CN114265104A - Neutron critical monitoring system and method - Google Patents
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Abstract
The invention provides a neutron critical monitoring system and a method, the system comprises a control system and a neutron critical detector, the neutron critical detector comprises a probe and a signal processing system, the probe is used for detecting neutrons emitted by radioactive substances and converting the neutrons into pulse signals, the signal processing system is used for receiving the pulse signals output by the probe and amplifying, discriminating, counting and calculating the pulse signals to obtain dose rates of the radioactive substances corresponding to the neutrons in a set energy interval and generate dose rate communication signals, and the control system is used for receiving and displaying the dose rate communication signals transmitted by a plurality of neutron critical detectors. The dosage rate communication signal formed by the detector can be transmitted to the control system through the RS485 bus to be processed in time, and no external interference or signal attenuation exists in the transmission process, so that the false alarm phenomenon caused by inaccurate measured data is avoided, and the safety of normal production and personnel is guaranteed.
Description
Technical Field
The invention particularly relates to a neutron critical monitoring system and a method.
Background
There is a potential risk of nuclear-critical accidents occurring during handling, application, storage and transport of fissionable materials, and although the probability of an accident is small, once it occurs, the resulting hazard is enormous. The neutron critical monitoring alarm system can give an alarm before a critical accident occurs, record the radiation and change process of an accident site and analyze the critical accident process.
Because the detector of the neutron critical monitoring alarm system is installed in a spent fuel processing place, a detected pulse signal needs to be transmitted to the alarm system for processing through a long distance, and factors such as attenuation and external interference exist in the long-distance transmission process of the pulse signal, the inaccurate measured data is easily caused, and false alarm is caused.
Disclosure of Invention
The invention aims to solve the technical problem of providing a neutron critical monitoring system for preventing false alarm and a neutron critical monitoring method correspondingly aiming at the defects in the prior art.
The technical scheme adopted for solving the technical problem of the invention is as follows:
the invention provides a neutron critical monitoring system, which comprises a control system and a neutron critical detector,
the neutron critical detectors are provided with a plurality of neutron critical detectors, each neutron critical detector comprises a probe and a signal processing system,
the probe is used for detecting neutrons emitted by the radioactive substances and converting the neutrons into pulse signals,
the signal processing system is electrically connected with the probe and is used for receiving the pulse signals output by the probe, amplifying, discriminating, counting and calculating the pulse signals to obtain the dose rate of the radioactive substances corresponding to the neutrons in a set energy interval and generate dose rate communication signals,
the control system is electrically connected with the signal processing systems of the neutron critical detectors, is used for receiving the dose rate communication signals transmitted by the signal processing systems of the neutron critical detectors, displays the dose rate communication signals, and is also used for sending parameter setting instructions to the signal processing systems of the neutron critical detectors.
Optionally, the signal processing system of the neutron critical detector is further configured to determine whether the dose rate of the radioactive substance is greater than or equal to the alert dose rate stored therein, and when the determination result is "yes", generate a first alarm switch signal,
the control system is also used for judging the number of the received first alarm switch signals, and outputting second alarm switch signals when the number of the first alarm switch signals is larger than a set value.
Optionally, the signal processing system comprises a signal conversion module, a data processing module and a communication module, the probe, the signal conversion module, the data processing module and the communication module are electrically connected in sequence,
the signal conversion module is used for receiving the pulse signals output by the probe, amplifying, screening and counting the pulse signals to obtain pulse count values within preset upper threshold and lower threshold ranges, and sending the pulse count values to the data processing module,
the data processing module is used for calculating the dose rate of the radioactive substance corresponding to the pulse count value according to the relation between the pulse count value and the dose rate of the radioactive substance stored in the data processing module so as to generate a dose rate communication signal,
the communication module is electrically connected with the control system through a bus and is used for transmitting the dosage rate communication signal to the control system through the bus.
Optionally, the data processing module is further configured to determine whether the dose rate of the radioactive substance is greater than or equal to an alert dose rate stored therein, and generate a first alarm switch signal when the determination result is "yes",
the signal processing system further comprises a first switching value output module, wherein the first switching value output module is electrically connected with the data processing module, is electrically connected with the control system through a bus and is used for transmitting a first alarm switching signal to the control system through the bus.
Optionally, the data processing module adopts an FPGA chip, and the communication module is an RS485 communication interface.
Optionally, the signal conversion module comprises a signal amplification circuit and a signal screening circuit,
the signal amplifying circuit is connected with the probe and is used for receiving, amplifying and shaping the pulse signal output by the probe,
the signal screening circuit is electrically connected with the signal amplification circuit and the data processing module and is used for screening the pulse signals processed by the signal amplification circuit to obtain the pulse signals within a preset upper threshold value range and a preset lower threshold value range, counting the pulse signals within the range to obtain the number of pulses within the range and sending the number of pulses to the data processing module.
Optionally, the control system comprises a signal switching module, a control processing module, a second switching value output module, an operation display module and an alarm device,
the signal switching module is electrically connected with the signal processing systems of the neutron critical detectors and is used for receiving the communication signals and the first alarm switch signals transmitted by the neutron critical detectors and carrying out level standardization conversion,
the control processing module is electrically connected with the signal switching module and the operation display module and is used for receiving the communication signals switched by the signal switching module and driving the operation display module to display,
and the second switching value output module is electrically connected with the signal switching module and the alarm device and is used for judging the number of the received first alarm switching signals and outputting second alarm switching signals to trigger the alarm device to alarm when the number of the first alarm switching signals is greater than a set value.
Optionally, an RS485 communication interface and a network port are integrated in the second switching value output module, and are used for performing communication data interaction between the system and the radiation monitoring platform.
Optionally, the control system further includes a power supply module, which is electrically connected to the control processing module and is configured to convert an external power supply into a supply voltage required by components in the system;
the signal processing system further comprises a power management module and a high voltage converter,
the power management module is electrically connected with the data processing module and the high-voltage converter and used for transmitting the power supply voltage of the system to the high-voltage converter, and the high-voltage converter is used for converting the system power consumption input by the power management module into direct current high voltage used by the probe.
The invention also provides a neutron critical monitoring method, which comprises the following steps:
the neutron critical detectors are provided with a plurality of neutron critical detectors, each neutron critical detector comprises a probe and a signal processing system,
the probe of the neutron critical detector detects neutrons emitted by the radioactive substance and converts the neutrons into pulse signals,
a signal processing system of the neutron critical detector receives the pulse signal output by the probe, and performs amplification, discrimination, counting and calculation processing on the pulse signal to obtain the dose rate of the radioactive substance corresponding to the neutron in a set energy interval and generate a dose rate communication signal,
the control system receives the dose rate communication signals transmitted by the signal processing systems of the neutron critical detectors, displays the dose rate communication signals, and sends parameter setting instructions to the signal processing systems of the neutron critical detectors.
Optionally, the method further comprises:
the signal processing system of the neutron critical detector judges whether the dosage rate of the radioactive substance is more than or equal to the warning dosage rate stored in the signal processing system, when the judgment result is 'yes', a first alarm switch signal is generated,
the control system judges the number of the received first alarm switch signals, and outputs second alarm switch signals when the number of the first alarm switch signals is larger than a set value.
According to the invention, the signal processing system is integrated in the detector, pulse signals detected by the probe are sequentially amplified, discriminated, counted and calculated by the signal processing system, the formed dose rate communication signals can be transmitted to the control system for timely processing through RS485 bus digital signals, the transmission distance can reach 1200 meters, and the problems of external interference and signal attenuation do not exist in the transmission process, so that the false alarm phenomenon caused by inaccurate measured data is avoided, and the normal production and personnel safety are ensured.
Drawings
Fig. 1 is a schematic structural diagram of a neutron critical monitoring system provided in embodiment 1 of the present invention;
fig. 2 is a schematic structural diagram of a neutron critical detector provided in embodiment 1 of the present invention. In the figure: 1. a neutron critical detector; 11. a probe; 12. a data processing module; 13. a communication module; 14. a first switching value output module; 15. a signal amplification circuit; 16. a signal discrimination circuit; 17. a power management module; 18. a high voltage converter; 2. a control system; 21. a signal transfer module; 22. a control processing module; 23. a second switching value output module; 24. an operation display module; 25. an alarm device; 26. and a power supply module.
Detailed Description
The technical solutions in the present invention will be described clearly and completely with reference to the accompanying drawings, and it is obvious that the described embodiments are some, but not all embodiments of the present invention. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the scope of the present invention.
In the description of the present invention, it should be noted that the indication of orientation or positional relationship, such as "on" or the like, is based on the orientation or positional relationship shown in the drawings, and is only for convenience and simplicity of description, and does not indicate or imply that the device or element referred to must be provided with a specific orientation, constructed and operated in a specific orientation, and thus, should not be construed as limiting the present invention.
In the description of the present invention, the terms "first" and "second" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.
In the description of the present invention, it is to be noted that, unless otherwise explicitly specified or limited, the terms "connected," "disposed," "mounted," "fixed," and the like are to be construed broadly, e.g., as being fixedly or removably connected, or integrally connected; either directly or indirectly through intervening media, or may be interconnected between two elements. The specific meaning of the above terms in the present invention can be understood in specific cases for those skilled in the art.
The invention provides a neutron critical monitoring system, which comprises a control system and a neutron critical detector,
the neutron critical detectors are provided with a plurality of neutron critical detectors, each neutron critical detector comprises a probe and a signal processing system,
the probe is used for detecting neutrons emitted by the radioactive substances and converting the neutrons into pulse signals,
the signal processing system is electrically connected with the probe and is used for receiving the pulse signals output by the probe, amplifying, discriminating, counting and calculating the pulse signals to obtain the dose rate of the radioactive substances corresponding to the neutrons in a set energy interval and generate dose rate communication signals,
the control system is electrically connected with the signal processing systems of the neutron critical detectors, is used for receiving the dose rate communication signals transmitted by the signal processing systems of the neutron critical detectors, displays the dose rate communication signals, and is also used for sending parameter setting instructions to the signal processing systems of the neutron critical detectors.
The invention also provides a neutron critical monitoring method, which comprises the following steps:
the neutron critical detectors are provided with a plurality of neutron critical detectors, each neutron critical detector comprises a probe and a signal processing system,
the probe of the neutron critical detector detects neutrons emitted by the radioactive substance and converts the neutrons into pulse signals,
a signal processing system of the neutron critical detector receives the pulse signal output by the probe, and performs amplification, discrimination, counting and calculation processing on the pulse signal to obtain the dose rate of the radioactive substance corresponding to the neutron in a set energy interval and generate a dose rate communication signal,
the control system receives the dose rate communication signals transmitted by the signal processing systems of the neutron critical detectors, displays the dose rate communication signals, and sends parameter setting instructions to the signal processing systems of the neutron critical detectors.
Example 1:
as shown in fig. 1, the present embodiment provides a neutron critical monitoring system, which includes a control system 2 and a neutron critical detector 1,
the neutron critical detector 1 is provided with a plurality of neutron critical detectors 1, each neutron critical detector 1 comprises a probe 11 and a signal processing system,
the probe 11 is used for detecting neutrons emitted by the radioactive substance, converting the neutrons into pulse signals,
the signal processing system is electrically connected with the probe 11 and is used for receiving the pulse signal output by the probe 11, amplifying, discriminating, counting and calculating the pulse signal to obtain the dose rate of the radioactive substance corresponding to the neutron in the set energy interval and generate a dose rate communication signal,
the control system 2 is electrically connected with the signal processing systems of the neutron critical detectors 1, and is configured to receive and display the dose rate communication signals transmitted by the signal processing systems of the neutron critical detectors 1, and further configured to send a parameter setting instruction to the signal processing system of the neutron critical detector 1.
Therefore, by integrating the signal processing system in the neutron critical detector 1, the pulse signals detected by the probe 11 are sequentially amplified, screened, counted and calculated by the signal processing system, the formed dosage rate communication signals can be transmitted to the control system 2 through the RS485 bus digital signals to be processed in time, the transmission distance can reach 1200 meters, and the problems of external interference and signal attenuation do not exist in the transmission process, so that the false alarm phenomenon caused by inaccurate measured data is avoided, and the safety of normal production and personnel is guaranteed.
The neutron critical detectors 1 are distributed at different places and form a neutron critical monitoring system with the control system 2, so that monitoring of critical accidents achieves better reliability.
In this embodiment, the signal processing system of the neutron critical detector 1 is further configured to determine whether the dose rate of the radioactive substance is greater than or equal to the alert dose rate stored therein, and when the determination result is "yes", generate a first alarm switch signal,
the control system 2 is further configured to determine the number of the received first alarm switch signals, and output a second alarm switch signal when the number of the first alarm switch signals is greater than a set value.
Therefore, the alarm switch signal generated by the signal processing system integrated in the neutron critical detector 1 through judgment can also be transmitted to the control system 2 through the RS485 bus digital signal, so that the control system 2 can quickly send out the alarm signal without processing data.
And the control system 2 is used for logically judging the alarm signals of the neutron critical detectors 1 at different positions so as to avoid the alarm phenomenon caused by false alarm of the individual neutron critical detectors 1.
In the present embodiment, the first and second electrodes are,
the signal processing system comprises a signal conversion module, a data processing module 12 and a communication module 13, the probe 11, the signal conversion module, the data processing module 12 and the communication module 13 are electrically connected in sequence,
the signal conversion module is used for receiving the pulse signal output by the probe 11, amplifying, discriminating and counting the pulse signal to obtain a pulse count value within a preset upper threshold and a preset lower threshold, and sending the pulse count value to the data processing module 12,
the data processing module 12 is configured to calculate a dose rate of the radioactive substance corresponding to the pulse count value according to a relationship between the pulse count value and the dose rate of the radioactive substance stored therein, so as to generate a dose rate communication signal,
the communication module 13 is electrically connected to the control system 2 through a bus, and is configured to transmit the dose rate communication signal to the control system 2 through the bus.
In the present embodiment, the first and second electrodes are,
the data processing module 12 is further configured to determine whether the dose rate of the radioactive substance is greater than or equal to the alert dose rate stored therein, and when the determination result is "yes", generate a first alarm switch signal,
in addition, the data processing module is also used for receiving and analyzing the instruction for parameter setting of each module sent by the control system through the communication module, executing the corresponding instruction to complete setting of the corresponding parameter, and storing each parameter and the calculated dose rate.
The data processing module stores the received parameters separately and locally so as to read the parameters directly after being powered on, thereby avoiding repeated parameter instruction receiving.
The signal processing system further comprises a first switching value output module 14, wherein the first switching value output module 14 is electrically connected with the data processing module 12, electrically connected with the control system 2 through a bus, and used for transmitting a first alarm switching signal to the control system 2 through the bus.
In this embodiment, the signal conversion module includes a signal amplification circuit 15 and a signal discrimination circuit 16,
the signal amplifying circuit 15 is connected with the probe 11 and is used for receiving, amplifying and shaping the pulse signal output by the probe 11,
the signal discrimination circuit 16 is electrically connected to the signal amplification circuit 15 and the data processing module 12, and is configured to discriminate the pulse signal processed by the signal amplification circuit 15 to obtain a pulse signal within a preset upper threshold and a preset lower threshold, and count the pulse signal within the preset upper threshold and the preset lower threshold to obtain the number of pulses within the preset upper threshold and send the number of pulses to the data processing module 12.
Specifically, the signal screening circuit 16 includes a discriminator and a count acquisition circuit.
The discriminator comprises an upper discriminator and a lower discriminator, the input ends of the upper discriminator and the lower discriminator are respectively connected with the output end of the signal amplification circuit 15, the upper discriminator is used for comparing each pulse value in the pulse signal with a preset upper threshold value, and outputting a high level signal when the pulse value is higher than the upper threshold value, and outputting a low level signal when the pulse value is lower than or equal to the upper threshold value; the lower discriminator is used for comparing each pulse value in the pulse signals with a preset lower threshold value, and outputting high level signals when the pulse values are higher than or equal to the lower threshold value, and outputting low level signals when the pulse values are lower than the lower threshold value.
The counting acquisition circuit comprises an exclusive-OR gate circuit and a timing counter;
the input end of the exclusive-OR gate circuit is respectively connected with the upper discriminator and the lower discriminator, and the exclusive-OR gate circuit is used for carrying out exclusive-OR processing on the outputs of the upper discriminator and the lower discriminator so as to obtain a discriminated digital level signal;
the input end of the timing counter is connected with the output end of the exclusive-or gate circuit, and is used for collecting the number of pulses in the corresponding screened digital level signal and sending the count value to the data processing module 12.
In this embodiment, the data processing module 12 adopts an FPGA chip, and the communication module 13 is an RS485 interface circuit.
The probe part comprises 2-channel neutron BF3In a proportional counter, the probe 11 outputs a minute pulse in the millivolt range under normal operation. Pulses output by the probe are processed by a signal amplification circuit 15 (specifically, a three-stage amplification and shaping comparison circuit) to be TTL level signals, and are sent to an FPGA chip to complete calculation processing such as millisecond counting and second counting, and are converted into corresponding dose rates according to a formula. And the FPGA chip also compares the millisecond-level counting and the dosage rate result with the set warning dosage rate respectively to acquire an alarm state. IntelligenceThe probe part selects an XC7A100TFGG484-2L industrial-grade FPGA chip of American Xilinx company as a main controller, integrates a large number of embedded blocks and abundant logic resources on the chip, and has the advantages of high cost performance, low power consumption, small package and the like.
Therefore, the signal processing system of the neutron critical detector 1 adopts a hardware architecture based on the FPGA technology to realize main control and communication functions, and the stable operation of the system does not depend on a microprocessor and software.
The hardware architecture based on the FPGA technology has the following advantages:
certainty: the FPGA chip realizes the designed safety function in a pure hardware circuit mode, and the execution of the hardware circuit is more definite than the execution of software and an operating system.
Reliability: the FPGA chip based on the FLASH and the FPGA chip based on the anti-fuse technology can effectively resist single event upset caused by random irradiation, so that the FPGA chip has higher reliability compared with a CPU chip.
Security: the FPGA technology provides better protection against network malicious attacks. Firstly, the hardware logic burned into the FPGA chip cannot be modified randomly without an engineering tool; secondly, the modification of the hardware logic needs to be carried out through a special interface, and the interface is generally disconnected when the system runs; finally, the hardware logic adopts encryption measures to make the FPGA logic difficult to reproduce through reverse engineering.
The performance is that the response time depends not only on the logic processing time but also on the signal processing time and the communication time. The parallel processing mode adopted by the internal hardware logic of the FPGA chip has higher processing speed than the serial processing mode of the software code in the CPU chip. In addition, the FPGA-based intelligent probe processes input and output signals in parallel, and the execution time of the FPGA-based intelligent probe is not limited by the data refresh rate in a periodic or regular mode. The input and output signals of the device can be processed simultaneously, and when the system scale is increased, the parallel processing mode does not increase the time required for inputting and outputting the signals.
Sustainability and economy: the CPU chip is updated faster than the FPGA chip, which means that the service life of the probe based on the CPU technology is shorter than that of the intelligent probe based on the FPGA technology. With the updating and upgrading of the CPU chip, the existing software codes in the original CPU chip are difficult to be transplanted to the CPU chip of the new generation. On the contrary, the FPGA technology makes the system upgrade easier in the future. FPGA logic code and register level design programmed using a hardware description language can be migrated to a new FPGA chip that requires only new synthesis and layout wiring of existing code and new software tools used by the design, and the previous investment in software design can be retained to the maximum extent.
In this embodiment, the control system 2 includes a signal switching module 21, a control processing module 22, a second switching value output module 23, an operation display module 24 and an alarm device 25,
the signal switching module 21 is electrically connected with the signal processing systems of the neutron critical detectors 1, and is used for receiving the communication signal and the first alarm switch signal transmitted by the neutron critical detector 1, performing level standardization conversion,
the control processing module 22 is electrically connected to the signal switching module 21 and the operation display module 24, and is configured to receive the communication signal switched by the signal switching module 21, and drive the operation display module 24 to display,
the second switching value output module 23 is electrically connected to the signal switching module 21 and the alarm device 25, and is configured to determine the number of the received first alarm switch signals, and output a second alarm switch signal to trigger the alarm device 25 to alarm when the number of the first alarm switch signals is greater than a set value.
In this embodiment, there are three neutron critical detectors 1, and each neutron critical detector 1 and the signal switching module 21 perform simplex mode data interaction through two RS485 channels, so as to upload measurement data of the neutron critical detector 1 and receive and respond to an operation instruction.
In the present embodiment, the first and second electrodes are,
the control system 2 further comprises a power supply module 26, wherein the power supply module 26 is electrically connected with the control processing module 22 and is used for converting an external power supply into a power supply voltage required by components in the system;
the signal processing system further comprises a power management module 17 and a high voltage converter 18,
the power management module 17 is electrically connected to the data processing module 12 and the high voltage converter 18, and is configured to transmit the power supply voltage of the system to the high voltage converter 18, and the high voltage converter 18 is configured to convert the system power input by the power management module 17 into a dc high voltage used by the probe 11.
Specifically, the signal switching module 21 provides +24V dc voltage for the intelligent probe through the cable. The power management module 17 takes +24V voltage as input of the high voltage converter 18, and the high voltage converter 18 outputs high voltage to supply power to the probe after voltage conversion.
The specific functions of the modules in the control system 2 are as follows:
the signal switching module: the signal switching module 21 is connected with the three independent neutron critical detectors 1, receives the RS485 signal and the alarm switching value signal transmitted by the detectors, and all signals of interaction of the intelligent probe and the signal switching module need to be subjected to electric optical coupling isolation processing, so that on one hand, the anti-interference performance between the modules is improved, and meanwhile, the level standard conversion between the modules is realized. Meanwhile, the signal switching module 21 provides +24V dc voltage for the intelligent probe through a cable.
The control processing module: and driving the liquid crystal display screen to display a three-channel data result in real time according to the measurement data uploaded by the three-channel neutron critical detector 1. The control processing module 22 controls the interactive operation between the 4x4 keyboard and the liquid crystal display screen to complete the issuing of various functional instructions and data query. The control processing module 22 is responsible for controlling the hardware communication interface signals of the serial port and the network port of the second switching value output module 23 and simultaneously controlling the front panel LED status indicator lamp of the case.
The second switching value output module: the second switching value output module 23 performs processing of taking 2 out of 3 on the alarm signal transmitted by the signal switching module, and finally outputs a redundant alarm state to the alarm lamp whistle group in a switching value mode. The output module integrates two RS485 and 1 network ports and performs communication data interaction with the radiation monitoring platform.
Alarm lamp flute: the alarm whistle is the alarm device who comprises a plurality of red light green light whistle, and the red light sends red signal, and green light is normal signal indication for work, sends sound signal when the flute is reported to the police.
A power supply module: the power module 26 converts the 220VAC power supply to +24 DC voltage for use by the device for powering the system.
An operation display module: the operation display module 24 mainly includes a keyboard and a liquid crystal display. The keyboard is used for data input and interface switching. The display screen is used for displaying the graphic data. The operation display module inputs data through a keyboard, and the data is transmitted to the control processing module through an interface bus.
In this embodiment, the control system 2 is disposed in a chassis, and two sets of control system 2 devices are disposed in a set of standard NIM chassis.
Example 2:
the present embodiment provides a method for performing neutron criticality monitoring using the system of embodiment 1, including:
the probe 11 of the neutron critical detector 1 detects neutrons emitted by radioactive substances, converts the neutrons into pulse signals,
the signal processing system of the neutron critical detector 1 receives the pulse signal output by the probe 11, and performs amplification, discrimination, counting and calculation processing on the pulse signal to obtain the dose rate of the radioactive substance corresponding to the neutron in the set energy interval and generate a dose rate communication signal,
the control system 2 receives the dose rate communication signals transmitted by the signal processing systems of the neutron critical detectors 1, displays the dose rate communication signals, and sends parameter setting instructions to the signal processing systems of the neutron critical detectors 1.
In this embodiment, the method further includes:
the signal processing system of the neutron critical detector 1 judges whether the dosage rate of the radioactive substance is larger than or equal to the warning dosage rate stored in the signal processing system, when the judgment result is 'yes', a first alarm switch signal is generated,
the control system 2 judges the number of the received first alarm switch signals, and outputs second alarm switch signals when the number of the first alarm switch signals is larger than a set value.
It will be understood that the above embodiments are merely exemplary embodiments taken to illustrate the principles of the present invention, which is not limited thereto. It will be apparent to those skilled in the art that various modifications and improvements can be made without departing from the spirit and substance of the invention, and these modifications and improvements are also considered to be within the scope of the invention.
Claims (10)
1. A neutron critical monitoring system is characterized by comprising a control system (2) and a neutron critical detector (1),
the neutron critical detector (1) is provided with a plurality of neutron critical detectors, the neutron critical detector (1) comprises a probe (11) and a signal processing system,
the probe (11) is used for detecting neutrons emitted by the radioactive substances and converting the neutrons into pulse signals,
the signal processing system is electrically connected with the probe (11) and is used for receiving the pulse signals output by the probe (11), amplifying, discriminating, counting and calculating the pulse signals to obtain the dose rate of the radioactive substances corresponding to the neutrons in a set energy interval and generate dose rate communication signals,
the control system (2) is electrically connected with the signal processing systems of the neutron critical detectors (1), is used for receiving the dose rate communication signals transmitted by the signal processing systems of the neutron critical detectors (1), displays the dose rate communication signals, and is also used for sending parameter setting instructions to the signal processing systems of the neutron critical detectors (1).
2. The neutron criticality monitoring system of claim 1,
the signal processing system of the neutron critical detector (1) is also used for judging whether the dosage rate of the radioactive substances is more than or equal to the warning dosage rate stored in the signal processing system, when the judgment result is 'yes', a first alarm switch signal is generated,
the control system (2) is also used for judging the number of the received first alarm switch signals, and outputting second alarm switch signals when the number of the first alarm switch signals is larger than a set value.
3. The neutron criticality monitoring system of claim 2,
the signal processing system comprises a signal conversion module, a data processing module (12) and a communication module (13), the probe (11), the signal conversion module, the data processing module (12) and the communication module (13) are electrically connected in sequence,
the signal conversion module is used for receiving the pulse signals output by the probe (11), amplifying, screening and counting the pulse signals to obtain pulse count values within a preset upper threshold value and a preset lower threshold value range, and sending the pulse count values to the data processing module (12),
the data processing module (12) is used for calculating the dose rate of the radioactive substance corresponding to the pulse count value according to the relation between the pulse count value and the dose rate of the radioactive substance stored in the data processing module to generate a dose rate communication signal,
the communication module (13) is electrically connected with the control system (2) through a bus and is used for transmitting the dosage rate communication signal to the control system (2) through the bus.
4. The neutron criticality monitoring system of claim 3,
the data processing module (12) is also used for judging whether the dosage rate of the radioactive substance is more than or equal to the warning dosage rate stored in the data processing module, and when the judgment result is 'yes', a first warning switch signal is generated,
the signal processing system further comprises a first switching value output module (14), wherein the first switching value output module (14) is electrically connected with the data processing module (12) and the control system (2) through a bus and is used for transmitting a first alarm switching signal to the control system (2) through the bus.
5. The neutron critical monitoring system according to claim 3, wherein the data processing module (12) is an FPGA chip, and the communication module (13) is an RS485 communication interface.
6. The neutron threshold monitoring system of claim 3, wherein the signal conversion module includes a signal amplification circuit (15) and a signal discrimination circuit (16),
the signal amplification circuit (15) is connected with the probe (11) and is used for receiving, amplifying and shaping the pulse signal output by the probe (11),
the signal screening circuit (16) is electrically connected with the signal amplification circuit (15) and the data processing module (12) and is used for screening the pulse signals processed by the signal amplification circuit (15) to obtain the pulse signals within a preset upper threshold value range and a preset lower threshold value range, counting the pulse signals within the range to obtain the number of pulses within the range and sending the number of pulses to the data processing module (12).
7. The neutron threshold monitoring system according to any of claims 2-6, characterized in that the control system (2) comprises a signal transfer module (21), a control processing module (22), a second switching value output module (23), an operation display module (24) and an alarm device (25),
the signal switching module (21) is electrically connected with the signal processing systems of the neutron critical detectors (1) and is used for receiving the communication signals and the first alarm switch signals transmitted by the neutron critical detectors (1) and carrying out level standardization conversion,
the control processing module (22) is electrically connected with the signal switching module (21) and the operation display module (24) and is used for receiving the communication signals converted by the signal switching module (21) and driving the operation display module (24) to display,
and the second switching value output module (23) is electrically connected with the signal switching module (21) and the alarm device (25) and is used for judging the number of the received first alarm switching signals, and when the number of the first alarm switching signals is larger than a set value, a second alarm switching signal is output to trigger the alarm device (25) to alarm.
8. The neutron criticality monitoring system of claim 7,
the control system (2) further comprises a power supply module (26), wherein the power supply module (26) is electrically connected with the control processing module (22) and is used for converting an external power supply into power supply voltage required by components in the system;
the signal processing system further comprises a power management module (17) and a high voltage converter (18),
the power management module (17) is electrically connected with the data processing module (12) and the high-voltage converter (18) and is used for transmitting the power supply voltage of the system to the high-voltage converter (18), and the high-voltage converter (18) is used for converting the system power input by the power management module (17) into direct current high voltage used by the probe (11).
9. A method of neutron criticality monitoring, comprising:
the neutron critical detector (1) is provided with a plurality of neutron critical detectors, the neutron critical detector (1) comprises a probe (11) and a signal processing system,
the probe (11) of the neutron critical detector (1) detects neutrons emitted by radioactive substances and converts the neutrons into pulse signals,
a signal processing system of the neutron critical detector (1) receives the pulse signal output by the probe (11), and amplifies, discriminates, counts and calculates the pulse signal to obtain the dose rate of the radioactive substance corresponding to the neutron in a set energy interval and generate a dose rate communication signal,
the control system (2) receives the dose rate communication signals transmitted by the signal processing systems of the neutron critical detectors (1), displays the dose rate communication signals, and sends parameter setting instructions to the signal processing systems of the neutron critical detectors (1).
10. The neutron criticality monitoring method of claim 9, further comprising:
a signal processing system of the neutron critical detector (1) judges whether the dosage rate of the radioactive substance is more than or equal to the warning dosage rate stored in the signal processing system, when the judgment result is 'yes', a first warning switch signal is generated,
the control system (2) judges the number of the received first alarm switch signals, and outputs second alarm switch signals when the number of the first alarm switch signals is larger than a set value.
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Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US20180267174A1 (en) * | 2015-11-13 | 2018-09-20 | Flir Detection, Inc. | Dose rate measurement systems and methods |
JP2019148429A (en) * | 2018-02-26 | 2019-09-05 | 株式会社日立製作所 | Radiation monitor |
CN111366964A (en) * | 2019-12-16 | 2020-07-03 | 中国辐射防护研究院 | Fixed integrated device for monitoring regional gamma neutron radiation |
CN211979212U (en) * | 2019-11-12 | 2020-11-20 | 中核控制系统工程有限公司 | Neutron critical accident monitoring and alarming instrument |
CN112907914A (en) * | 2021-02-09 | 2021-06-04 | 陕西卫峰核电子有限公司 | Nuclear criticality alarm system and alarm method thereof |
CN113281798A (en) * | 2021-03-26 | 2021-08-20 | 中国核电工程有限公司 | Multichannel nuclear electronics data acquisition instrument, system and method |
-
2021
- 2021-12-31 CN CN202111663354.0A patent/CN114265104A/en active Pending
Patent Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US20180267174A1 (en) * | 2015-11-13 | 2018-09-20 | Flir Detection, Inc. | Dose rate measurement systems and methods |
JP2019148429A (en) * | 2018-02-26 | 2019-09-05 | 株式会社日立製作所 | Radiation monitor |
CN211979212U (en) * | 2019-11-12 | 2020-11-20 | 中核控制系统工程有限公司 | Neutron critical accident monitoring and alarming instrument |
CN111366964A (en) * | 2019-12-16 | 2020-07-03 | 中国辐射防护研究院 | Fixed integrated device for monitoring regional gamma neutron radiation |
CN112907914A (en) * | 2021-02-09 | 2021-06-04 | 陕西卫峰核电子有限公司 | Nuclear criticality alarm system and alarm method thereof |
CN113281798A (en) * | 2021-03-26 | 2021-08-20 | 中国核电工程有限公司 | Multichannel nuclear electronics data acquisition instrument, system and method |
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