CN114355427A - Nuclear critical detector and detection method - Google Patents
Nuclear critical detector and detection method Download PDFInfo
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- CN114355427A CN114355427A CN202111676737.1A CN202111676737A CN114355427A CN 114355427 A CN114355427 A CN 114355427A CN 202111676737 A CN202111676737 A CN 202111676737A CN 114355427 A CN114355427 A CN 114355427A
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Abstract
The invention provides a nuclear critical detector and a detection method, the detector comprises a probe and a signal processing system, the signal processing system comprises a signal conversion module, a data processing module and a communication module which are electrically connected in sequence, the probe detects gamma rays emitted by radioactive substances and converts the gamma rays into pulse signals to be output, the signal conversion module converts and counts the pulse signals to obtain pulse counting rates corresponding to the gamma rays in a set energy interval, and the data processing module calculates the dose rate of the radioactive substances corresponding to the pulse counting rates according to a relation between the pulse counting rates and the dose rates of the radioactive substances stored in the data processing module to generate dose rate communication signals and transmits the dose rate communication signals through the communication module. The dose rate communication signal generated by the nuclear critical detector can be transmitted through an RS485 bus, 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.
Description
Technical Field
The invention particularly relates to a nuclear critical detector and a detection 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 nuclear critical monitoring alarm system can give an alarm before a critical accident occurs, record the radiation and change process of the accident site and analyze the critical accident process.
Because the detector of the nuclear critical monitoring alarm system is installed in a spent fuel processing place, a pulse signal detected by the detector needs to be transmitted to the alarm system for processing through a long distance, and factors such as attenuation, external interference and the like 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 technical problem to be solved by the present invention is to provide a nuclear critical detector for avoiding the occurrence of false alarm and a nuclear critical detection method, aiming at the above-mentioned defects existing in the prior art.
The technical scheme adopted for solving the technical problem of the invention is as follows:
the invention provides a nuclear critical detector, comprising: the probe comprises a probe body, a signal processing system and a communication module, wherein the signal processing system comprises a signal conversion module, a data processing module and the communication module which are sequentially and electrically connected,
the probe is used for detecting gamma rays emitted by radioactive substances and converting the gamma rays into pulse signals to be output,
the signal conversion module is used for receiving the pulse signals output by the probe, performing conversion and counting processing on the pulse signals to acquire the pulse counting rate corresponding to the gamma rays in a set energy interval and sending the pulse counting rate to the data processing module,
the data processing module comprises a dose rate calculation module, and the dose rate calculation module is used for calculating the dose rate of the radioactive substance corresponding to the pulse counting rate according to a relation between the pulse counting rate and the dose rate of the radioactive substance stored in the data processing module so as to generate a dose rate communication signal, and the communication module transmits the dose rate communication signal.
Optionally, the signal processing system further comprises an alarm output module, the alarm output module is electrically connected with the data processing module,
the data processing module further comprises a threshold value comparison module, the threshold value comparison module is electrically connected with the dosage rate calculation module and is used for judging whether the dosage rate of the radioactive substance is larger than or equal to the warning dosage rate stored in the dosage rate calculation module, and when the judgment result is 'yes', an alarm switch signal is output and transmitted through the alarm output module.
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 pulse filtering circuit and a pulse counting circuit,
the pulse filter circuit is connected with the probe and is used for receiving the pulse signal output by the probe and filtering out the pulse with the pulse width less than a set value,
the pulse counting circuit is electrically connected with the pulse filter circuit and the data processing module and is used for counting pulse signals processed by the pulse filter circuit so as to obtain the number of pulses in a second period and sending the number of pulses to the data processing module.
Optionally, the signal processing system further comprises a parameter storage module,
the parameter storage module is electrically connected with the communication module and the data processing module and is used for receiving and storing a parameter setting command sent by the remote control system;
the data processing module is further configured to execute the parameter setting command to complete setting of the corresponding parameter, and is further configured to send the calculated dose rate to the parameter storage module for storage.
Optionally, the probe is provided with three, respectively an ionization chamber, a medium dose G-M tube and a low dose G-M tube.
Optionally, the signal processing system further comprises a high voltage detection module, a high voltage switching module and a self-checking control module,
the high-voltage detection module is electrically connected with the communication module and the ionization chamber and is used for receiving a high-voltage detection command sent by the remote control system, detecting a high-voltage signal of the ionization chamber and sending the high-voltage signal to the remote control system through the communication module;
the high-voltage switching module is electrically connected with the communication module and the ionization chamber and is used for receiving a high-voltage switching command sent by the remote control system and controlling a high-voltage switching signal of the ionization chamber;
the input end of the self-checking control module is electrically connected with the communication module, the output end of the self-checking control module is electrically connected with the ionization chamber, the medium-dose G-M tube and the low-dose G-M tube respectively, and the self-checking control module is used for receiving a self-checking control command sent by the remote control system, detecting the equipment function states of the ionization chamber, the medium-dose G-M tube and the low-dose G-M tube, and sending an equipment function state signal to the remote control system through the communication module.
The invention also provides a nuclear critical detection method, which comprises the following steps:
the probe detects the gamma rays emitted by the radioactive substance and converts the gamma rays into pulse signals to be output,
the signal conversion module receives the pulse signal output by the probe, and performs conversion and counting processing on the pulse signal to acquire a pulse counting rate corresponding to the gamma ray in a set energy interval and sends the pulse counting rate to the data processing module,
and a dosage rate calculation module of the data processing module calculates the dosage rate of the radioactive substance corresponding to the pulse counting rate according to a relation between the pulse counting rate and the dosage rate of the radioactive substance stored in the data processing module so as to generate a dosage rate communication signal, and transmits the dosage rate communication signal through the communication module.
Optionally, the method further comprises:
and the threshold comparison module of the data processing module judges whether the dosage rate of the radioactive substance is greater than or equal to the warning dosage rate stored in the data processing module, and when the judgment result is yes, an alarm switch signal is output and transmitted through the alarm output module.
Optionally, the method further comprises: the signal conversion module comprises a pulse filter circuit and a pulse counting circuit,
the pulse filter circuit receives the pulse signal output by the probe and filters out the pulse with the pulse width less than a set value,
the pulse counting circuit counts the pulse signals processed by the pulse filtering circuit to obtain the number of pulses in a second period, and sends the number of pulses to the data processing module.
According to the invention, a signal processing system consisting of a signal conversion module, a data processing module and a communication module is integrated in the detector, pulse signals detected by the probe sequentially pass through a filter plate, counting and calculation, formed dosage rate communication signals can be transmitted 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 nuclear critical detector provided in embodiment 1 of the present invention.
In the figure: 1. a probe; 2. a data processing module; 3. a communication module; 4. a switching value output module; 5. a pulse filter circuit; 6. a pulse counting circuit; 7. a parameter storage module; 8. a high voltage detection module; 9. a high voltage switching module; 10. and the self-checking control 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 nuclear critical detector, comprising: the probe comprises a probe body, a signal processing system and a communication module, wherein the signal processing system comprises a signal conversion module, a data processing module and the communication module which are sequentially and electrically connected,
the probe is used for detecting gamma rays emitted by radioactive substances and converting the gamma rays into pulse signals to be output,
the signal conversion module is used for receiving the pulse signals output by the probe, performing conversion and counting processing on the pulse signals to acquire the pulse counting rate corresponding to the gamma rays in a set energy interval and sending the pulse counting rate to the data processing module,
the data processing module comprises a dose rate calculation module, and the dose rate calculation module is used for calculating the dose rate of the radioactive substance corresponding to the pulse counting rate according to a relation between the pulse counting rate and the dose rate of the radioactive substance stored in the data processing module so as to generate a dose rate communication signal, and the communication module transmits the dose rate communication signal.
The invention also provides a neutron critical detection method, which comprises the following steps:
the probe detects the gamma rays emitted by the radioactive substance and converts the gamma rays into pulse signals to be output,
the signal conversion module receives the pulse signal output by the probe, and performs conversion and counting processing on the pulse signal to acquire a pulse counting rate corresponding to the gamma ray in a set energy interval and sends the pulse counting rate to the data processing module,
and a dosage rate calculation module of the data processing module calculates the dosage rate of the radioactive substance corresponding to the pulse counting rate according to a relation between the pulse counting rate and the dosage rate of the radioactive substance stored in the data processing module so as to generate a dosage rate communication signal, and transmits the dosage rate communication signal through the communication module.
Example 1:
as shown in fig. 1, the present embodiment provides a nuclear critical detector, including: the probe 1 and the signal processing system, the signal processing system comprises a signal conversion module, a data processing module 2 and a communication module 3, the probe 1, the signal conversion module, the data processing module 2 and the communication module 3 are electrically connected in sequence,
the probe 1 is used for detecting gamma rays emitted by radioactive substances, converting the gamma rays into pulse signals and outputting the pulse signals,
the signal conversion module is used for receiving the pulse signal output by the probe 1, performing conversion and counting processing on the pulse signal to acquire a pulse counting rate corresponding to the gamma ray in a set energy interval, sending the pulse counting rate to the data processing module 2,
the data processing module 2 comprises a dose rate calculation module 21, and the dose rate calculation module 21 is configured to calculate a dose rate of the radioactive substance corresponding to the pulse count rate according to a relationship between the pulse count rate and the dose rate of the radioactive substance stored in the data processing module 21, so as to generate a dose rate communication signal, and transmit the dose rate communication signal through the communication module 3.
From this, through the signal processing system who integrates signal conversion module in the detector, data processing module 2 and communication module 3 are constituteed, the pulse signal that probe 1 detected is in proper order through conversion, count and calculation, the dose rate communication signal that forms can pass through RS485 bus digital signal transmission, if transmit and judge for remote control system dose rate, transmission distance can reach 1200 meters, and there is not external disturbance and signal attenuation problem in the transmission course, thereby avoided the inaccurate and wrong report police phenomenon that produces of measured data, ensured normal production and personnel's safety.
In this embodiment, the signal processing system further comprises an alarm output module 4, the alarm output module 4 is electrically connected with the data processing module 2,
the data processing module 2 further comprises a threshold value comparison module 22, the threshold value comparison module 22 is electrically connected with the dose rate calculation module 21 and is used for judging whether the dose rate of the radioactive substance is greater than or equal to the warning dose rate stored in the dose rate calculation module, and when the judgment result is yes, an alarm switch signal is output and transmitted through the alarm output module 4.
Therefore, the alarm switch signal generated by the signal processing system integrated in the nuclear detector through judgment can also be transmitted to the remote control system through the RS485 bus digital signal, so that the remote control system can quickly send out the alarm signal without processing data.
In this embodiment, the data processing module 2 adopts an FPGA chip, and the communication module 3 is an RS485 communication interface.
In this embodiment, the signal conversion module includes a pulse filter circuit 5 and a pulse counter circuit 6,
the pulse filter circuit 5 is connected with the probe 1 and is used for receiving the pulse signal output by the probe 1 and filtering out the pulse with the pulse width less than the set value,
the pulse counting circuit 6 is electrically connected with the pulse filtering circuit 5 and the data processing module 2, and is used for counting the second period of the pulse signals processed by the pulse filtering circuit 5 to obtain the number of pulses in the second period, and sending the number of pulses to the data processing module 2.
Specifically, in the present embodiment, the pulse filter circuit 5 filters out pulses having a pulse width of less than 200 us.
In this embodiment, the signal processing system further includes a parameter storage module 7, specifically, an EEPROM memory.
The parameter storage module 7 is electrically connected with the communication module 3 and the data processing module 2 and is used for receiving and storing a parameter setting command sent by the remote control system;
the data processing module 2 is further configured to execute the parameter setting command to complete setting of the corresponding parameter, and is further configured to send the calculated dose rate to the parameter storage module 7 for storage.
In this embodiment, the probe 1 is provided with three ionization chambers, a medium dose G-M tube and a low dose G-M tube.
The ionization chamber, the medium-dose G-M tube and the low-dose G-M tube are all ray detectors, and the detectors have different detection accuracies in different dose ranges.
In this embodiment, the signal processing system further includes a high voltage detection module 8, a high voltage switching module 9, and a self-test control module 10,
the high-voltage detection module 8 is electrically connected with the communication module 3 and the ionization chamber, and is used for receiving a high-voltage detection command sent by the remote control system, detecting a high-voltage signal of the ionization chamber, and sending the high-voltage signal to the remote control system through the communication module 3;
the high-voltage switching module 9 is electrically connected with the communication module 3 and the ionization chamber and is used for receiving a high-voltage switching command sent by a remote control system and controlling a high-voltage switching signal of the ionization chamber;
the input end of the self-checking control module 10 is electrically connected with the communication module 3, the output end of the self-checking control module is electrically connected with the ionization chamber, the medium dosage G-M tube and the low dosage G-M tube respectively, and the self-checking control module is used for receiving a self-checking control command sent by the remote control system, detecting the device function states of the ionization chamber, the medium dosage G-M tube and the low dosage G-M tube, and sending a device function state signal to the remote control system through the communication module 3.
In summary, the signal processing system of the nuclear critical detector in the invention adopts a hardware architecture based on the FPGA technology to realize the 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.
Example 2:
this embodiment provides a method for performing nuclear threshold detection by using the nuclear detector of embodiment 1, including:
the probe 1 detects the gamma rays emitted by the radioactive substance, converts the gamma rays into pulse signals and outputs the pulse signals,
the signal conversion module receives the pulse signal output by the probe 1, and performs conversion and counting processing on the pulse signal to acquire a pulse counting rate corresponding to the gamma ray in a set energy interval, and sends the pulse counting rate to the data processing module 2,
the dose rate calculation module 21 of the data processing module 2 calculates the dose rate of the radioactive substance corresponding to the pulse count rate according to the stored relation between the pulse count rate and the dose rate of the radioactive substance, so as to generate a dose rate communication signal, and transmits the dose rate communication signal through the communication module 3.
In this embodiment, the method further includes:
the threshold comparison module 22 of the data processing module 2 determines whether the dose rate of the radioactive substance is greater than or equal to the alert dose rate stored therein, and outputs an alert switch signal when the determination result is "yes", and transmits the alert switch signal through the alert output module 4.
In this embodiment, the method further includes: the signal conversion module comprises a pulse filtering circuit 5 and a pulse counting circuit 6,
the pulse filter circuit 5 receives the pulse signal output by the probe 1, filters out the pulse with the pulse width less than the set value,
the pulse counting circuit 6 counts the pulse signals processed by the pulse filtering circuit 5 to obtain the number of pulses in a second period, and sends the number of pulses to the data processing module 2.
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 nuclear criticality detector, comprising: the probe comprises a probe (1) and a signal processing system, wherein the signal processing system comprises a signal conversion module, a data processing module (2) and a communication module (3), the probe (1), the signal conversion module, the data processing module (2) and the communication module (3) are sequentially and electrically connected,
the probe (1) is used for detecting gamma rays emitted by radioactive substances and converting the gamma rays into pulse signals to be output,
the signal conversion module is used for receiving the pulse signals output by the probe (1), performing conversion and counting processing on the pulse signals to acquire the pulse counting rate corresponding to the gamma rays in a set energy interval and sending the pulse counting rate to the data processing module (2),
the data processing module (2) comprises a dosage rate calculating module (21), the dosage rate calculating module (21) is used for calculating the dosage rate of the radioactive substance corresponding to the pulse counting rate according to a relation between the pulse counting rate and the dosage rate of the radioactive substance stored in the dosage rate calculating module to generate a dosage rate communication signal, and the dosage rate communication signal is transmitted through the communication module (3).
2. Nuclear criticality detector according to claim 1, characterized in that the signal processing system further comprises an alarm output module (4), the alarm output module (4) being electrically connected with the data processing module (2),
the data processing module (2) further comprises a threshold value comparison module (22), the threshold value comparison module (22) is electrically connected with the dosage rate calculation module (21) and is used for judging whether the dosage rate of the radioactive substances is larger than or equal to the warning dosage rate stored in the dosage rate calculation module, when the judgment result is 'yes', an alarm switch signal is output, and the alarm switch signal is transmitted through the alarm output module (4).
3. The nuclear criticality detector of claim 1, wherein the data processing module (2) is an FPGA chip, and the communication module (3) is an RS485 communication interface.
4. Nuclear critical detector as in any of claims 1-3, characterized in that the signal conversion module comprises a pulse filtering circuit (5) and a pulse counting circuit (6),
the pulse filter circuit (5) is connected with the probe (1) and is used for receiving the pulse signal output by the probe (1) and filtering out the pulse with the pulse width less than a set value,
the pulse counting circuit (6) is electrically connected with the pulse filtering circuit (5) and the data processing module (2) and is used for counting pulse signals processed by the pulse filtering circuit (5) so as to obtain the number of pulses in a second period and sending the number of pulses to the data processing module (2).
5. Nuclear critical detector as in any of claims 1-3, characterized in that the signal processing system further comprises a parameter storage module (7),
the parameter storage module (7) is electrically connected with the communication module (3) and the data processing module (2) and is used for receiving and storing a parameter setting command sent by the remote control system;
the data processing module (2) is further configured to execute the parameter setting command to complete setting of the corresponding parameter, and is further configured to send the calculated dose rate to the parameter storage module (7) for storage.
6. Nuclear critical detector as in any of claims 1-3, characterized in that the probe (1) is provided with three, respectively ionization chamber, medium dose G-M tube and low dose G-M tube.
7. Nuclear critical detector as in claim 6, characterized in that the signal processing system further comprises a high voltage detection module (8), a high voltage switching module (9) and a self-test control module (10),
the high-voltage detection module (8) is electrically connected with the communication module (3) and the ionization chamber and is used for receiving a high-voltage detection command sent by the remote control system, detecting a high-voltage signal of the ionization chamber and sending the high-voltage signal to the remote control system through the communication module (3);
the high-voltage switching module (9) is electrically connected with the communication module (3) and the ionization chamber and is used for receiving a high-voltage switching command sent by a remote control system and controlling a high-voltage switching signal of the ionization chamber;
the input end of the self-checking control module (10) is electrically connected with the communication module (3), the output end of the self-checking control module is electrically connected with the ionization chamber, the medium-dose G-M tube and the low-dose G-M tube respectively, and the self-checking control module is used for receiving a self-checking control command sent by the remote control system, detecting the equipment function states of the ionization chamber, the medium-dose G-M tube and the low-dose G-M tube, and sending an equipment function state signal to the remote control system through the communication module (3).
8. A nuclear criticality detection method, comprising:
the probe (1) detects gamma rays emitted by radioactive substances and converts the gamma rays into pulse signals to be output,
the signal conversion module receives the pulse signal output by the probe (1), converts and counts the pulse signal to acquire a pulse counting rate corresponding to the gamma ray in a set energy interval and sends the pulse counting rate to the data processing module (2),
a dosage rate calculation module (21) of the data processing module (2) calculates the dosage rate of the radioactive substance corresponding to the pulse counting rate according to a relation between the pulse counting rate and the dosage rate of the radioactive substance stored in the data processing module to generate a dosage rate communication signal, and the dosage rate communication signal is transmitted through a communication module (3).
9. The nuclear criticality detection method of claim 8, further comprising:
a threshold value comparison module (22) of the data processing module (2) judges whether the dosage rate of the radioactive substance is larger than or equal to the warning dosage rate stored in the data processing module, and when the judgment result is 'yes', an alarm switch signal is output and transmitted through an alarm output module (4).
10. The nuclear criticality detection method of claim 8 or 9, further comprising: the signal conversion module comprises a pulse filtering circuit (5) and a pulse counting circuit (6),
the pulse filter circuit (5) receives the pulse signal output by the probe (1) and filters out the pulse with the pulse width less than a set value,
the pulse counting circuit (6) counts the pulse signals processed by the pulse filtering circuit (5) to obtain the number of pulses in a second period, and sends the number of pulses to the data processing module (2).
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