of description, only the portions related to the present invention are shown in the drawings.
In the present invention, the embodiments and features of the embodiments may be combined with each other without conflict. The present invention will be described in detail below with reference to the accompanying drawings in conjunction with embodiments.
Example one
The embodiment provides a measuring system for a nuclear safety level pressure transmitter identification test, which mainly has the following functions;
and continuously monitoring the state of the pressure transmitter during the test of the plurality of nuclear safety level pressure transmitters. The system can provide power for a plurality of nuclear-grade nuclear safety-grade pressure transmitters, continuously monitor output values of the plurality of nuclear-grade nuclear safety-grade pressure transmitters, and give out an out-of-tolerance alarm in real time according to the output values.
And measuring basic deviation of a plurality of nuclear safety level pressure transmitters. The method can provide power for a plurality of nuclear safety level pressure transmitters, can simultaneously measure the output of the plurality of nuclear safety level pressure transmitters, measures according to the measurement process of basic deviation, and calculates the measurement results of the basic deviation, the return difference, the repeatability deviation, the end group consistency deviation and the like.
And measuring the response time of the plurality of nuclear safety level pressure transmitters. The system can provide power for a plurality of nuclear safety level pressure transmitters, output control signals of the pressure source, control the pressure source to change rapidly, measure the output of the plurality of nuclear safety level pressure transmitters simultaneously, and analyze and calculate the response time of the plurality of nuclear safety level pressure transmitters.
A measuring system for a nuclear safety level pressure transmitter identification test comprises a signal acquisition module, a pressure source, a control system and a working power supply.
The signal acquisition module is used for acquiring output signals of the nuclear safety level pressure transmitters, the output end of the pressure source is communicated with the pressure input ends of the nuclear safety level pressure transmitters, the signal end of the control system is electrically connected with the signal output end of the signal acquisition device and the signal input end of the pressure source, and the working power supply is electrically connected with the pressure source, the control system and the nuclear safety level pressure transmitters and supplies power to the nuclear safety level pressure transmitters.
In practical cases, the number of nuclear safety level pressure transmitters is plural, but in this embodiment and all the embodiments described below, the number of nuclear safety level pressure transmitters is 3 as an example, and the related description is made, as shown in fig. 1 and fig. 2.
The measuring loop formed by the measuring system consists of a pressure source, a four-way joint, a control system, a signal acquisition module, a working power supply and a nuclear-grade nuclear safety-grade pressure transmitter, wherein the output of the pressure source is controlled by an operating system of the pressure source or an RS232 interface of the control system, the output of the pressure source is connected to the four-way joint through a pipeline, the four-way joint outputs in three ways and respectively outputs to the input of the three nuclear-grade nuclear safety-grade pressure transmitters through pipelines.
The control system outputs a 24VDC power supply, the three nuclear-grade nuclear safety-grade pressure transmitters are connected in parallel to the power supply output by the control system to form three power supply loops, the three power supply loops are also loops output by the nuclear-grade nuclear safety-grade pressure transmitters, the signal acquisition module respectively measures output currents of the three loops, the output state of the nuclear-grade nuclear safety-grade pressure transmitter is monitored in real time, and reference parameters of the nuclear-grade nuclear safety-grade pressure transmitter are measured.
The connection structure of the control system, the signal acquisition module and the working power supply is shown in fig. 2.
The working power supply converts a 220VAC power supply into three groups of power outputs of 5VDC, 12VDC and 24VDC, and respectively provides a 5VD working power supply for a control system (an embedded computer is adopted in the embodiment) and a signal acquisition module, a 12VDC working power supply for a touch screen and a 24VDC working power supply for a nuclear-grade nuclear safety-grade pressure transmitter.
The embedded computer is communicated with the signal acquisition module through a PC104 bus interface, and controls the signal acquisition module to acquire signals and read data acquired by the signal acquisition module.
The embedded computer communicates with the touch screen through an RS232 interface, and sends the measurement result required to be displayed by the touch screen and received operation control. The embedded computer communicates with an external pressure source through another RS232 interface, and sends a signal for controlling the output of the pressure source and receives an output state signal of the pressure source.
In practical use, the signal acquisition module is used as an embedded computer function extension and consists of the following parts: the circuit comprises a programmable logic array (FPGA), a signal sampling circuit, a signal selection circuit and an analog-to-digital conversion (ADC) circuit.
The signal sampling circuit comprises a plurality of sampling resistors which are respectively connected in series on a plurality of nuclear safety level pressure transmitters and a power supply loop of a working power supply;
the signal sampling circuit is characterized in that a high-precision sampling resistor is connected in series in an output loop of each nuclear-grade nuclear safety-grade pressure transmitter. The nuclear safety level pressure transmitter comprises three nuclear safety level pressure transmitters, therefore, 250 omega +/-0.01% high-precision sampling resistors are respectively connected in series on output loops of the three nuclear safety level pressure transmitters, one ends of the three sampling resistors are connected to a 24VDC ground, the nuclear safety level pressure transmitter outputs 4-20 mA signals to generate 1-5V voltages on the three sampling resistors, and the other ends of the three sampling resistors are used as output signals to be connected to input ends of a signal selection circuit.
The signal selection circuit is used for sequentially conducting the input ports with the output port according to a certain time interval, and the input ends of the signal selection circuit are respectively and electrically connected with the non-grounding ends of the sampling resistors;
the signal selection circuit is composed of a multi-channel analog switch, and the analog switch comprises a plurality of input ports, an output port and a control interface. The three paths of output of the signal sampling circuit are connected with the input ports of the signal analog switches, the control output port of the FPGA is connected with the control ports of the analog switches, the FPGA module outputs the control logic time sequence of the analog switches, and the analog switches are controlled to conduct the input ports of the analog switches with the output ports in sequence according to a certain time interval, so that the multiple paths of input signals are output one by one in sequence.
The input end of the FPGA is electrically connected with the output end of the signal selection circuit through the digital-to-analog conversion circuit, the output end of the FPGA is electrically connected with the input end of the control system, and the control end of the FPGA is electrically connected with the signal selection circuit and the control end of the digital-to-analog conversion circuit.
The FPGA mainly realizes the logic control function of the signal selection circuit and the analog-to-digital conversion circuit, an FPGA chip of the cycle I series of Altera company is adopted as a core processor, and the peripheral circuit of the FPGA further comprises: serial configurators, external clocks, power and download interfaces, etc. The FPGA is compatible with the 5V TTL level of the PC104 bus, the FPGA pin is directly configured into the PC104 bus pin, and the PC104 bus working time sequence module is integrated in the FPGA to realize the communication with the embedded computer. In addition, the FPGA is also provided with pins for controlling the AD conversion chip, inputting data of the AD conversion chip and controlling a multi-channel analog switch, and a working time sequence module for controlling AD and a working time sequence module for selecting signals are integrated in the FPGA.
The digital-to-analog conversion circuit carries out analog-to-digital conversion on voltage signals output and sampled by the three nuclear-grade nuclear safety-grade pressure transmitters to serial digital signals, and the serial digital signals enter the FPGA module to be stored and read by the embedded computer. The circuit adopts a 16-bit AD conversion chip, the conversion frequency of the circuit can reach 100kbps, an output port of the signal selection circuit is connected with an input port of the AD conversion chip, an AD control output port of the FPGA module is connected to a control port of the AD conversion chip, and a serial signal input port of the FPGA module is connected with a serial signal output port of the AD conversion chip.
Example two
The present embodiment provides a measurement method for a nuclear safety level pressure transmitter qualification test for continuous monitoring of conditions during the nuclear safety level pressure transmitter test, as shown on the left side of fig. 3, the method is based on a measurement system for the nuclear safety level pressure transmitter qualification test in the first embodiment, the method includes:
a1, setting state continuous monitoring parameters including pressure source output pressure and deviation alarm threshold;
the parameters of the control system are set through a touch screen, a prototype is set to be a gauge type in the embodiment, the measuring range is 0-2 MPa, the deviation alarm threshold is +/-0.65% FS, the number of monitoring channels is 3 (namely 3 nuclear safety level pressure transmitters are detected), the pressure source output is 1.9MPa and the like, and the parameters are written into an embedded computer through an RS232 interface;
a2, sending a pressure source output pressure value to the pressure source by the control system, and waiting for the pressure source to return to an output state; for determining that the pressure source has been put into operation.
A3, after receiving the output state returned by the pressure source, controlling a signal acquisition module to sequentially read the output signals of a plurality of nuclear safety level pressure transmitters; in this embodiment, the data of the channels 1-3 are sequentially read.
A4, calculating the output deviation according to the output signal of the nuclear safety level pressure transmitter and the output pressure of the pressure source, wherein the calculation method of the output deviation is (output signal-pressure source output pressure)/pressure source output pressure multiplied by 100%.
And A5, comparing the output deviation with a deviation alarm threshold value, outputting an alarm signal if the output deviation reaches the alarm threshold value, and continuously detecting if the output deviation does not reach the alarm threshold value, thereby realizing the continuous monitoring of the state.
EXAMPLE III
The present embodiment provides a method for measuring a nuclear safety level pressure transmitter qualification test for basic deviation measurement during a nuclear safety level pressure transmitter test, as shown in fig. 3, the method is based on a measurement system of the nuclear safety level pressure transmitter qualification test in the first embodiment, the method includes:
b1, setting basic deviation measurement parameters including test points and cycle times, wherein the test points are a plurality of pressure values within the range of the nuclear safety level pressure transmitter;
the pressure values of the test points comprise a minimum pressure value, a maximum pressure value and a plurality of sequentially increased pressure values of the range of the nuclear safety level pressure transmitter, and the pressure value difference of two adjacent test points is equal;
through the input of a touch screen, a prototype is set to be of a gauge type in the embodiment, the measuring range is 0-2 MPa, the test points are respectively 0MPa, 0.4MPa, 0.8MPa, 1.2MPa, 1.8MPa and 2MPa, the cycle number is 3 times, the number of measurement channels is 3, and the parameters are written into an embedded computer through an RS232 interface.
B2, the control system sends one of the test points (in the embodiment, the first test point is selected to be 0MPa) to the pressure source, waits for the pressure source to return to the output state, and determines that the pressure source starts to work.
B3, after receiving the output state returned by the pressure source, controlling the signal acquisition module to sequentially read the output signals of the plurality of nuclear safety level pressure transmitters, and then circularly reading for 3 times according to the set cycle times;
b4, obtaining the measured deviation of the test point;
the measured deviation is calculated as:
δ i ＝(I i -I 0 )/I w ×100％
in the formula, delta i -the deviation is measured at the ith cycle of a test point and a trip; in the embodiment, i is 1, 2 and 3;
I i -the test point output current for the ith time;
I 0 -the test point standard output current;
I w the output range is the difference between the upper and lower limits of the output current.
B5, obtaining the measured deviations of the other test points according to the steps B2-B4 in sequence;
in this embodiment, two measurement strokes are included, the first measurement stroke is an upper stroke (0MPa, 0.4MPa, 0.8MPa, 1.2MPa, 1.8MPa, 2MPa) in which the pressure values are sequentially increased, and the second measurement stroke is a lower stroke (2MPa, 1.8MPa, 1.2MPa, 0.8MPa, 0.4MPa, 0MPa) in which the pressure values are sequentially decreased.
And B6, obtaining basic deviation, return difference, end group consistency deviation and repeatability deviation according to the measured deviation of the plurality of test points, and displaying the basic deviation, the return difference, the end group consistency deviation and the repeatability deviation through a touch screen.
The base deviation is the maximum deviation of any measured deviation from the ideal deviation when the input pressure value is increased or decreased in any cycle (i.e., the ith cycle) reading;
the return difference is the maximum deviation of the adjacent up stroke output and down stroke output in any cycle (i.e. the ith cycle) on the same test point;
the end group consistency deviation is the maximum deviation between the measured deviation curve and the end group straight line;
repeatability deviation delta R The calculation formula of (2) is as follows:
wherein i is the cycle number set in the step B1;
δ 1 ，δ 2 ......δ i -the deviation is measured from the ith cycle of the same stroke.
Example four
The present embodiment provides a method for measuring a nuclear safety class pressure transmitter qualification test for response time measurement during a nuclear safety class pressure transmitter test, as shown on the right side of fig. 3, the method being based on a measurement system of the nuclear safety class pressure transmitter qualification test in the first embodiment, the method comprising:
c1, setting response time parameters including the measuring range and the response time percentage of the nuclear safety level pressure transmitter;
in the embodiment, a prototype is set to be of a gauge type, the measuring range is 0-2 MPa, the response time percentage is 63.2%, the number of measuring channels is 3, and the parameters are written into an embedded computer through an RS232 interface.
C2, the control system sends the pressure value of the maximum range (2MPa) of the nuclear safety level pressure transmitter to the pressure source and waits for the pressure source to return to an output state; the pressure source is determined to be active.
C3, after receiving the output state returned by the pressure source, the control system sends a pressure relief instruction to the pressure source and starts timing;
c4, the control signal acquisition module reads the output signals of the nuclear safety level pressure transmitters in sequence;
and C5, after the output signals of the plurality of nuclear safety level pressure transmitters return to zero, ending timing, independently timing each nuclear safety level pressure transmitter, and recording the relation between the pressure value and the time.
C6, obtaining the response time, wherein the response time is the time required for the output signal to drop from 100% to the set response time percentage.
And drawing a curve of the output of the three channels along the time on an X axis and an output Y axis, and selecting the time required for the output to be reduced from 100% to 63.2% as response time.
EXAMPLE five
The present embodiment provides a computer readable storage medium storing a computer program which, when executed by a processor, implements the steps of a method of measurement for a nuclear safety class pressure transmitter qualification test as described above.
That is, as shown in fig. 3, in this embodiment, the methods in the second, third, and fourth embodiments may all be written in one computer program, and then different measurement methods in the second, third, and fourth embodiments may be implemented by selecting an operation mode.
Without loss of generality, computer readable media may comprise computer storage media and communication media. Computer storage media includes volatile and nonvolatile, removable and non-removable media implemented in any method or technology for storage of information such as computer readable instruction data structures, program modules or other data. Computer storage media includes RAM, ROM, EPROM, EEPROM, flash memory or other solid state storage technology, CD-ROM, DVD, or other optical storage, magnetic cassettes, magnetic tape, magnetic disk storage or other magnetic storage devices. Of course, those skilled in the art will appreciate that computer storage media is not limited to the foregoing. The system memory and mass storage devices described above may be collectively referred to as memory.
An electronic device, comprising: at least one processor; and (c) a second step of,
a memory communicatively coupled to the at least one processor; wherein the content of the first and second substances,
the memory stores instructions executable by the at least one processor to cause the at least one processor to perform the steps of a method of measurement for a nuclear safety class pressure transmitter qualification test as described above.
The memory may be used to store software programs and modules, and the processor may execute various functional applications of the terminal and data processing by operating the software programs and modules stored in the memory. The memory may mainly include a program storage area and a data storage area, wherein the program storage area may store an operating system, an execution program required for at least one function, and the like.
The storage data area may store data created according to the use of the terminal, and the like. Further, the memory may include high speed random access memory, and may also include non-volatile memory, such as at least one magnetic disk storage device, flash memory device, or other volatile solid state storage device.
In the description herein, reference to the description of the terms "one embodiment/mode," "some embodiments/modes," "example," "specific example," or "some examples," etc., means that a particular feature, structure, material, or characteristic described in connection with the embodiment/mode or example is included in at least one embodiment/mode or example of the application. In this specification, the schematic representations of the terms used above are not necessarily intended to be the same embodiment/mode or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments/modes or examples. Furthermore, the various embodiments/aspects or examples and features of the various embodiments/aspects or examples described in this specification can be combined and combined by one skilled in the art without conflicting therewith.
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 at least one such feature. In the description of the present application, "plurality" means at least two, e.g., two, three, etc., unless specifically limited otherwise.
It will be understood by those skilled in the art that the foregoing embodiments are merely for clarity of description and are not intended to limit the scope of the invention. It will be apparent to those skilled in the art that other variations or modifications may be made on the above invention and still be within the scope of the invention.
Claims (10)
1. A measurement system for a nuclear safety level pressure transmitter qualification test, comprising:
the signal acquisition module is used for acquiring output signals of the nuclear safety level pressure transmitters;
a pressure source having an output in communication with pressure inputs of the plurality of nuclear safety level pressure transmitters;
the signal end of the control system is electrically connected with the signal output end of the signal collector and the signal input end of the pressure source;
a working power supply electrically connected with the pressure source, the control system and the nuclear safety level pressure transmitter.
2. The system of claim 1, wherein the signal acquisition module comprises:
the sampling resistors are respectively connected in series on a plurality of nuclear safety level pressure transmitters and a power supply loop of the working power supply;
the signal selection circuit is used for sequentially conducting a plurality of input ports with an output port at certain time intervals, and a plurality of input ends of the signal selection circuit are respectively and electrically connected with the non-grounding ends of the plurality of sampling resistors;
the input end of the FPGA is electrically connected with the output end of the signal selection circuit through a digital-to-analog conversion circuit, the output end of the FPGA is electrically connected with the input end of the control system, and the control end of the FPGA is electrically connected with the signal selection circuit and the control end of the digital-to-analog conversion circuit.
3. A method of measurement for a nuclear safety level pressure transmitter qualification test, the method being based on a measurement system of a nuclear safety level pressure transmitter qualification test according to any of claims 1-2, the method comprising:
a1, setting state continuous monitoring parameters including pressure source output pressure and deviation alarm threshold;
a2, sending a pressure source output pressure value to the pressure source by the control system, and waiting for the pressure source to return to an output state;
a3, after receiving the output state returned by the pressure source, controlling a signal acquisition module to sequentially read the output signals of a plurality of nuclear safety level pressure transmitters;
a4, calculating an output deviation according to the output signal of the nuclear safety level pressure transmitter and the output pressure of the pressure source;
and A5, comparing the output deviation with a deviation alarm threshold value, and outputting an alarm signal if the output deviation reaches the alarm threshold value.
4. A method of measurement for nuclear safety level pressure transmitter qualification tests, for basic deviation measurement during the nuclear safety level pressure transmitter test, the method being based on a measurement system of a nuclear safety level pressure transmitter qualification test according to any of claims 1-2, the method comprising:
b1, setting basic deviation measurement parameters including test points and cycle times, wherein the test points are a plurality of pressure values within the range of the nuclear safety level pressure transmitter;
b2, the control system sends one of the test points to the pressure source and waits for the pressure source to return to an output state;
b3, after receiving the output state returned by the pressure source, controlling the signal acquisition module to sequentially read the output signals of the plurality of nuclear safety level pressure transmitters, and then circularly reading for a plurality of times according to the set cycle times;
b4, obtaining the measured deviation of the test point;
b5, obtaining the measured deviations of the other test points according to the steps B2-B4 in sequence;
and B6, obtaining basic deviation, return difference, end group consistency deviation and repeatability deviation according to the measured deviation of a plurality of test points.
5. The method of claim 4, wherein the pressure values at the test points comprise a minimum pressure value, a maximum pressure value and a plurality of sequentially increasing pressure values of the range of the nuclear safety pressure transmitter, and the pressure value difference between two adjacent test points is equal;
step B5 includes two measurement strokes, the first measurement stroke is an up stroke in which the pressure values are sequentially increased, and the second measurement stroke is a down stroke in which the pressure values are sequentially decreased.
6. The method of claim 5, wherein the measured deviation is calculated by the formula:
δ i ＝(I i -I 0 )/I w ×100％
in the formula, delta i -the deviation is measured at the ith cycle of a test point and a trip;
I i ——the ith output current of the test point;
I 0 -the test point standard output current;
I w the output range is the difference between the upper and lower limits of the output current.
7. The method of claim 6, wherein the base deviation is the maximum deviation of any measured deviation from the ideal deviation upon increasing or decreasing the input pressure value in any one of the cyclical readings;
the return difference is the maximum deviation of the adjacent up stroke output and down stroke output in any cycle on the same test point;
the end group consistency deviation is the maximum deviation of the measured deviation curve and the end group straight line;
the repeatability deviation delta R The calculation formula of (2) is as follows:
wherein i is the cycle number set in the step B1;
δ 1 ，δ 2 ......δ i -the deviation is measured from the ith cycle of the same stroke.
8. A method of measurement for a nuclear safety level pressure transmitter qualification test, for response time measurement during the nuclear safety level pressure transmitter test, the method being based on a measurement system of a nuclear safety level pressure transmitter qualification test according to any of claims 1-2, the method comprising:
c1, setting response time parameters including the measuring range and the response time percentage of the nuclear safety level pressure transmitter;
c2, the control system sends the pressure value of the maximum range of the nuclear safety level pressure transmitter to the pressure source and waits for the pressure source to return to an output state;
c3, after receiving the output state returned by the pressure source, the control system sends a pressure relief instruction to the pressure source and starts timing;
c4, the control signal acquisition module reads the output signals of the nuclear safety level pressure transmitters in sequence;
c5, after the output signals of the plurality of nuclear safety level pressure transmitters return to zero, ending timing;
c6, obtaining the response time, wherein the response time is the time required for the output signal to drop from 100% to the set response time percentage.
9. 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 3-8.
10. An electronic device, comprising: at least one processor; and the number of the first and second groups,
a memory communicatively coupled to the at least one processor; wherein the content of the first and second substances,
the memory stores instructions executable by the at least one processor to enable the at least one processor to implement the steps of the method of any one of claims 3-8.
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Citations (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1332545A (en) * | 1971-06-10 | 1973-10-03 | Vnii Komiteta Standartov Mer I | Apparatus for testing pneumatic pressure transmitters |
| JPH08178788A (en) * | 1994-12-21 | 1996-07-12 | Hitachi Ltd | Calibrator for pressure transmitter |
| RU2304762C1 (en) * | 2006-03-30 | 2007-08-20 | Государственное образовательное учреждение высшего профессионального образования "Южно-Уральский государственный университет" | Method and device for measuring pressure |
| WO2010015569A1 (en) * | 2008-08-07 | 2010-02-11 | Siemens Aktiengesellschaft | Pressure measurement converter and method for the operation thereof |
| US20100255796A1 (en) * | 2009-04-03 | 2010-10-07 | Koukol Jr John L | Self evaluating transmitter |
| RU2010103045A (en) * | 2007-06-30 | 2011-08-10 | Эндресс + Хаузер Флоутек Аг (Ch) | MEASURING SYSTEM FOR THE ENVIRONMENT FLOWING IN THE TECHNOLOGICAL PIPELINE |
| US20130080084A1 (en) * | 2011-09-28 | 2013-03-28 | John P. Miller | Pressure transmitter with diagnostics |
| US20130325369A1 (en) * | 2012-05-31 | 2013-12-05 | Brian Edward Sofen | Process variable transmitter system with analog communication |
| CN206019924U (en) * | 2016-08-29 | 2017-03-15 | 上海光华仪表有限公司 | A kind of test system that is debugged for multiple stage nuclear safe level pressure transmitter simultaneously |
| US20180335361A1 (en) * | 2017-05-17 | 2018-11-22 | Yokogawa Electric Corporation | Calibration work support device, calibration work support method, and non-transitory computer readable storage medium |
| CN111817538A (en) * | 2020-07-15 | 2020-10-23 | 中国核动力研究设计院 | Multi-channel power adapter of two-wire system connection charge converter and application method |
| CN212059232U (en) * | 2020-03-18 | 2020-12-01 | 华电莱州发电有限公司 | Intelligent pressure transmitter calibration system |
| CN112629575A (en) * | 2019-09-24 | 2021-04-09 | 罗斯蒙特公司 | Process variable sensor testing |
-
2022
- 2022-03-24 CN CN202210293404.9A patent/CN114864124A/en active Pending
Patent Citations (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1332545A (en) * | 1971-06-10 | 1973-10-03 | Vnii Komiteta Standartov Mer I | Apparatus for testing pneumatic pressure transmitters |
| JPH08178788A (en) * | 1994-12-21 | 1996-07-12 | Hitachi Ltd | Calibrator for pressure transmitter |
| RU2304762C1 (en) * | 2006-03-30 | 2007-08-20 | Государственное образовательное учреждение высшего профессионального образования "Южно-Уральский государственный университет" | Method and device for measuring pressure |
| RU2010103045A (en) * | 2007-06-30 | 2011-08-10 | Эндресс + Хаузер Флоутек Аг (Ch) | MEASURING SYSTEM FOR THE ENVIRONMENT FLOWING IN THE TECHNOLOGICAL PIPELINE |
| WO2010015569A1 (en) * | 2008-08-07 | 2010-02-11 | Siemens Aktiengesellschaft | Pressure measurement converter and method for the operation thereof |
| US20100255796A1 (en) * | 2009-04-03 | 2010-10-07 | Koukol Jr John L | Self evaluating transmitter |
| US20130080084A1 (en) * | 2011-09-28 | 2013-03-28 | John P. Miller | Pressure transmitter with diagnostics |
| CN103033309A (en) * | 2011-09-28 | 2013-04-10 | 罗斯蒙德公司 | Pressure transmitter with diagnostics |
| US20130325369A1 (en) * | 2012-05-31 | 2013-12-05 | Brian Edward Sofen | Process variable transmitter system with analog communication |
| CN206019924U (en) * | 2016-08-29 | 2017-03-15 | 上海光华仪表有限公司 | A kind of test system that is debugged for multiple stage nuclear safe level pressure transmitter simultaneously |
| US20180335361A1 (en) * | 2017-05-17 | 2018-11-22 | Yokogawa Electric Corporation | Calibration work support device, calibration work support method, and non-transitory computer readable storage medium |
| CN112629575A (en) * | 2019-09-24 | 2021-04-09 | 罗斯蒙特公司 | Process variable sensor testing |
| CN212059232U (en) * | 2020-03-18 | 2020-12-01 | 华电莱州发电有限公司 | Intelligent pressure transmitter calibration system |
| CN111817538A (en) * | 2020-07-15 | 2020-10-23 | 中国核动力研究设计院 | Multi-channel power adapter of two-wire system connection charge converter and application method |
Non-Patent Citations (2)
| Title |
|---|
| JIAOYAN WANG ET AL.: ""Investigate Calibration Methods for Pressure Transmitters"", 《JOURNAL OF PHYSICS: CONFERENCE SERIES》, 30 November 2020 (2020-11-30) * |
| 张艾森: ""智能压力变送器功能安全评估与测试"", 《中国优秀硕士学位论文全文数据库 信息科技》, 15 October 2013 (2013-10-15) * |
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