CN107204208A - A kind of portable neutron detector signal dynamics simulator - Google Patents
A kind of portable neutron detector signal dynamics simulator Download PDFInfo
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- CN107204208A CN107204208A CN201710280180.7A CN201710280180A CN107204208A CN 107204208 A CN107204208 A CN 107204208A CN 201710280180 A CN201710280180 A CN 201710280180A CN 107204208 A CN107204208 A CN 107204208A
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- 230000003993 interaction Effects 0.000 claims abstract description 38
- 238000004891 communication Methods 0.000 claims abstract description 30
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 claims abstract description 26
- 229910052796 boron Inorganic materials 0.000 claims abstract description 26
- 230000004992 fission Effects 0.000 claims abstract description 22
- 238000004088 simulation Methods 0.000 claims description 111
- 230000003287 optical effect Effects 0.000 claims description 13
- 230000004907 flux Effects 0.000 claims description 12
- 230000000737 periodic effect Effects 0.000 claims description 10
- 239000003990 capacitor Substances 0.000 claims description 8
- 238000005094 computer simulation Methods 0.000 claims description 7
- 230000005540 biological transmission Effects 0.000 claims description 3
- 238000010586 diagram Methods 0.000 description 7
- 238000001514 detection method Methods 0.000 description 4
- 238000007689 inspection Methods 0.000 description 4
- 238000012423 maintenance Methods 0.000 description 4
- 238000005070 sampling Methods 0.000 description 4
- 230000008859 change Effects 0.000 description 3
- 238000013461 design Methods 0.000 description 3
- 238000003745 diagnosis Methods 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 2
- 238000011900 installation process Methods 0.000 description 2
- 238000012827 research and development Methods 0.000 description 2
- 230000000630 rising effect Effects 0.000 description 2
- 230000003068 static effect Effects 0.000 description 2
- 230000008878 coupling Effects 0.000 description 1
- 238000010168 coupling process Methods 0.000 description 1
- 238000005859 coupling reaction Methods 0.000 description 1
- 238000002955 isolation Methods 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/108—Measuring reactor flux
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The present invention provides a kind of portable neutron detector signal dynamics simulator, the human-computer interaction module of connection communication, boron proportional counter-tube detector signal emulation module, compensated ionization chamber's detector signal emulation module, long ion chamber's detector signal emulation module, fission chamber detector signal emulation module, analog module, digital module and control communication module are realized including backboard, and by backboard.Human-computer interaction module obtains user input data and produces corresponding emulation signal by controlling communication module to distribute to boron proportional counter-tube detector signal emulation module, compensated ionization chamber's detector signal emulation module, long ion chamber's detector signal emulation module, fission chamber detector signal emulation module, analog module and digital module through backboard.Implement the present invention, emulation RPN neutron detectors output signal and the external system output signal associated with RPN, examined for the equipment debugging of RPN systems, logic function and fault detect provides technological means.
Description
Technical Field
The invention relates to the technical field of nuclear power safety measurement, in particular to a portable neutron detector signal dynamic simulation device.
Background
The out-of-reactor nuclear instrumentation system (RPN) continuously monitors reactor power, power change rate and axial distribution of power by a series of neutron detectors distributed outside the reactor pressure vessel of a nuclear power plant, displays and records various measured signals, and feeds back reactor state information during reactor loading, shutdown, startup and power operation, which is one of important systems directly related to reactor safety.
At present, a nuclear power plant RPN system has no special neutron detector signal simulation device to realize equipment debugging and fault diagnosis, and the safe and stable operation of a nuclear power plant is influenced. Therefore, a neutron detector signal simulation device is needed, which can simulate and generate the output signal of the RPN neutron detector and the output signal of the external system associated with the RPN during the startup, shutdown and stable operation of the nuclear power plant, and provide a technical means for equipment debugging, logic function inspection and fault detection of the RPN system.
Disclosure of Invention
The technical problem to be solved by the embodiments of the present invention is to provide a portable neutron detector signal dynamic simulation apparatus, which can simulate and generate an output signal of an RPN neutron detector and an external system output signal associated with an RPN during a reactor start-up, a reactor shutdown and a stable operation of a nuclear power plant, and provide a technical means for equipment debugging, logic function inspection and fault detection of the RPN system.
In order to solve the technical problem, an embodiment of the present invention provides a portable neutron detector signal dynamic simulation apparatus, which includes a back plate, and a human-computer interaction module, a boron proportional counter tube detector signal simulation module, a compensation ionization chamber detector signal simulation module, a long ionization chamber detector signal simulation module, a fission chamber detector signal simulation module, an analog quantity module, a digital quantity module and a control communication module, which are all interconnected and communicated through the back plate; wherein,
the man-machine interaction module is used for acquiring user input data and correspondingly allocating the acquired user input data to the boron proportional counter tube detector signal simulation module, the compensation ionization chamber detector signal simulation module, the long ionization chamber detector signal simulation module, the fission chamber detector signal simulation module, the analog quantity module and the digital quantity module;
the boron proportional counter tube detector signal simulation module is used for simulating a voltage pulse periodic signal or a voltage pulse constant value signal output by the source range detector when the neutron flux is positioned in a first preset variation range during the shutdown period and the startup initial stage of the reactor according to corresponding data distributed by the human-computer interaction module;
the compensation ionization chamber detector signal simulation module is used for simulating a current periodic signal or a current constant value signal output by the middle-range detector when the neutron flux is within a second preset variation range from the critical stage of the reactor to the 10% Pn stage of the rated power according to corresponding data distributed by the man-machine interaction module;
the long ionization chamber detector signal simulation module is used for simulating a current constant value signal output by the power range detector when the neutron flux of the upper half part and the lower half part of the reactor core of the reactor is positioned in a third preset variation range according to corresponding data distributed by the human-computer interaction module;
the fission chamber detector signal simulation module is used for simulating a current pulse signal output by the intermediate range detector when the nuclear power of the reactor is smaller than a preset threshold value and/or a voltage signal output by the intermediate range detector when the nuclear power of the reactor is larger than or equal to the preset threshold value according to corresponding data distributed by the man-machine interaction module;
the analog quantity module is used for correspondingly simulating and generating an analog quantity signal outside the RPN according to the corresponding data distributed by the human-computer interaction module, and carrying out data acquisition, functional operation and interface communication with an external system related to the RPN;
the digital quantity module is used for correspondingly simulating and generating digital quantity signals outside the RPN according to the corresponding data distributed by the human-computer interaction module, and carrying out data acquisition, functional operation and interface communication with an external system related to the RPN;
and the control communication module is used for controlling data exchange and transmission among the modules in the device.
The boron proportional counter tube detector signal simulation module comprises a first optical coupler isolator, a first monostable trigger, a first n-shaped attenuation network and a first high-voltage capacitor which are sequentially connected.
The compensation ionization chamber detector signal simulation module comprises a first digital-to-analog converter, a first low-pass filter and a first voltage/current converter formed by an operational amplifier, wherein the first digital-to-analog converter, the first low-pass filter and the first voltage/current converter are sequentially connected.
The long ionization chamber detector signal simulation module consists of six identical current constant value signal simulation circuits, three of the six current constant value signal simulation circuits are used for simulating the upper half part of the reactor core, and the other three of the six current constant value signal simulation circuits are used for simulating the lower half part of the reactor core; each current constant value signal analog circuit comprises a second digital-to-analog converter, a second low-pass filter and a second voltage/current converter formed by an operational amplifier which are connected in sequence.
Wherein the fission chamber detector signal simulation module comprises a pulse mode analog circuit and/or a root mean square mode analog circuit; wherein,
the pulse mode analog circuit is used for simulating a current pulse signal output by the intermediate range detector when the nuclear power of the reactor is smaller than the preset threshold value; the pulse mode analog circuit comprises a second optical coupler isolator, a second monostable trigger, a second n-shaped attenuation network and a second high-voltage capacitor which are sequentially connected;
the root-mean-square mode analog circuit is used for simulating a voltage signal output by the intermediate range detector when the nuclear power of the reactor is greater than or equal to the preset threshold value; the RMS mode analog circuit comprises a third digital-to-analog converter, a third low-pass filter and a third n-type attenuation network which are connected in sequence.
The analog quantity module is provided with eight analog quantity output channels and eight analog quantity acquisition channels, and all the channels are mutually isolated by using optical couplers; the temperature drift of the analog quantity module is less than or equal to 100ppm/° C, and the analog quantity module has surge and electrostatic discharge protection functions. .
The digital quantity module is provided with sixteen digital quantity output channels and sixteen digital quantity acquisition channels, and all the channels are mutually isolated by using optical couplers; the digital quantity module has surge and electrostatic discharge protection functions.
Wherein the first preset variation range is [10 ]-1n/cm2·s，2*105n/cm2·s](ii) a The second predetermined variation rangeIs enclosed as [2 x 10]2n/cm2·s，5*1010n/cm2·s](ii) a The third preset variation range is [5 x 10]2n/cm2·s，5*1010n/cm2·s]。
Wherein the preset threshold is 10 of the full power of the reactor-2%。
The back plate, the human-computer interaction module, the boron proportional counter tube detector signal simulation module, the compensation ionization chamber detector signal simulation module, the long ionization chamber detector signal simulation module, the fission chamber detector signal simulation module, the analog quantity module, the digital quantity module and the control communication module in the device are all arranged in a portable case and are all integrated circuit boards; the boron proportional counter tube detector signal simulation module, the compensation ionization chamber detector signal simulation module, the long ionization chamber detector signal simulation module, the fission chamber detector signal simulation module, the analog quantity module, the digital quantity module and the control communication module can be installed on the back plate in a hot-plug mode.
The embodiment of the invention has the following beneficial effects:
1. the invention adopts a modular design, can be integrated in a portable case, and has the advantages of easy portability, simple installation process, low maintenance cost and the like;
2. the invention not only simulates the output signals of different types of neutron detectors of the RPN in the periods of starting, stopping and stable operation of the nuclear power station, provides check signals for research and development, equipment operation and maintenance, fault diagnosis and the like of the RPN system under laboratory conditions and in the field environment of the power plant, but also simulates signals of analog quantity, switching value and the like of other systems related to the RPN, and provides technical means for equipment debugging, logic function inspection and fault detection of the RPN system.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly introduced below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is within the scope of the present invention for those skilled in the art to obtain other drawings based on the drawings without inventive exercise.
Fig. 1 is a schematic system structure diagram of a portable neutron detector signal dynamic simulation apparatus provided in an embodiment of the present invention;
FIG. 2 is a schematic diagram of a system configuration of a signal simulation module of the boron proportional counter tube detector of FIG. 1;
FIG. 3 is a schematic diagram of a system architecture for generating periodic signals of a signal simulation module of the boron proportional counter tube detector of FIG. 2;
FIG. 4 is a schematic diagram of a system configuration of a signal simulation module of the compensated ionization chamber detector of FIG. 1;
FIG. 5 is a schematic diagram of a system configuration for generating a periodic signal of the detector signal simulation module of the compensated ionization chamber of FIG. 4;
FIG. 6 is a schematic diagram of a system architecture of a signal simulation module of the long ionization chamber detector of FIG. 1;
FIG. 7 is a schematic diagram of the system architecture of the fission chamber detector signal simulation module of FIG. 1.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention will be described in further detail with reference to the accompanying drawings.
As shown in fig. 1, in an embodiment of the present invention, a portable neutron detector signal dynamic simulation apparatus is provided, which includes a back plate 1, and a human-computer interaction module 2, a boron proportional counter tube detector signal simulation module 3, a compensation ionization chamber detector signal simulation module 4, a long ionization chamber detector signal simulation module 5, a fission chamber detector signal simulation module 6, an analog quantity module 7, a digital quantity module 8, and a control communication module 9, which are all interconnected and communicated through the back plate 1.
In the embodiment of the invention, a back plate 1, a human-computer interaction module 2, a boron proportional counter tube detector signal simulation module 3, a compensation ionization chamber detector signal simulation module 4, a long ionization chamber detector signal simulation module 5, a fission chamber detector signal simulation module 6, an analog quantity module 7, a digital quantity module 8 and a control communication module 9 are all arranged in a portable case and are all integrated circuit boards; the boron proportional counter tube detector signal simulation module 3, the compensation ionization chamber detector signal simulation module 4, the long ionization chamber detector signal simulation module 5, the fission chamber detector signal simulation module 6, the analog quantity module 7, the digital quantity module 8 and the control communication module 9 can be arranged on the back plate 1 in a hot-plug mode. Of course, it can be understood that the front panel of the portable case is provided with a touch screen for displaying, and can read and control the data processed by the communication module 9, and also can set the user input data required by the human-computer interaction module 2 through the touch screen. Of course, the test data can be exported and analyzed through the USB interface of the front panel, and the data can be stored in an external device. Wherein,
the man-machine interaction module 2 is used for acquiring user input data and correspondingly allocating the acquired user input data to the boron proportional counter tube detector signal simulation module 3, the compensation ionization chamber detector signal simulation module 4, the long ionization chamber detector signal simulation module 5, the fission chamber detector signal simulation module 6, the analog quantity module 7 and the digital quantity module 8;
the boron proportional counter tube detector signal simulation module 3 is used for simulating a voltage pulse periodic signal or a voltage pulse constant value signal output by the source range detector when the neutron flux is positioned in a first preset variation range during the shutdown period and the startup initial stage of the reactor according to corresponding data distributed by the human-computer interaction module 2;
the compensation ionization chamber detector signal simulation module 4 is used for simulating a current periodic signal or a current constant value signal output by the middle-range detector when the neutron flux is within a second preset variation range from the critical stage of the reactor to the 10% Pn stage of the rated power according to corresponding data distributed by the man-machine interaction module 2;
the long ionization chamber detector signal simulation module 5 is used for simulating a current constant value signal output by the power range detector when the neutron flux of the upper half part and the lower half part of the reactor core of the reactor is positioned in a third preset variation range according to corresponding data distributed by the human-computer interaction module 2;
the fission chamber detector signal simulation module 6 is used for simulating a current pulse signal output by the intermediate range detector when the nuclear power of the reactor is smaller than a preset threshold value and/or a voltage signal output by the intermediate range detector when the nuclear power of the reactor is larger than or equal to the preset threshold value according to corresponding data distributed by the man-machine interaction module 2;
the analog quantity module 7 is used for correspondingly simulating and generating an analog quantity signal outside the RPN according to the corresponding data distributed by the human-computer interaction module 2, and carrying out data acquisition, functional operation and interface communication with an external system related to the RPN;
the digital quantity module 8 is used for correspondingly simulating and generating digital quantity signals outside the RPN according to the corresponding data distributed by the human-computer interaction module 2, and carrying out data acquisition, functional operation and interface communication with an external system related to the RPN;
and the control communication module 9 is used for controlling data exchange and transmission among the modules in the device.
It should be noted that the device also includes a low voltage power supply module 10 for each module in the device.
It can be understood that the boron proportional counter tube detector signal simulation module 3, the compensation ionization chamber detector signal simulation module 4, the long ionization chamber detector signal simulation module 5, the fission chamber detector signal simulation module 6, the analog quantity module 7 and the digital quantity module 8 control the respective modules to execute respective defined functions through software running on the human-computer interaction module 2, and simultaneously monitor the states of the respective modules in real time. The software running on the human-computer interaction module 2 is application software which is developed independently, and different working state models can be run to simulate different signals. For example, the corresponding detector signal simulation module is controlled to output corresponding simulation signals according to the running state models of the reactor under different working conditions, and analog quantity signals and switching quantity signals output by the external system of the RPN system are simulated, so that the purpose of simulating the external input environment of the RPN system under different working conditions of the reactor is achieved.
In the embodiment of the present invention, as shown in fig. 2, the boron proportional counter tube detector signal simulation module 3 includes a first optical coupler isolator 31, a first monostable trigger 32, a first n-type attenuation network 33, and a first high-voltage capacitor 34, which are connected in sequence. At this time, the man-machine interaction module 2 generates a signal through the control communication module 9, outputs a pulse signal through the first optical coupler isolator 31, outputs a pulse signal of a TTL level through the first monostable trigger 32 of 74LS123, reduces the amplitude of the pulse through the first n-type resistance attenuation network 33, and finally outputs a voltage pulse signal through the isolation of the first high-voltage capacitor 34. It should be noted that the first Π -shaped attenuation network 33 is formed from three resistors using designs common in the art.
The neutron flux in the shutdown period and the initial starting stage of the simulation reactor of the signal simulation module 3 of the boron proportional counter tube detector is within a first preset variation range (such as [10 ]-1n/cm2·s，2*105n/cm2·s]) The time source range detector outputs signals, the frequency of the signals is 1 Hz-10 MHz, the amplitude is 1mV, and the pulse width is less than or equal to 100 ns. It should be noted that the boron proportional counter tube detector signal simulation module 3 may also simulate the source range detector output signal according to the nuclear power range during reactor shutdown and during startup initialization, such as from 10-9% FP to 10-3% FP (FP full power) range.
The signal is not only a static voltage pulse constant value signal, but also a dynamic voltage pulse periodic signal, the period can be customized, such as 15s, 30s, 50s and 100s, and the output precision is less than 1%. Specifically, referring to fig. 3, the setting of the signal period is implemented by sampling the exponential signal in advance, storing the exponential signal in the ROM, determining the initial values of the period control word and the phase offset by the control communication module 9, triggering the rising edge of the clock signal, accumulating the phases, looking up the corresponding frequency value in the ROM table, and outputting the pulse signal with a period change through the frequency divider.
In the embodiment of the present invention, as shown in fig. 4, the compensation ionization chamber detector signal simulation module 4 includes a first digital-to-analog converter 41, a first low-pass filter 42 and a first voltage/current converter 43 composed of an operational amplifier, which are connected in sequence. At this time, the man-machine interaction module 2 generates a signal through the control communication module 9, outputs a voltage signal through the first analog-to-digital converter 41, filters a high-frequency signal through the first low-pass filter 42, and finally converts the high-frequency signal into a current signal through the first voltage/current converter 43 for output.
The neutron flux in the stage from critical simulation of the reactor to 10% Pn of rated power by the compensation ionization chamber detector signal simulation module 4 is within a second preset variation range (such as [2 x 10]2n/cm2·s，5*1010n/cm2·s]) The time intermediate range detector outputs a signal with a current of 10-11A～10-3A. It should be noted that the compensated ionization chamber detector signal simulation module 4 may also simulate mid-range detector output signals based on the nuclear power range from after reactor criticality to the 10% Pn phase of the rated power, e.g., from 10-6% FP to 100% FP.
The signal is not only a static voltage pulse constant value signal, but also a dynamic voltage pulse periodic signal, the period can be customized, such as 15s, 30s, 50s and 100s, and the output precision is less than 1%. Specifically referring to fig. 5, the setting of the signal period is implemented by sampling the exponential signal in advance, storing the exponential signal in the ROM, determining the initial values of the period control word and the phase offset by the control communication module 9, triggering the rising edge of the clock signal, accumulating the phases, looking up the corresponding current value in the ROM table, and outputting the current signal with the period change through the digital-to-analog converter.
In the embodiment of the present invention, as shown in fig. 6, the long ionization chamber detector signal simulation module 5 is composed of six identical current constant value signal simulation circuits, three of the six current constant value signal simulation circuits are used for simulating the upper half part of the reactor core, and the other three of the six current constant value signal simulation circuits are used for simulating the lower half part of the reactor core; each current constant value signal analog circuit includes a second digital-to-analog converter 51, a second low pass filter 52 and a second voltage/current converter 53 formed by an operational amplifier, which are connected in sequence. At this time, the human-computer interaction module 2 generates signals through the control communication module 9, and outputs voltage signals through the second analog-to-digital converter 51 in the six-path current constant value signal analog circuit, filters high-frequency signals through the second low-pass filter 52, and finally converts the high-frequency signals into corresponding six-path current signals through the second voltage/current converter 53 formed by an operational amplifier to output.
The long ionization chamber detector signal simulation module 5 simulates that the neutron flux of the upper half part and the lower half part of the reactor core are positioned in a third preset variation range (such as [5 x 10]2n/cm2·s，5*1010n/cm2·s]) The current constant value signal is output by the time-power range detector, and the current of the signal is 10-6A～2*10-4A. It should be noted that the long ionization chamber detector signal simulation module 5 may also simulate mid-span detector output signals according to the range of reactor nuclear power, such as from 10-1% FP to 200% FP.
In an embodiment of the invention, as shown in fig. 7, the fission-chamber detector signal simulation module 6 includes a pulse-mode simulation circuit 61 and/or a root-mean-square-mode simulation circuit 62; wherein,
a pulse mode simulation circuit 61 for simulating reactor nuclear power being less than a predetermined threshold (e.g., 10)-2% FP) the current pulse signal output by the intermediate range detector; the pulse mode analog circuit 61 includes a second optical isolator 611, a second monostable trigger 612, a second n-type attenuation network 613, and a second opto-isolator, a second monostable flip-flop 612, and a second n-type attenuation network 613, which are connected in sequenceA high voltage capacitor 614;
RMS mode simulation circuit 62 for simulating reactor core power being greater than or equal to a predetermined threshold (e.g., 10)-2% FP) the voltage signal output by the intermediate range detector; the rms mode analog circuit 62 includes a third digital-to-analog converter 621, a third low pass filter 622, and a third pi-type attenuation network 623 connected in sequence.
The fission chamber detector signal simulation module 6 uses two modes of operation, including a pulsed mode and a root Mean Square (MSV) mode, as follows:
(1) pulse mode: at this time, the man-machine interaction module 2 generates a signal through the control communication module 9, outputs a pulse signal through the second optical coupling isolator 611, outputs a pulse signal of TTL level through the second monostable trigger 612 with the model number of 74LS123, reduces the amplitude of the pulse through the second n-type attenuation network 613, and finally outputs a current pulse signal through the second high-voltage capacitor 614, wherein the frequency of the current pulse signal is 1Hz to 10MHz, and the pulse width is less than 100 ns.
(2) MSV mode: at this time, the man-machine interaction module 2 generates a signal by controlling the communication module 9, outputs a voltage signal through the third digital-to-analog converter 621, filters a high-frequency signal through the third low-pass filter 622, and finally reduces and outputs the amplitude of the voltage signal through the third n-type attenuation network 623, wherein the voltage of the voltage signal is 160mVrms to 5Vrms, and the bandwidth is 30 +/-5 KHz.
In the embodiment of the invention, the analog quantity module 7 is provided with eight analog quantity output channels and eight analog quantity acquisition channels, and all the channels are mutually isolated by using optical couplers; the temperature drift of the analog quantity module 7 is less than or equal to 100 ppm/DEG C, and the analog quantity module has surge and electrostatic discharge protection functions.
The analog quantity module 7 is provided with an AI/AO interface; wherein, the AI interface has eight analog quantity acquisition channels, the voltage range is [0, 10] V, the precision is 0.1%, and the sampling rate is 125 ksps; the current range is [4, 20] mA, the precision is 0.1%, and the sampling rate is 125 ksps; the AO interface is provided with eight analog quantity output channels, each channel can be configured with output current or output voltage according to requirements, the voltage range is [0, 10] V, the precision is 0.1%, and the updating speed is 125ksps full-scale range; the current range is [4, 20] mA, the precision is 0.1%, and the updating speed is 125ksps full-scale.
In the embodiment of the invention, the digital quantity module 8 is provided with sixteen digital quantity output channels and sixteen digital quantity acquisition channels, and all the channels are mutually isolated by using optical couplers; the digital value module 8 has surge and electrostatic discharge protection functions.
The digital quantity module 8 has a DI/DO interface; the DI interface is provided with sixteen digital quantity acquisition channels, so that digital quantity signals can be processed and then transmitted to the control communication module 9 through a bus of the backboard 1, and 15V bias voltage can be provided; and the DO interface is provided with sixteen digital quantity output channels, transmits the bus switching value to the relay output board card, provides the real-time state of the switching value through a readback circuit, and provides the self-check of each digital quantity output channel.
The embodiment of the invention has the following beneficial effects:
1. the invention adopts a modular design, can be integrated in a portable case, and has the advantages of easy portability, simple installation process, low maintenance cost and the like;
2. the invention not only simulates the output signals of different types of neutron detectors of the RPN in the periods of starting, stopping and stable operation of the nuclear power station, provides check signals for research and development, equipment operation and maintenance, fault diagnosis and the like of the RPN system under laboratory conditions and in the field environment of the power plant, but also simulates signals of analog quantity, switching value and the like of other systems related to the RPN, and provides technical means for equipment debugging, logic function inspection and fault detection of the RPN system. .
While the invention has been described in connection with what is presently considered to be the most practical and preferred embodiment, it is to be understood that the invention is not to be limited to the disclosed embodiment, but on the contrary, is intended to cover various modifications and equivalent arrangements included within the spirit and scope of the appended claims.
Claims (10)
1. A portable neutron detector signal dynamic simulation device is characterized by comprising a back plate, a human-computer interaction module, a boron proportional counter tube detector signal simulation module, a compensation ionization chamber detector signal simulation module, a long ionization chamber detector signal simulation module, a fission chamber detector signal simulation module, an analog quantity module, a digital quantity module and a control communication module, wherein the human-computer interaction module, the boron proportional counter tube detector signal simulation module, the compensation ionization chamber detector signal simulation module, the long ionization chamber detector signal simulation module, the fission chamber detector signal simulation module, the analog quantity module, the digital quantity module and the control; wherein,
the man-machine interaction module is used for acquiring user input data and correspondingly allocating the acquired user input data to the boron proportional counter tube detector signal simulation module, the compensation ionization chamber detector signal simulation module, the long ionization chamber detector signal simulation module, the fission chamber detector signal simulation module, the analog quantity module and the digital quantity module;
the boron proportional counter tube detector signal simulation module is used for simulating a voltage pulse periodic signal or a voltage pulse constant value signal output by the source range detector when the neutron flux is positioned in a first preset variation range during the shutdown period and the startup initial stage of the reactor according to corresponding data distributed by the human-computer interaction module;
the compensation ionization chamber detector signal simulation module is used for simulating a current periodic signal or a current constant value signal output by the middle-range detector when the neutron flux is within a second preset variation range from the critical stage of the reactor to the 10% Pn stage of the rated power according to corresponding data distributed by the man-machine interaction module;
the long ionization chamber detector signal simulation module is used for simulating a current constant value signal output by the power range detector when the neutron flux of the upper half part and the lower half part of the reactor core of the reactor is positioned in a third preset variation range according to corresponding data distributed by the human-computer interaction module;
the fission chamber detector signal simulation module is used for simulating a current pulse signal output by the intermediate range detector when the nuclear power of the reactor is smaller than a preset threshold value and/or a voltage signal output by the intermediate range detector when the nuclear power of the reactor is larger than or equal to the preset threshold value according to corresponding data distributed by the man-machine interaction module;
the analog quantity module is used for correspondingly simulating and generating an analog quantity signal outside the RPN according to the corresponding data distributed by the human-computer interaction module, and carrying out data acquisition, functional operation and interface communication with an external system related to the RPN;
the digital quantity module is used for correspondingly simulating and generating digital quantity signals outside the RPN according to the corresponding data distributed by the human-computer interaction module, and carrying out data acquisition, functional operation and interface communication with an external system related to the RPN;
and the control communication module is used for controlling data exchange and transmission among the modules in the device.
2. The apparatus of claim 1, wherein the boron proportional counter tube detector signal simulation module comprises a first opto-isolator, a first monostable trigger, a first n-type attenuation network, and a first high voltage capacitor connected in sequence.
3. The apparatus of claim 1, wherein the compensated ionization chamber detector signal emulation module comprises a first digital-to-analog converter, a first low pass filter, and a first voltage/current converter comprised of an operational amplifier connected in series.
4. The apparatus of claim 1 wherein said long ionospheric detector signal simulation module is comprised of six identical current-fixed signal simulation circuits, three of said six current-fixed signal simulation circuits being for simulating the upper reactor core half and the other three of said six current-fixed signal simulation circuits being for simulating the lower reactor core half; each current constant value signal analog circuit comprises a second digital-to-analog converter, a second low-pass filter and a second voltage/current converter formed by an operational amplifier which are connected in sequence.
5. The apparatus of claim 1, wherein said fission-chamber detector signal simulation module includes a pulse-mode analog circuit and/or a root-mean-square-mode analog circuit; wherein,
the pulse mode analog circuit is used for simulating a current pulse signal output by the intermediate range detector when the nuclear power of the reactor is smaller than the preset threshold value; the pulse mode analog circuit comprises a second optical coupler isolator, a second monostable trigger, a second n-shaped attenuation network and a second high-voltage capacitor which are sequentially connected;
the root-mean-square mode analog circuit is used for simulating a voltage signal output by the intermediate range detector when the nuclear power of the reactor is greater than or equal to the preset threshold value; the RMS mode analog circuit comprises a third digital-to-analog converter, a third low-pass filter and a third n-type attenuation network which are connected in sequence.
6. The device of claim 1, wherein the analog quantity module is provided with eight analog quantity output channels and eight analog quantity acquisition channels, and the channels are mutually isolated by using optical couplers; the temperature drift of the analog quantity module is less than or equal to 100ppm/° C, and the analog quantity module has surge and electrostatic discharge protection functions.
7. The apparatus of claim 1, wherein the digital quantity module has sixteen digital quantity output channels and sixteen digital quantity acquisition channels, and the channels are isolated from each other by using optical couplers; the digital quantity module has surge and electrostatic discharge protection functions.
8. The apparatus of claim 1, wherein the first predetermined range of variation is [10 ]-1n/cm2·s，2*105n/cm2·s](ii) a The second preset variation range is [2 x 10]2n/cm2·s，5*1010n/cm2·s](ii) a The third preset variation range is [5 x 10]2n/cm2·s，5*1010n/cm2·s]。
9. The apparatus of claim 1, wherein the predetermined threshold is 10 of the full reactor power-2%。
10. The device of any one of claims 1-9, wherein the backplane, the human-computer interaction module, the boron proportional counter detector signal simulation module, the compensated ionization chamber detector signal simulation module, the long ionization chamber detector signal simulation module, the fission chamber detector signal simulation module, the analog quantity module, the digital quantity module and the control communication module are all built in a portable case and are all integrated circuit boards; the boron proportional counter tube detector signal simulation module, the compensation ionization chamber detector signal simulation module, the long ionization chamber detector signal simulation module, the fission chamber detector signal simulation module, the analog quantity module, the digital quantity module and the control communication module can be installed on the back plate in a hot-plug mode.
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