CN212515056U - Nuclear emergency multifunctional portable radiation monitoring system - Google Patents
Nuclear emergency multifunctional portable radiation monitoring system Download PDFInfo
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Abstract
The utility model discloses a multi-functional portable radiation monitoring system of nuclear emergency, include: the device comprises a detection module and a data processing and control module; the detection module is bidirectionally connected with the data processing and control module; the detection module comprises a G-M counting tube, a NaI detector and a 3He neutron detection counting tube; the data processing and control module comprises a detector selection unit, a multichannel pulse amplitude analyzer and a dose conversion unit; the utility model discloses can survey simultaneously and measure two kinds of data of dose rate and gamma energy spectrum, carry out the broadening to the dose rate range again, increase the application scope of system.
Description
Technical Field
The utility model relates to a nuclear radiation monitoring technology field, more specifically the utility model relates to a multi-functional portable radiation monitoring system of nuclear emergency that says so.
Background
With the development of nuclear technology, the utilization of nuclear technology has gradually gone into people's lives, and more projects are related to nuclear technology, such as nuclear power industry, radioactive medicine, irradiation inactivation modification and the like. However, it should be noted that nuclear technology can benefit us as well as endanger human life. The radioactive sources used in the medical, industrial and agricultural departments in China have large quantity, long period, scattered distribution and great management difficulty. Although the management measures of the radioactive source are continuously strengthened by relevant government departments, the radioactive source accidents still occur. Such as: the source used for industrial flaw detection and the neutron source used for petroleum well logging are lost, radioactive tailings are not treated in time, and radioactivity leakage caused by nuclear accidents of nuclear facilities is caused. Thus, while nuclear technology is utilized, the detection and monitoring of the radiation environment must also be enhanced. In order to protect the public and the environment, the improvement of the emergency response capability of radiation accidents is of great importance, and the exploration of more advanced technology to perfect the nuclear radiation detection instrument becomes of great importance.
The size of radioactivity (dose rate) and the radioactivity (X, gamma and n) are two parameters of most interest in radioactivity evaluation, environmental protection departments in China generally adopt detectors with single functions to carry out related work, and analysis of a radiation field usually requires simultaneous cooperative work of a plurality of types of detectors. After various data are measured, the actual situation of the whole radiation field is analyzed, certain information lag can be caused in some sudden nuclear accidents, and the rapid control and treatment of the nuclear accidents are not facilitated.
Therefore, how to develop a nuclear emergency multifunctional portable radiation monitoring system capable of detecting the nuclear radiation and accurately detecting the nuclear radiation type is a problem that needs to be solved by those skilled in the art.
SUMMERY OF THE UTILITY MODEL
In view of this, the utility model provides an emergent multi-functional portable radiation monitoring system of nuclear, its aim at can detect out nuclear radiation size and can accurately survey out the nuclear radiation kind again.
In order to achieve the above purpose, the utility model adopts the following technical scheme:
a nuclear emergency multifunctional portable radiation monitoring system comprising: the device comprises a detection module and a data processing and control module; the detection module is bidirectionally connected with the data processing and control module;
the detection module comprises a G-M counting tube, a NaI detector and a 3He neutron detection counting tube;
the G-M counting tube and the NaI detector are respectively used for detecting radiation at a high energy end and a low energy end of radiation dose, and the 3He neutron detection counting tube is used for detecting neutron dose;
the data processing and control module comprises a detector selection unit, a multichannel pulse amplitude analyzer and a dose conversion unit;
the detector selection unit is respectively connected with the G-M counting tube and the NaI detector and is used for controlling gating of the G-M counting tube and the NaI detector in the detection module to realize switching of the G-M counting tube and the NaI detector;
the multichannel pulse amplitude analyzer is connected with the NaI detector and used for acquiring an energy spectrum, and comparing the acquired energy spectrum with a standard energy spectrum to determine the type of the radionuclide generating the current radiation;
and the dose conversion unit is respectively connected with the multichannel pulse amplitude analyzer, the G-M counting tube and the 3He neutron detection counting tube and is used for acquiring corresponding air absorption dose rate and neutron radiation dose through conversion.
Preferably, the detector selection unit comprises a memory, a range discriminator and a gating switch;
a counting value threshold value Ns is preset in the memory, wherein the counting value threshold value Ns belongs to the crossing range of the measuring ranges of the G-M counting tube and the NaI detector;
the range discriminator is connected with the memory and the gating switch and is used for comparing the pulse count N0 obtained by the pre-gated G-M counting tube with the count value threshold Ns;
and the gating switch controls the on-off of the G-M counting tube and the NaI detector according to the comparison result of the range discriminator.
Preferably, the data processing and control module further comprises an amplifying circuit, and the amplifying circuit is respectively connected with the NaI detector and the output end of the 3He neutron detection counting tube, and is used for amplifying the pulse signals generated by detection.
Preferably, the detection module further comprises a temperature sensor, and the temperature sensor is used for acquiring the ambient temperature in real time.
Preferably, the data processing and control module further comprises a spectrum stabilizing unit; the energy spectrum stabilizing unit is respectively connected with the multichannel pulse amplitude analyzer and the temperature sensor and used for finishing energy spectrum channel address correction according to real-time environment temperature so that the energy spectrum tends to be stable under the temperature change.
The beneficial effects of adopting the above technical scheme are:
the low-energy over-response problem of the radiation is corrected through G (E) fitting of the energy spectrum and the dose, and the detection efficiency of weak radioactivity of the instrument and the accuracy of low dose are improved by combining temperature compensation.
Preferably, the device further comprises a power module, wherein the power module comprises a high-voltage power supply and a low-voltage power supply, the high-voltage power supply is used for supplying power to the detection module, and the low-voltage power supply is used for supplying power to the data processing and control module.
Preferably, the system also comprises a data transmission module, wherein the data transmission module is connected with the data processing and control module, and data interaction with an upper computer is realized through the data transmission module.
According to the technical scheme, compared with the prior art, the utility model discloses a multi-functional portable radiation monitoring system of nuclear emergency, at first, through adopting the multiple detector composite design of G-M pipe, NaI, 3He pipe, realize carrying out radiation detection to X, gamma, n three kinds of rays simultaneously, can accurate quick acquisition radiation dose rate; secondly, because the operating characteristic that two kinds of radiation detectors of G-M pipe, NaI, 3He pipe lead to because of the existence of dead time is comparatively limited, the utility model discloses a control it surveys at low, high dose rate environment automatic selection for use NaI detector and GM count pipe, and both complement each other and make the system can record two kinds of data of dose rate and energy spectrum simultaneously, widen the dose rate range again, increased the application scope of system; in addition, the energy spectrum can be rapidly acquired through the multichannel pulse amplitude analyzer, the type of radionuclide can be further rapidly acquired according to the comparison between the energy spectrum and the standard energy spectrum, the wide-range coverage of the dose rate and the rapid and effective identification of the common nuclide can be accurately and effectively realized, the radiation monitoring system is simple in structure, the volume is smaller after a monitoring instrument is formed, the relevant radiation personnel can be guided to carry out relevant work more conveniently, rapidly, more accurately and more safely, and the detection equipment and the technology are promoted to be not only suitable for the site of a sudden nuclear accident, but also more suitable for various places needing radiation monitoring.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings required to be used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to the provided drawings without creative efforts.
Fig. 1 is a schematic diagram of an overall structure of a nuclear emergency multifunctional portable radiation monitoring system provided by the present invention;
fig. 2 is a schematic flow chart of a monitoring method of the nuclear emergency multifunctional portable radiation monitoring system provided by the present invention.
Detailed Description
The technical solutions in the embodiments of the present invention will be described clearly and completely with reference to the accompanying drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only some embodiments of the present invention, not all embodiments. Based on the embodiments in the present invention, all other embodiments obtained by a person skilled in the art without creative work belong to the protection scope of the present invention.
The embodiment of the utility model discloses emergent multi-functional portable radiation monitoring system of nuclear, include: the device comprises a detection module and a data processing and control module; the detection module is bidirectionally connected with the data processing and control module;
the detection module comprises a G-M counting tube, a NaI detector and a 3He neutron detection counting tube;
the G-M counting tube and the NaI detector are respectively used for detecting radiation at a high energy section and a low energy end of radiation dose, and the 3He neutron detection counting tube is used for detecting neutron dose;
the data processing and control module comprises a detector selection unit, a multichannel pulse amplitude analyzer and a dose conversion unit;
the detector selection unit is respectively connected with the G-M counting tube and the NaI detector and is used for controlling the gating of the G-M counting tube and the NaI detector in the detection module to realize the switching of the G-M counting tube and the NaI detector;
the multichannel pulse amplitude analyzer is connected with the NaI detector and used for acquiring an energy spectrum and comparing the acquired energy spectrum with a standard energy spectrum to determine the type of the radionuclide generating the current radiation;
and the dose conversion unit is respectively connected with the multichannel pulse amplitude analyzer, the G-M counting tube and the 3He neutron detection counting tube and is used for acquiring the corresponding air absorption dose rate and neutron radiation dose through conversion.
In order to further implement the technical scheme, the detector selection unit comprises a memory, a range discriminator and a gating switch;
a counting value threshold value Ns is preset in the memory, wherein the counting value threshold value Ns belongs to the crossing range of the measuring ranges of the G-M counting tube and the NaI detector;
the range discriminator is connected with the memory and the gating switch and is used for comparing a pulse count N0 obtained by the pre-gated G-M counting tube with a count value threshold Ns;
and the gating switch controls the on-off of the G-M counting tube and the NaI detector according to the comparison result of the range discriminator.
In order to further implement the technical scheme, the data processing and control module further comprises an amplifying circuit, and the amplifying circuit is respectively connected with the output ends of the NaI detector and the 3He neutron detection counting tube and is used for amplifying pulse signals generated by detection.
In order to further implement the above technical solution, the detection module further includes a temperature sensor, and the temperature sensor is used for acquiring the ambient temperature in real time.
In order to further implement the technical scheme, the data processing and control module further comprises an energy spectrum stabilizing unit; the energy spectrum stabilizing unit is respectively connected with the multichannel pulse amplitude analyzer and the temperature sensor and is used for finishing energy spectrum channel address correction according to real-time environment temperature so that the energy spectrum tends to be stable under the temperature change.
It should be noted that:
the working temperature range of the gamma spectrometer in the outdoor environment is generally-20-50 ℃. The NaI scintillation crystal and the photomultiplier in the NaI detector are temperature sensitive devices, and any temperature change can cause the output of the detector to change, thereby causing the energy peak position to shift, and causing difficulty in the analysis of energy spectrum data and nuclide identification.
In this embodiment, the137The Cs radioactive source is used as a scale source and is aligned in a high-low temperature experimental box at different temperatures (-20-30 ℃, 5 ℃/interval)
And (4) performing experiments by using the detector to obtain and store the gamma energy spectrums at various temperatures. And recording the channel values of the X-ray peak position and the photoelectric peak in each energy spectrum according to the obtained gamma energy spectrums at different temperatures, and fitting the change curve of the channel address along with the temperature. In the stable spectrum, a straight line with the slope of Gain and the zero point of offset can be used as an energy scale curve, and measurement is carried out137The two reference peak positions of Cs are energy scaled. And finally, taking 137Cs as a reference source, firstly measuring the 32KeV characteristic X-ray peak position ch32KeV and the 662KeV characteristic gamma-ray peak position ch622KeV, then carrying out energy calibration formulas 1 and 2, and correcting the measurement channel address ch measurement to a correction channel address ch correction formula 3 according to energy calibration curves and initial energy calibration curves calibrated at different moments:
gain 662-32/(ch622 KeV-ch 32KeV) KeV equation 1
offset is 32 × ch622 KeV-662 × ch32KeV/(ch622 KeV-ch 32KeV) KeV formula 2
ch correction is 1/Gain0(Gain (n) × ch measurement + offset (n) -offset (0)) formula 3
And finally, obtaining correction coefficient curves at different temperatures according to the temperature drift curve, and writing the correction functions into an upper computer program. When the system works, the upper computer acquires the value of the temperature sensor in real time, selects the correction coefficient corresponding to the temperature, and automatically finishes the correction of the gamma energy spectrum channel address, so that the energy spectrum tends to be stable under the temperature change.
In order to further implement the technical scheme, the device further comprises a power supply module, wherein the power supply module comprises a high-voltage power supply and a low-voltage power supply, the high-voltage power supply is used for supplying power to the detection module, and the low-voltage power supply is used for supplying power to the data processing and control module.
In order to further implement the technical scheme, the system further comprises a data transmission module, wherein the data transmission module is connected with the data processing and control module, and data interaction with the upper computer is realized through the data transmission module.
A monitoring method of a nuclear emergency multifunctional portable radiation monitoring system comprises the following steps:
s1, a detection module carries out real-time detection, wherein a G-M counting tube and a NaI detector respectively carry out radiation detection on a high-energy section and a low-energy end of radiation dose, a 3He neutron detection counting tube detects the neutron dose, and detected results are all sent to a data processing and control module;
s2, a detector selection unit controls gating of the G-M counting tube and the NaI detector;
when the G-M counting tube is gated, counting the pulses, and sending an obtained result to the dose conversion unit, wherein the dose conversion unit converts the pulse counting rate into the air absorption dose rate;
when the NaI detector is gated, counting pulses, sending an obtained result to a multi-channel pulse amplitude analyzer, obtaining an energy spectrum by the multi-channel pulse amplitude analyzer, and comparing the obtained energy spectrum with a standard energy spectrum by an energy window discrimination method to determine the type of the radionuclide generating the current radiation; the dose conversion unit acquires an energy spectrum, and calculates a corresponding air absorption dose rate result through a G (E) function;
and the 3He neutron detection counting tube sends the detected result to the dose conversion unit so as to obtain a neutron radiation dose detection result.
It should be noted that:
the energy window discrimination method divides an energy section into a plurality of energy windows according to needs, reasonably sets the energy upper limit and the energy lower limit of each energy window, takes the total count of rays in the range as the main contribution of the energy characteristic peak, can judge nuclide information through direct comparison, and can add different energy windows for nuclide analysis according to needs.
The energy of each radionuclide is in a range of relatively fixed positions throughout the spectrum, typically the energy of the contacting radionuclide is in the range of 30keV-3MeV, and typically the energy range is divided into 2 resolution10Integer multiples of 1024 (if divided by 1024, i.e. 3 Mev/1024-3 keV) the energy of some species is known, e.g.131The energy of I is 365.4keV,137The energy of Cs is 661.7keV,60Co is 1173.2keV,238U is 2680keV, when specific nuclide is measuredThe observation can be carried out only aiming at a certain range of energy, the certain range can be used as a window, and if the energy range of a certain nuclide is found to fall within the energy window range, the radionuclide can be determined.
The g (e) function is not only related to the corresponding counts of gamma energy spectrum channel addresses, but also related to the corresponding energies, so that the contributions of each count and energy to the air absorption dose rate are different. Therefore, the g (e) function method is a method of calculating the air absorption dose rate by performing weighted integration processing on counts using a gamma energy spectrum obtained by measurement.
The functional relationship may be described by the following equation:
Dairdose rate for air absorption; t is measuring time; n (E) is a gamma energy spectrum measured in T time; g (E) is a weight function form of the gamma energy spectrum. The most common form of the G (E) function is as follows:
in formula (1.2): k is the order of the function; ak is a undetermined coefficient; and E is the energy corresponding to the gamma energy spectrum channel address, and when the standard radioactive nuclide point source is used for scaling the HPGe gamma spectrometer, the standard radioactive nuclide point source j comprises the following components:
then, the following formula can be obtained:
Eithe energy corresponding to the ith channel of the gamma energy spectrum; j is the number of standard radionuclide point sources; n is a radical ofjiThe corresponding count on the i trace of the energy spectrum of the j-th nuclide. Therefore, the method uses a gamma spectrometer to measure a standard radionuclide point source, constructs a function matrix equation, and solves the value of the undetermined coefficient AK by using a least square method or a conjugate gradient method, so that the corresponding air absorption dose rate result can be calculated according to the counting and energy of the gamma energy spectrum.
In order to further implement the above technical solution, the specific method for controlling the gating of the G-M counting tube and the NaI detector by the detector selection unit in S2 is as follows:
gating a G-M counting tube, acquiring a counting value N0, and comparing the counting value N0 with a counting value threshold Ns;
if N0 is not less than Ns, the G-M counting tube is continuously gated through the gating switch to obtain a counting value N1, and N1 is a final counting value;
if N0 is less than Ns, the G-M counting tube is closed through the gating switch, and then the NaI detector is gated on.
The embodiments in the present description are described in a progressive manner, each embodiment focuses on differences from other embodiments, and the same and similar parts among the embodiments are referred to each other. The device disclosed by the embodiment corresponds to the method disclosed by the embodiment, so that the description is simple, and the relevant points can be referred to the method part for description.
The previous description of the disclosed embodiments is provided to enable any person skilled in the art to make or use the present invention. Various modifications to these embodiments will be readily apparent to those skilled in the art, and the generic principles defined herein may be applied to other embodiments without departing from the spirit or scope of the invention. Thus, the present invention is not intended to be limited to the embodiments shown herein but is to be accorded the widest scope consistent with the principles and novel features disclosed herein.
Claims (7)
1. A nuclear emergency multifunctional portable radiation monitoring system is characterized by comprising: the device comprises a detection module and a data processing and control module; the detection module is bidirectionally connected with the data processing and control module;
the detection module comprises a G-M counting tube, a NaI detector and a 3He neutron detection counting tube;
the G-M counting tube and the NaI detector are respectively used for detecting radiation at a high energy end and a low energy end of radiation dose, and the 3He neutron detection counting tube is used for detecting neutron dose;
the data processing and control module comprises a detector selection unit, a multichannel pulse amplitude analyzer and a dose conversion unit;
the detector selection unit is respectively connected with the G-M counting tube and the NaI detector and is used for controlling gating of the G-M counting tube and the NaI detector in the detection module to realize switching of the G-M counting tube and the NaI detector;
the multichannel pulse amplitude analyzer is connected with the NaI detector and used for acquiring an energy spectrum, and comparing the acquired energy spectrum with a standard energy spectrum to determine the type of the radionuclide generating the current radiation;
and the dose conversion unit is respectively connected with the multichannel pulse amplitude analyzer, the G-M counting tube and the 3He neutron detection counting tube and is used for acquiring corresponding air absorption dose rate and neutron radiation dose through conversion.
2. The nuclear emergency multifunctional portable radiation monitoring system of claim 1, wherein the detector selection unit includes a memory, a range discriminator and a gating switch;
a counting value threshold value Ns is preset in the memory, wherein the counting value threshold value Ns belongs to the crossing range of the measuring ranges of the G-M counting tube and the NaI detector;
the range discriminator is connected with the memory and the gating switch and is used for comparing the pulse count N0 obtained by the pre-gated G-M counting tube with the count value threshold Ns;
and the gating switch controls the on-off of the G-M counting tube and the NaI detector according to the comparison result of the range discriminator.
3. The nuclear emergency multifunctional portable radiation monitoring system according to claim 1, wherein the data processing and control module further comprises an amplifying circuit, and the amplifying circuit is respectively connected with the output ends of the NaI detector and the 3He neutron detection counting tube, and is used for amplifying pulse signals generated by detection.
4. The nuclear emergency multifunctional portable radiation monitoring system of claim 1, wherein the detection module further comprises a temperature sensor for acquiring the ambient temperature in real time.
5. The nuclear emergency multifunctional portable radiation monitoring system of claim 4, wherein the data processing and control module further comprises a spectrum stabilization unit; the energy spectrum stabilizing unit is respectively connected with the multichannel pulse amplitude analyzer and the temperature sensor and used for finishing energy spectrum channel address correction according to real-time environment temperature so that the energy spectrum tends to be stable under the temperature change.
6. The nuclear emergency multifunctional portable radiation monitoring system according to claim 1, further comprising a power module, wherein the power module comprises a high voltage power supply and a low voltage power supply, the high voltage power supply is used for supplying power to the detection module, and the low voltage power supply is used for supplying power to the data processing and control module.
7. The nuclear emergency multifunctional portable radiation monitoring system according to claim 1, further comprising a data transmission module, wherein the data transmission module is connected with the data processing and control module, and data interaction with an upper computer is realized through the data transmission module.
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| 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 |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| 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 |
| CN112907914B (en) * | 2021-02-09 | 2022-01-25 | 陕西卫峰核电子有限公司 | Nuclear criticality alarm system and alarm method thereof |
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