CN114864124B - Measuring system, method and medium for nuclear safety level pressure transmitter identification test - Google Patents
Measuring system, method and medium for nuclear safety level pressure transmitter identification test Download PDFInfo
- Publication number
- CN114864124B CN114864124B CN202210293404.9A CN202210293404A CN114864124B CN 114864124 B CN114864124 B CN 114864124B CN 202210293404 A CN202210293404 A CN 202210293404A CN 114864124 B CN114864124 B CN 114864124B
- Authority
- CN
- China
- Prior art keywords
- nuclear safety
- safety level
- output
- pressure
- level pressure
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
- 238000000034 method Methods 0.000 title claims abstract description 42
- 238000013095 identification testing Methods 0.000 title abstract description 13
- 238000005259 measurement Methods 0.000 claims abstract description 34
- 230000004044 response Effects 0.000 claims abstract description 27
- 238000012360 testing method Methods 0.000 claims description 84
- 238000012797 qualification Methods 0.000 claims description 23
- 238000006243 chemical reaction Methods 0.000 claims description 19
- 238000005070 sampling Methods 0.000 claims description 17
- 238000004590 computer program Methods 0.000 claims description 6
- 238000004364 calculation method Methods 0.000 claims description 5
- 230000003247 decreasing effect Effects 0.000 claims description 4
- 230000007423 decrease Effects 0.000 claims description 2
- 238000000691 measurement method Methods 0.000 abstract description 6
- 238000001514 detection method Methods 0.000 abstract description 3
- 238000012544 monitoring process Methods 0.000 description 10
- 230000006870 function Effects 0.000 description 4
- 238000011056 performance test Methods 0.000 description 3
- 238000004891 communication Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- QWCRAEMEVRGPNT-UHFFFAOYSA-N buspirone Chemical compound C1C(=O)N(CCCCN2CCN(CC2)C=2N=CC=CN=2)C(=O)CC21CCCC2 QWCRAEMEVRGPNT-UHFFFAOYSA-N 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000003287 optical effect Effects 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01L—MEASURING FORCE, STRESS, TORQUE, WORK, MECHANICAL POWER, MECHANICAL EFFICIENCY, OR FLUID PRESSURE
- G01L27/00—Testing or calibrating of apparatus for measuring fluid pressure
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Physics & Mathematics (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Measuring Fluid Pressure (AREA)
Abstract
The invention discloses a measuring system, a measuring method, a medium and electronic equipment for a nuclear safety level pressure transmitter identification test, 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 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 for the pressure source, the control system and the nuclear safety level pressure transmitters; the invention controls the pressure source to output pressure to a plurality of nuclear safety level pressure transmitters through the control system, then collects the output conditions of the plurality of nuclear safety level pressure transmitters through the signal collecting module, and then realizes the measurement of the state detection, the basic deviation measurement and the response time measurement of the nuclear safety level pressure transmitters through the measurement method adopting the 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 measuring method and a measuring medium for a nuclear safety level pressure transmitter identification test.
Background
The nuclear safety pressure transmitter is used for measuring thermal parameters such as pressure, liquid level, flow and the like of the nuclear power station during normal operation, and particularly can still provide important thermal parameters for a nuclear power station protection system and a post-accident monitoring system under accident working conditions and after accidents, so that whether a safety protection strategy under the accident working conditions can be realized or not is related, and the nuclear safety pressure transmitter has very important effect on safe and reliable operation of the nuclear power station.
The qualification tests of the nuclear safety level pressure transmitter include four main types of tests, namely a benchmark test, a limit parameter test, a durability test, an accident and a performance test after the accident.
The basic bias and response time measurements are included in the baseline test and require at least three nuclear safety grade pressure transmitters of the same model specification to be tested as prototypes.
Continuous monitoring of the basic deviation of the output results of the nuclear safety pressure transmitter is required during durability tests, accident and post-accident performance tests, and the basic deviation and response time are also generally required to be measured after the tests are finished.
The measurement of the basic deviation and the response time can be realized simultaneously by a plurality of nuclear safety level pressure transmitters, but the output of the transmitters is read out by a plurality of ampere meters, the measurement results of the basic deviation and the response time are obtained by analyzing and calculating after the data are arranged by a measurer, the measurement efficiency is low, and the degree of automation is low.
In the durability test, accident and performance test after accident, a fixed time point is selected, and the output result of the nuclear safety pressure transmitter is obtained by measuring the voltage values connected in series on the standard resistor of the loop one by one, so that continuous monitoring is not realized.
Disclosure of Invention
The invention aims to provide a measuring system, a measuring method, a medium and electronic equipment for the identification test of the nuclear safety level pressure transmitter, which solve the measuring problem in the identification test of the nuclear safety level pressure transmitter.
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 plurality of nuclear safety level pressure transmitters;
The output ends of the pressure sources are communicated with the pressure input ends of the plurality 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 collector and the signal input end of the pressure source;
And a working power supply electrically connected to 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 with the power supply loops of the nuclear safety pressure transmitters and the working power supply;
the signal selection circuit is used for sequentially conducting a plurality of input ports with the output ports according to a certain time interval, and a plurality of input ends of the signal selection circuit are respectively and electrically connected with non-grounding ends of a plurality of sampling resistors;
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 control ends of the signal selection circuit and the digital-to-analog conversion circuit.
A method of measuring a nuclear safety level pressure transmitter qualification test for continuous status monitoring during the nuclear safety level pressure transmitter test, the method being based on a system of measuring a nuclear safety level pressure transmitter qualification test as described above, the method comprising:
A1, setting state continuous monitoring parameters including pressure source output pressure and deviation alarm threshold;
a2, the control system sends the pressure value output by the pressure source to the pressure source, and waits for the pressure source to return to an output state;
A3, after receiving the output state returned by the pressure source, the control signal acquisition module sequentially reads the output signals of the plurality of nuclear safety level pressure transmitters;
a4, calculating 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, and outputting an alarm signal if the deviation reaches the alarm threshold.
A method of measuring a nuclear safety level pressure transmitter qualification test for use in basic bias measurement during the nuclear safety level pressure transmitter test, the method being based on a system of measuring a nuclear safety level pressure transmitter qualification test as 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 in 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, the control signal acquisition module sequentially reads the output signals of the plurality of nuclear safety level pressure transmitters, and then circularly reads the output signals for a plurality of times according to the set cycle times;
B4, obtaining the measured deviation of the test point;
B5, sequentially obtaining measured deviations of the rest test points according to the steps B2-B4;
and B6, obtaining basic deviation, return difference, end group consistency deviation and repeatability deviation according to the measured deviations of the test points.
Preferably, the pressure value of the test point comprises a minimum pressure value and a maximum pressure value of the measuring range of the nuclear safety level pressure transmitter and a plurality of sequentially increased pressure values, and the pressure value difference of two adjacent test points is equal;
Step B5 includes two measuring strokes, the first measuring stroke being an upper stroke in which the pressure value increases in sequence, and the second measuring stroke being a lower stroke in which the pressure value decreases in sequence.
Specifically, the calculation formula of the measured deviation is:
δi＝(Ii-I0)/Iw×100％
In the formula, delta i, namely, the ith cycle of the same stroke at a certain test point is used for measuring deviation;
I i -the ith output current of the test point;
I 0 -the standard output current of the test point;
I w -output range, i.e., the difference between the upper and lower limits of the output current.
Specifically, the basic 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 of reading;
the return difference is the maximum deviation between the adjacent upper stroke output and lower stroke output in any 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;
The calculation formula of the repeatability deviation delta R is as follows:
wherein i is the cycle number set in the step B1;
-average deviation value for a test point;
delta 1,δ2......δi -the deviation was measured for the ith cycle of the same run at this test point.
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 system of measuring a nuclear safety level pressure transmitter qualification test as described above, the method comprising:
c1, setting response time parameters including the range and the response time percentage of the nuclear safety level pressure transmitter;
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 release instruction to the pressure source and starts timing;
the control signal acquisition module sequentially reads output signals of the plurality of nuclear safety level pressure transmitters;
C5, after the output signals of the nuclear safety level pressure transmitters are all zeroed, finishing timing;
C6, obtaining response time, wherein the response time is the time required for the output signal to drop from 100% to a set response time percentage.
A computer readable storage medium storing a computer program, wherein the computer program when executed by a processor performs the steps of a method of measuring a nuclear safety level pressure transmitter identification test as described above.
An electronic device, comprising: at least one processor; and
A memory communicatively coupled to the at least one processor; wherein,
The memory stores instructions executable by the at least one processor to enable the at least one processor to perform the steps of a method of measuring a nuclear safety level pressure transmitter qualification test as described above.
Compared with the prior art, the invention has the following advantages and beneficial effects:
The invention realizes basic setting for state detection, basic deviation measurement and response time measurement of the nuclear safety level pressure transmitters by arranging a measurement system, controlling a pressure source to output pressure to the plurality of nuclear safety level pressure transmitters by a control system and then collecting the output conditions of the plurality of nuclear safety level pressure transmitters by a signal collecting module;
And then, carrying out real-time state detection, basic deviation measurement and influence time measurement on a plurality of nuclear safety level pressure transmitters in the identification test by adopting a measurement method of the nuclear safety level pressure transmitter identification test.
Drawings
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 in accordance with the present invention.
Fig. 2 is a block diagram of the control system, signal acquisition platform and operating power supply according to the present invention.
FIG. 3 is a flow chart of a method of measurement of a nuclear safety level pressure transmitter qualification test according to the present invention.
Detailed Description
The present invention will be described in further detail with reference to the drawings and embodiments, for the purpose of making the objects, technical solutions and advantages of the present invention more apparent. It is to be understood that the specific embodiments described herein are merely illustrative of the substances, and not restrictive of the invention.
It should be further noted that, for convenience of description, only the portions related to the present invention are shown in the drawings.
Embodiments of the present invention 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 1
The embodiment provides a measuring system for a nuclear safety level pressure transmitter identification test, which mainly has the following functions;
The status is continuously monitored during testing of the multiple nuclear safety level pressure transmitters. The power supply can be provided for the multi-nuclear-level safety-level pressure transmitters, the output values of the multi-nuclear-safety-level pressure transmitters are continuously monitored, and out-of-tolerance alarms are given in real time according to the output values.
Basic deviation measurement of multiple 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 flow of the basic deviation, and calculates the measurement results of the basic deviation, return difference, repeatability deviation, end group consistency deviation and the like.
Multiple nuclear safety level pressure transmitter response time measurements. The system can provide power for the multiple nuclear safety level pressure transmitters, output control signals of the pressure sources, control the pressure sources to change rapidly, measure the output of the multiple nuclear safety level pressure transmitters at the same time, and analyze and calculate the response time of the multiple 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 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 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 working power supply.
In practice, the number of the nuclear safety level pressure transmitters is plural, but in this embodiment and all the embodiments described below, the description is made in relation to the case where the number of the nuclear safety level pressure transmitters is 3 as an example, as shown in fig. 1 and 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 or a control system RS232 interface of the pressure source, the output of the pressure source is connected to the four-way joint through a pipeline, the four-way joint is divided into three paths of outputs, and the three paths of outputs are respectively output to the inputs of the three nuclear-grade nuclear safety-grade pressure transmitters through pipelines.
The control system outputs a 24VDC power supply, the three nuclear-level nuclear safety-level pressure transmitters are connected in parallel with the power supply output by the control system to form three power supply loops, the three power supply loops are loops output by the nuclear-level nuclear safety-level pressure transmitters at the same time, the signal acquisition modules respectively measure output currents on the three loops, real-time monitoring is carried out on the output state of the nuclear-level nuclear safety-level pressure transmitters, and reference parameters of the nuclear-level nuclear safety-level pressure transmitters are measured.
The connection structure of the control system, the signal acquisition module and the working power supply is shown in figure 2.
The working power supply converts 220VAC power supply into three groups of power supply output of 5VDC, 12VDC and 24VDC, and provides 5VD working power supply for the control system (an embedded computer is adopted in the embodiment) and the signal acquisition module, provides 12VDC working power supply for the touch screen and provides 24VDC working power supply for the nuclear-level nuclear safety-level 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 measurement results 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 and receives signals for controlling the output of the pressure source and signals for receiving the output state 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: 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 the power supply loops of the plurality of nuclear safety pressure transmitters and the working power supply;
The signal sampling circuit is connected with a high-precision sampling resistor in series in the output loop of each nuclear-level nuclear safety-level pressure transmitter. The example comprises three nuclear-level nuclear safety-level pressure transmitters, so 250 omega + -0.01% high-precision sampling resistors are respectively connected in series on output loops of the three nuclear-level nuclear safety-level pressure transmitters, one ends of the three sampling resistors are all connected to 24VDC ground, the nuclear safety-level pressure transmitters output 4-20 mA signals to generate 1-5V voltages on the three sampling resistors, and the other ends of the three sampling resistors are connected to input ends of a signal selection circuit as output signals respectively.
The signal selection circuit is used for sequentially conducting the plurality of input ports with the output ports according to a certain time interval, and the 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 signal selection circuit is composed of a multichannel 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 switch, the control output port of the FPGA is connected to the control port of the analog switch, the FPGA module outputs the control logic time sequence of the analog switch, and the control analog switch sequentially conducts the plurality of input ports of the analog switch with the output ports according to a certain time interval, so that the multipath input signals are sequentially output one by one.
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 control ends of the signal selection circuit and the digital-to-analog conversion circuit.
The FPGA mainly realizes the logic control functions of the signal selection circuit and the analog-to-digital conversion circuit, adopts an Altera Cyclone I series FPGA chip as a core processor, and the peripheral circuit comprises the following components: serial configurator, external clock, power supply and download interface, 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 the multipath 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 is used for carrying out analog-to-digital conversion on the voltage signals output by the three nuclear-level nuclear safety level pressure transmitters into serial digital signals, and the serial digital signals enter the FPGA module to be stored for reading by the embedded computer. The circuit adopts a 16-bit AD conversion chip, the conversion frequency of the circuit can reach 100kbps, the output port of the signal selection circuit is connected with the input port of the AD conversion chip, the AD control output port of the FPGA module is connected to the control port of the AD conversion chip, and the serial signal input port of the FPGA is connected with the serial signal output port of the AD conversion chip.
Example two
This embodiment provides a measurement method for a nuclear safety level pressure transmitter qualification test for status continuous monitoring during the nuclear safety level pressure transmitter test, as shown on the left side of fig. 3, the method being based on a measurement system for the nuclear safety level pressure transmitter qualification test in embodiment one, the method comprising:
A1, setting state continuous monitoring parameters including pressure source output pressure and deviation alarm threshold;
Setting parameters of a control system through a touch screen, wherein in the embodiment, a prototype is set to be a meter type, 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 output of a pressure source is 1.9MPa, and the like, and the parameters are written into an embedded computer through an RS232 interface;
A2, the control system sends the pressure value output by the pressure source to the pressure source, and waits for the pressure source to return to an output state; for determining that the pressure source has been operated.
A3, after receiving the output state returned by the pressure source, the control signal acquisition module sequentially reads the output signals of the plurality of nuclear safety level pressure transmitters; in this embodiment, the data of channels 1 to 3 are sequentially read.
A4, calculating output deviation according to the output signal of the nuclear safety level pressure transmitter and the output pressure of the pressure source, wherein the calculating method of the output deviation is (output signal-output pressure of the pressure source)/output pressure of the pressure source multiplied by 100%.
And A5, comparing the output deviation with a deviation alarm threshold, outputting an alarm signal if the deviation alarm threshold is reached, and continuously detecting if the deviation alarm threshold is not reached, so that continuous monitoring of the state is realized.
Example III
The present embodiment provides a measurement method for a nuclear safety level pressure transmitter qualification test for basic bias measurement during the nuclear safety level pressure transmitter test, as shown on the side of fig. 3, the method being based on a measurement system for the nuclear safety level pressure transmitter qualification test in embodiment one, 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;
The pressure value of the test point comprises a minimum pressure value and a maximum pressure value of the measuring range of the nuclear safety level pressure transmitter and a plurality of sequentially increased pressure values, and the pressure value difference of two adjacent test points is equal;
Through touch screen input, the sample machine is set as a meter 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 times are 3 times, the number of measuring channels is 3, and the parameters are written into the embedded computer through an RS232 interface.
And B2, the control system sends one test point (the first test point is selected to be 0MPa in the embodiment) to the pressure source, waits for the pressure source to return to an output state, and determines that the pressure source starts working.
B3, after receiving the output state returned by the pressure source, the control signal acquisition module sequentially reads the output signals of the plurality of nuclear safety level pressure transmitters, and then circularly reads for 3 times according to the set circulation times;
B4, obtaining the measured deviation of the test point;
The calculation formula of the measured deviation is:
δi＝(Ii-I0)/Iw×100％
In the formula, delta i, namely, the ith cycle of the same stroke at a certain test point is used for measuring deviation; i=1, 2, 3 in this embodiment;
I i -the ith output current of the test point;
I 0 -the standard output current of the test point;
I w -output range, i.e., the difference between the upper and lower limits of the output current.
B5, sequentially obtaining measured deviations of the rest test points according to the steps B2-B4;
the embodiment comprises two measuring strokes, wherein the first measuring stroke is an upper stroke (0 MPa, 0.4MPa, 0.8MPa, 1.2MPa, 1.8MPa and 2 MPa) with sequentially increased pressure values, and the second measuring stroke is a lower stroke (2 MPa, 1.8MPa, 1.2MPa, 0.8MPa, 0.4MPa and 0 MPa) with sequentially decreased pressure values.
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 between the adjacent upper stroke output and lower 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;
the calculation formula of the repeatability deviation delta R is as follows:
wherein i is the cycle number set in the step B1;
-average deviation value for a test point;
delta 1,δ2......δi -the deviation was measured for the ith cycle of the same run at this test point.
Example IV
This embodiment provides a measurement method for a nuclear safety level pressure transmitter qualification test for response time measurement during the nuclear safety level pressure transmitter test, as shown on the right side of fig. 3, the method being based on a measurement system for the nuclear safety level pressure transmitter qualification test in embodiment one, the method comprising:
c1, setting response time parameters including the range and the response time percentage of the nuclear safety level pressure transmitter;
in the embodiment, the prototype is set as a meter type, the measuring range is 0-2 MPa, the response time percentage is 63.2%, the number of measuring channels is 3 and the like, and the parameters are written into the embedded computer through an RS232 interface.
C2, the control system sends a pressure value of the maximum range (2 MPa) of the nuclear safety level pressure transmitter to the pressure source, and waits for the pressure source to return to an output state; it is determined that the pressure source is operating.
C3, after receiving the output state returned by the pressure source, the control system sends a pressure release instruction to the pressure source and starts timing;
the control signal acquisition module sequentially reads output signals of the plurality of nuclear safety level pressure transmitters;
and C5, after the output signals of the plurality of nuclear safety level pressure transmitters are all zeroed, ending the timing, independently timing each nuclear safety level pressure transmitter, and recording the relation between the pressure value and time of each nuclear safety level pressure transmitter.
C6, obtaining response time, which is the time required for the output signal to drop from 100% to a set percentage of response time.
And (3) drawing curves of the three channel outputs along with time on the Y axis by taking time as an X axis and taking the time required for the output to drop 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 performs the steps of a method of measuring a nuclear safety level pressure transmitter identification test as described above.
That is, as shown in fig. 3, the present embodiment can write the methods in the second, third, and fourth embodiments into one computer program, and then implement the different measurement methods in the second, third, and fourth embodiments by selecting the operation mode.
Computer readable media may include computer storage media and communication media without loss of generality. 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 memory 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 recognize that computer storage media are not limited to the ones described above. The above-described system memory and mass storage devices may be collectively referred to as memory.
An electronic device, comprising: at least one processor; and
A memory communicatively coupled to the at least one processor; wherein,
The memory stores instructions executable by the at least one processor to enable the at least one processor to perform the steps of a method of measuring a nuclear safety level pressure transmitter qualification test as described above.
The memory may be used to store software programs and modules, and the processor executes various functional applications of the terminal and data processing by running the software programs and modules stored in the memory. The memory may mainly include a storage program area and a storage data area, wherein the storage program 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, etc. In addition, 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 of the present specification, reference to the terms "one embodiment/manner," "some embodiments/manner," "example," "a particular example," "some examples," etc., means that a particular feature, structure, material, or characteristic described in connection with the embodiment/manner or example is included in at least one embodiment/manner or example of the application. In this specification, the schematic representations of the above terms are not necessarily for the same embodiment/manner 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/modes or examples described in this specification and the features of the various embodiments/modes or examples can be combined and combined by persons skilled in the art without contradiction.
Furthermore, the terms "first," "second," and the like, are used for descriptive purposes only and are not to be construed as indicating or implying a relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defining "a first" or "a second" may explicitly or implicitly include at least one such feature. In the description of the present application, the meaning of "plurality" means at least two, for example, two, three, etc., unless specifically defined otherwise.
It will be appreciated by persons skilled in the art that the above embodiments are provided for clarity of illustration only and are not intended to limit the scope of the invention. Other variations or modifications of the above-described invention will be apparent to those of skill in the art, and are still within the scope of the invention.
Claims (9)
1. A method of measuring a nuclear safety level pressure transmitter qualification test for use in a basic bias 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, the system comprising:
The signal acquisition module is used for acquiring output signals of the plurality of nuclear safety level pressure transmitters;
The output ends of the pressure sources are communicated with the pressure input ends of the plurality 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 collector and the signal input end of the pressure source;
A working power supply electrically connected to the pressure source, the control system, and the nuclear safety level pressure transmitter;
the method comprises the following steps:
B1, setting basic deviation measurement parameters including test points and cycle times, wherein the test points are a plurality of pressure values in 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, the control signal acquisition module sequentially reads the output signals of the plurality of nuclear safety level pressure transmitters, and then circularly reads the output signals for a plurality of times according to the set cycle times;
B4, obtaining the measured deviation of the test point;
B5, sequentially obtaining measured deviations of the rest test points according to the steps B2-B4;
and B6, obtaining basic deviation, return difference, end group consistency deviation and repeatability deviation according to the measured deviations of the test points.
2. The method of claim 1, 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 level pressure transmitter, and the pressure values at two adjacent test points are equal in difference;
Step B5 includes two measuring strokes, the first measuring stroke being an upper stroke in which the pressure value increases in sequence, and the second measuring stroke being a lower stroke in which the pressure value decreases in sequence.
3. The method of claim 2, wherein the measured deviation is calculated as:
δi＝(Ii-I0)/Iw×100％
in the formula, delta i is the deviation measured in the ith cycle of the same stroke at a certain test point;
ii-the ith output current of the test point;
I0, the standard output current of the test point;
iw-output range, i.e., the difference between the upper and lower limits of the output current.
4. A method of measuring a nuclear safety level pressure transmitter qualification test as claimed in claim 3, wherein the base deviation is the maximum deviation of any measured deviation from an ideal deviation when the input pressure value is increased or decreased in any one cycle of reading;
the return difference is the maximum deviation between the adjacent upper stroke output and lower stroke output in any 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;
The calculation formula of the repeatability deviation delta R is as follows:
wherein i is the cycle number set in the step B1;
-average deviation value for a test point;
delta 1,δ2......δi -the deviation was measured for the ith cycle of the same run at this test point.
5. The method of claim 1, wherein the signal acquisition module comprises:
the sampling resistors are respectively connected in series with the power supply loops of the nuclear safety pressure transmitters and the working power supply;
the signal selection circuit is used for sequentially conducting a plurality of input ports with the output ports according to a certain time interval, and a plurality of input ends of the signal selection circuit are respectively and electrically connected with non-grounding ends of a plurality of sampling resistors;
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 control ends of the signal selection circuit and the digital-to-analog conversion circuit.
6. 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, the system comprising:
The signal acquisition module is used for acquiring output signals of the plurality of nuclear safety level pressure transmitters;
The output ends of the pressure sources are communicated with the pressure input ends of the plurality 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 collector and the signal input end of the pressure source;
A working power supply electrically connected to the pressure source, the control system, and the nuclear safety level pressure transmitter;
the method comprises the following steps:
c1, setting response time parameters including the range and the response time percentage of the nuclear safety level pressure transmitter;
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 release instruction to the pressure source and starts timing;
the control signal acquisition module sequentially reads output signals of the plurality of nuclear safety level pressure transmitters;
C5, after the output signals of the nuclear safety level pressure transmitters are all zeroed, finishing timing;
C6, obtaining response time, wherein the response time is the time required for the output signal to drop from 100% to a set response time percentage.
7. The method of claim 6, wherein the signal acquisition module comprises:
the sampling resistors are respectively connected in series with the power supply loops of the nuclear safety pressure transmitters and the working power supply;
the signal selection circuit is used for sequentially conducting a plurality of input ports with the output ports according to a certain time interval, and a plurality of input ends of the signal selection circuit are respectively and electrically connected with non-grounding ends of a plurality of sampling resistors;
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 control ends of the signal selection circuit and the digital-to-analog conversion circuit.
8. A computer readable storage medium storing a computer program, characterized in that the computer program when executed by a processor implements the steps of the method according to any of claims 1-6.
9. An electronic device, comprising: at least one processor; and
A memory communicatively coupled to the at least one processor; wherein,
The memory stores instructions executable by the at least one processor to enable the at least one processor to perform the steps of the method of any one of claims 1-6.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210293404.9A CN114864124B (en) | 2022-03-24 | 2022-03-24 | Measuring system, method and medium for nuclear safety level pressure transmitter identification test |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210293404.9A CN114864124B (en) | 2022-03-24 | 2022-03-24 | Measuring system, method and medium for nuclear safety level pressure transmitter identification test |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN114864124A CN114864124A (en) | 2022-08-05 |
| CN114864124B true CN114864124B (en) | 2024-06-18 |
Family
ID=82627493
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202210293404.9A Active CN114864124B (en) | 2022-03-24 | 2022-03-24 | Measuring system, method and medium for nuclear safety level pressure transmitter identification test |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN114864124B (en) |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103033309A (en) * | 2011-09-28 | 2013-04-10 | 罗斯蒙德公司 | Pressure transmitter with diagnostics |
| 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 |
| CN212059232U (en) * | 2020-03-18 | 2020-12-01 | 华电莱州发电有限公司 | Intelligent pressure transmitter calibration system |
Family Cites Families (10)
| 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 |
| JP3329968B2 (en) * | 1994-12-21 | 2002-09-30 | 株式会社日立製作所 | Calibration device 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 |
| RU2452935C2 (en) * | 2007-06-30 | 2012-06-10 | Эндресс + Хаузер Флоутек Аг | Measuring system for medium flowing in process pipeline |
| WO2010015569A1 (en) * | 2008-08-07 | 2010-02-11 | Siemens Aktiengesellschaft | Pressure measurement converter and method for the operation thereof |
| US8145145B2 (en) * | 2009-04-03 | 2012-03-27 | Invensys Systems, Inc. | Self evaluating transmitter |
| US9121743B2 (en) * | 2012-05-31 | 2015-09-01 | Rosemount Inc. | Process variable transmitter system with analog communication |
| JP6624156B2 (en) * | 2017-05-17 | 2019-12-25 | 横河電機株式会社 | Calibration work support device, calibration work support method, calibration work support program, and recording medium |
| US11181403B2 (en) * | 2019-09-24 | 2021-11-23 | Rosemount Inc. | Process variable sensor testing |
| CN111817538B (en) * | 2020-07-15 | 2021-10-01 | 中国核动力研究设计院 | Multi-channel power adapter of two-wire system connection charge converter and application method |
-
2022
- 2022-03-24 CN CN202210293404.9A patent/CN114864124B/en active Active
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103033309A (en) * | 2011-09-28 | 2013-04-10 | 罗斯蒙德公司 | Pressure transmitter with diagnostics |
| 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 |
| CN212059232U (en) * | 2020-03-18 | 2020-12-01 | 华电莱州发电有限公司 | Intelligent pressure transmitter calibration system |
Also Published As
| Publication number | Publication date |
|---|---|
| CN114864124A (en) | 2022-08-05 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN101718849B (en) | Automatic calibration system of charge/discharge detection instrument of storage battery | |
| CN102478385B (en) | Probe card detection method and system | |
| CN201378204Y (en) | Automatic detecting and metrological characteristic analyzing device for energy meter standard devices | |
| CN211452669U (en) | Multi-temperature-point multi-channel resistance acquisition system based on standard sample | |
| CN101865958A (en) | System and method for testing power supply adapter | |
| CN101750597A (en) | Effectiveness calibrating method used for automatic testing equipment | |
| CN109856484A (en) | Battery management system physical detection function test method | |
| CN112034412A (en) | Intelligent electric energy meter misalignment analysis method and system based on intelligent isolating switch | |
| CN105548865A (en) | Camera module group power-on time sequence testing device and method | |
| CN111929587A (en) | Integrated detection method for power battery pack finished product | |
| CN102928124A (en) | Inspection tool of temperature transmitter | |
| CN114864124B (en) | Measuring system, method and medium for nuclear safety level pressure transmitter identification test | |
| CN110496799B (en) | Method for distinguishing abnormal cell by formation | |
| CN111693922A (en) | Automatic calibration system of impedance tester | |
| CN107543574B (en) | Automatic detector for high-temperature aging test of airborne sensor and operation method | |
| CN110308412A (en) | A kind of method and its system of automatically calibrating electrical high capability instrument instrument | |
| CN110118630B (en) | Calibration judgment method for magnetic control vacuum gauge | |
| CN113759241A (en) | Method for realizing automatic testing system of shaft angle type chip | |
| CN211123230U (en) | Portable automatic debugging system for calibrator | |
| CN208537602U (en) | A kind of emulation clamp on amperemeter | |
| CN102072990A (en) | Ageing detection device for laser | |
| CN112578292A (en) | Method and system for graded utilization and sorting of retired batteries | |
| CN107247186B (en) | A kind of resistance multi-point tester and its detection method | |
| CN111157938A (en) | Method and system for evaluating metering process capacity of automatic verification system | |
| CN113030821A (en) | Electric quantity calibration method and device |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| TA01 | Transfer of patent application right |
Effective date of registration: 20230111 Address after: No.328, Section 1, Changshun Avenue, Shuangliu District, Chengdu, Sichuan 610000 Applicant after: NUCLEAR POWER INSTITUTE OF CHINA Applicant after: SHANGHAI GUANGHUA INSTRUMENT Co.,Ltd. Address before: No.328, Section 1, Changshun Avenue, Shuangliu District, Chengdu, Sichuan 610000 Applicant before: NUCLEAR POWER INSTITUTE OF CHINA |
|
| TA01 | Transfer of patent application right | ||
| GR01 | Patent grant |