CN218412918U - Portable radiation measuring instrument - Google Patents
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- CN218412918U CN218412918U CN202221885713.7U CN202221885713U CN218412918U CN 218412918 U CN218412918 U CN 218412918U CN 202221885713 U CN202221885713 U CN 202221885713U CN 218412918 U CN218412918 U CN 218412918U
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The utility model discloses a portable radiation measuring instrument. The portable radiation measuring instrument comprises: the multifunctional detector comprises a host, a connecting mechanism and a multifunctional detector, wherein the connecting mechanism comprises a data transmission line and a telescopic extension rod; the two ends of the data transmission line are respectively and electrically connected with the host and the multifunctional detector and are used for providing voltage and transmitting communication signals; the first end of the telescopic extension rod is fixedly connected with the host, and the second end of the telescopic extension rod is detachably connected with the multifunctional detector; the multifunctional detector is used for measuring the dosage value of the radiation source to be measured; the multifunctional detector comprises a first probe, a second probe and a third probe. Through the separated design of adopting host computer and a plurality of probe, can satisfy different application scenarios, improved operating personnel to the measurement of the radiation source that awaits measuring efficiency, facilitate the use.
Description
Technical Field
The embodiment of the utility model provides a relate to radiometric measurement technical field, especially relate to a portable radiometer.
Background
Currently, in order to protect the health and life safety of the public, personnel need to monitor and evaluate the radioactivity level of radioactive materials and equipment in the natural environment and radioactive workplace, and to control the level of radioactivity within the safety range stipulated by the country.
The existing measurement method widely uses various dose rate meters and surface pollution measurement instruments to monitor the environmental radioactivity, and common portable radiation measurement instruments generally have single functions, such as a gamma dose rate meter (only used for measuring gamma rays), a surface pollution measurement instrument (used for measuring alpha and beta rays), a neutron dose rate meter (used for measuring neutron rays) and the like. At present, measuring instruments with different measuring functions are also arranged on the market, but the use is inconvenient, if different detection window baffle materials need to be switched when alpha and beta rays are measured, the volume and the weight of the neutron detector are large, the neutron detector is inconvenient to carry, the measurement is inconvenient in a narrow space, and various defects such as different application scenes cannot be met.
Therefore, how to provide a portable radiation measuring instrument which can measure multiple types of radiation simultaneously and meet the measurement requirements of various application scenarios becomes a problem to be solved urgently.
SUMMERY OF THE UTILITY MODEL
The utility model provides a portable radiation measuring instrument to the disconnect-type design of realizing host computer and a plurality of probe satisfies different application scenes, has improved operating personnel to the measurement of the radiation source that awaits measuring efficiency.
The embodiment of the utility model provides a portable radiation measuring instrument, this portable radiation measuring instrument includes: the multifunctional detector comprises a host, a connecting mechanism and a multifunctional detector, wherein the connecting mechanism comprises a data transmission line and a telescopic extension rod;
the two ends of the data transmission line are respectively and electrically connected with the host and the multifunctional detector and are used for providing voltage and transmitting communication signals;
the first end of the telescopic extension rod is fixedly connected with the host, and the second end of the telescopic extension rod is detachably connected with the multifunctional detector;
the multifunctional detector is used for measuring the dosage value of the radiation source to be measured;
the multifunctional detector comprises a first probe, a second probe and a third probe; the first probe is used for detecting alpha rays, beta rays and gamma rays, the second probe is used for detecting the beta rays and the gamma rays, and the third probe is used for detecting neutron rays.
Further, the host includes: the device comprises a rechargeable battery, a main control circuit, a power supply conversion circuit, a first counting tube detector, an amplifying circuit, a micro control circuit and a display terminal;
the rechargeable battery is electrically connected with the input end of the main control circuit, the output end of the main control circuit is electrically connected with the input end of the power supply conversion circuit, the output end of the power supply conversion circuit is electrically connected with the input end of the first counting tube detector, the output end of the first counting tube detector is electrically connected with the amplifying circuit, and the amplifying circuit is connected with the display terminal through the micro control circuit.
Further, the first probe comprises: the detector comprises a first scintillator detector, a first photomultiplier transistor, a first pulse width discriminator, a second counting tube detector and a first signal processor;
the first scintillator detector is used for detecting the dosage value of alpha particles and beta particles, the second counting tube detector is used for detecting the dosage value of gamma particles, and the first scintillator detector and the second counting tube detector are arranged in parallel along the detection axis direction;
the first scintillator detector is electrically connected with the input end of the first photomultiplier, the output end of the first photomultiplier is electrically connected with the input end of the first pulse width discriminator, and the output end of the first pulse width discriminator and the second counting tube detector are respectively electrically connected with the first signal processor.
Further, the second probe comprises: the detector comprises a second scintillator detector, a second photomultiplier transistor, a second pulse width discriminator, a third counting tube detector, a first inorganic crystal detector and a second signal processor;
the second scintillator detector is used for detecting the dosage value of beta particles, and the third counting tube detector and the first inorganic crystal detector are used for detecting the dosage value of gamma particles;
the second scintillator detector is electrically connected with the input end of the second photomultiplier, the output end of the second photomultiplier is electrically connected with the input end of the second pulse width discriminator, and the output end of the second pulse width discriminator, the third counting tube detector and the first inorganic crystal detector are respectively electrically connected with the signal processor.
Further, the third probe comprises: a second inorganic crystal detector, a third photomultiplier transistor, and a third signal processor;
the second inorganic crystal detector is used for detecting the dosage value of neutrons;
the second inorganic crystal detector is electrically connected with the input end of the third photomultiplier transistor, and the output end of the third photomultiplier transistor is electrically connected with the third signal processor.
Further, the first scintillator detector comprises a plastic scintillator, and a film layer formed by a silver-doped zinc sulfide material is coated on the surface of the plastic scintillator.
Further, the second scintillator detector comprises a plastic scintillator, and a film layer formed by a silver-doped zinc sulfide material is coated on the surface of the plastic scintillator.
Further, the first inorganic crystal detector is a bismuth germanate crystal detector.
Further, the direct current voltage that the host computer provided for multi-functional detector is 5V.
Further, the host and the multifunctional detector are communicated based on an RS485 protocol.
The utility model discloses a set up portable radiation measurement appearance and include the host computer, coupling mechanism and multifunctional detector, coupling mechanism includes data transmission line and flexible extension rod, data transmission line's both ends are connected with host computer and multifunctional detector electricity respectively, be used for providing voltage and transmission communication signal, the first end and the host computer fixed connection of flexible extension rod, the second end and the multifunctional detector of flexible extension rod can be dismantled and be connected, multifunctional detector is used for measuring the dose value of the radiation source that awaits measuring, multifunctional detector includes first probe, second probe and third probe, first probe is used for alpha ray, beta ray and gamma ray are surveyed, the second probe is used for surveying beta ray and gamma ray, the third probe is used for surveying neutron ray. Through the disconnect-type design that adopts host computer and a plurality of probe, can be applicable to different application scenes, satisfied the portable measuring demand of personnel to the at utmost, and can simultaneous measurement polytype radiation through a plurality of probes, improved operating personnel to the measurement of the radiation source that awaits measuring efficiency, facilitate the use.
Drawings
Fig. 1 is a schematic structural diagram of a portable radiation measuring instrument according to an embodiment of the present invention;
fig. 2 is a schematic exterior view of a portion of a portable radiation measuring instrument according to a first embodiment of the present invention;
fig. 3 is a block diagram of a host according to a second embodiment of the present invention;
fig. 4 is a block diagram of a first probe according to a second embodiment of the present invention;
fig. 5 is a structural block diagram of a second probe according to a second embodiment of the present invention;
fig. 6 is a block diagram of a third probe according to an embodiment of the present invention.
Detailed Description
The present invention will be described in further detail with reference to the accompanying drawings and examples. It is to be understood that the specific embodiments described herein are merely illustrative of the invention and are not limiting of the invention. It should be further noted that, for the convenience of description, only some of the structures related to the present invention are shown in the drawings, not all of the structures.
Example one
Fig. 1 is the embodiment of the present invention provides a structural schematic diagram of a portable radiation measuring instrument, fig. 2 is the embodiment of the present invention provides an exterior schematic diagram of a part of equipment of a portable radiation measuring instrument, see fig. 1 and fig. 2, the structure of the portable radiation measuring instrument is as follows:
the portable radiation measuring instrument comprises: the multifunctional detector comprises a host 11, a connecting mechanism 12 and a multifunctional detector 13, wherein the connecting mechanism 12 comprises a data transmission line 121 and a telescopic extension rod 122; both ends of the data transmission line 121 are electrically connected with the host 11 and the multifunctional detector 13 respectively, and are used for providing voltage and transmitting communication signals; the first end of flexible extension rod 122 and host computer 11 fixed connection, the second end and the multi-functional detector 13 detachable connection of flexible extension rod 122.
It can be understood that the host 11 is equivalent to a control unit, and is used for issuing a control command to the multifunctional detector 13, controlling the multifunctional detector 13 to measure the radiation value of the radiation source to be detected, and receiving the measurement result fed back by the multifunctional detector 13. The connecting mechanism 12 is used for connecting the host 11 and the multifunctional probe 13, wherein the data transmission line 121 is used for mutual data transmission between the host 11 and the multifunctional probe 13, and the data transmission line 121 may be a spring data line with an aviation plug; the telescopic extension rod 122 is composed of connecting pipes with different calibers, a pipeline connecting piece and a fixed connecting piece (not shown in the figure), the telescopic extension rod can be shortened and prolonged by the sliding of the connecting pipes in the pipes, the detection distance of the multifunctional detector can be changed, the multifunctional detector is suitable for different application scenes, for example, the telescopic extension rod can be extended in a long and narrow space, and the radiation value of a radiation source to be detected is measured by people. Further, the first end of flexible extension rod 122 in this embodiment can with host computer 11 fixed connection, the second end of flexible extension rod 122 can be connected through the detachable mode with multi-functional detector 13, adopts the detachable connected mode, can make host computer and multi-functional detector disconnect-type design, the use under the different scenes of being convenient for to satisfy personnel's measurement demand.
Specifically, the multifunctional detector 13 is used for measuring the dose value of the radiation source to be measured; the multifunction probe 13 includes a first probe 131, a second probe 132, and a third probe 133; the first probe 131 is used for detecting alpha rays, beta rays and gamma rays, the second probe 132 is used for detecting beta rays and gamma rays, and the third probe 133 is used for detecting neutron rays. Illustratively, referring to fig. 2, the multifunctional detector 13 is provided with three independent detector probes, namely a first probe 131, a second probe 132 and a third probe 133, the first probe 131 is an α β γ probe, and can measure dosage values of α, β and γ rays at the same time; the second probe 132 is a β γ probe, which can measure the dosage values of β and γ rays at the same time; the third probe 133 is a neutron probe, and can measure the dose value of neutron rays. Compared with the switching scheme that the external probe cannot be connected in an integrated design in the prior art, and the measurement function can only be realized by switching the separation blades made of different materials, in the embodiment, multiple types of radiation can be measured simultaneously through multiple probes, so that the measurement efficiency of an operator on a radiation source to be measured is improved, and the use is convenient.
Optionally, the portable radiation measuring apparatus may further include a handheld device, the handheld device may be disposed at an end of the host 11 away from the connecting device 12, in a work process, an operator may grip the handheld device to control the overall spatial movement of the radiation measuring apparatus, and the specific setting position of the handheld device is not specifically limited in this embodiment.
Optionally, the host 11 and the multifunctional detector 13 communicate with each other based on RS485 protocol. It should be noted that the RS485 communication protocol herein refers to a data acquisition method of a digital multipoint system in a communication interface, and the RS485 communication can balance transmission and differential reception, and has the capability of suppressing common-mode interference, and the implementation is simple. Of course, the communication mode between the host 11 and the multifunctional detector 13 may be other systems, and the present invention is not limited to the specific communication system mode.
Optionally, the host 11 provides the multifunctional detector 13 with a dc voltage of 5V. Illustratively, the host computer 11 provides 5V dc power to the probe head of the multifunction probe 13 via the data transmission line 121, thereby ensuring proper operation of the meter apparatus.
The technical scheme of this embodiment, include the host computer through setting up portable radiation measurement appearance, coupling mechanism and multifunctional detector, coupling mechanism includes data transmission line and flexible extension rod, data transmission line's both ends are connected with host computer and multifunctional detector electricity respectively, be used for providing voltage and transmission communication signal, the first end and the host computer fixed connection of flexible extension rod, the second end and the multifunctional detector of flexible extension rod can be dismantled and be connected, multifunctional detector is used for measuring the dose value of the radiation source that awaits measuring, multifunctional detector includes first probe, second probe and third probe, first probe is used for alpha ray, beta ray and gamma ray are surveyed, the second probe is used for surveying beta ray and gamma ray, the third probe is used for surveying neutron ray. Through the disconnect-type design that adopts host computer and a plurality of probe, can be applicable to different application scenes, satisfied the portable measuring demand of personnel to the at utmost, and can measure polytype radiation simultaneously through a plurality of probes, improved operating personnel to the measurement of the radiation source that awaits measuring efficiency, facilitate the use.
Example two
The second embodiment of the present invention provides a detailed explanation of the host of the portable radiation measuring apparatus and the specific internal structure of the multifunctional detector on the basis of the above embodiments.
Fig. 3 is a block diagram of a host provided by the second embodiment of the present invention, as shown in fig. 3, the host 11 of the present invention specifically includes: the system comprises a rechargeable battery 111, a main control circuit 112, a power supply conversion circuit 113, a first counting tube detector 114, an amplifying circuit 115, a micro-control circuit 116 and a display terminal 117; the rechargeable battery 111 is electrically connected with the input end of the main control circuit 112, the output end 112 of the main control circuit is electrically connected with the input end of the power conversion circuit 113, the output end of the power conversion circuit 113 is electrically connected with the input end of the first counting tube detector 114, the output end of the first counting tube detector 114 is electrically connected with the amplifying circuit 115, and the amplifying circuit 115 is electrically connected with the display terminal 117 through the micro control circuit 116.
The rechargeable battery 111 can be a lithium battery, which provides voltage for the main control circuit 112, and the lithium battery has good performance among various batteries, and has the advantages of small volume, light weight and large capacity; the power conversion circuit 113 is used for converting the voltage level; the first count tube detector 114 is a geiger miller count tube detector, a nuclear radiation detector, that is used to convert the ray signals to current signals; the amplifying circuit 115 is used for amplifying the current signal so as to facilitate signal processing; the display terminal 117 may be understood as an OLED display screen for displaying the processed information.
Illustratively, the rechargeable battery 111 is electrically connected to an input end of the main control circuit 112, the rechargeable battery 111 provides voltage for the main control circuit 112, an output end 112 of the main control circuit is electrically connected to an input end of the power conversion circuit 113, the main control circuit 112 controls the power conversion circuit 113 to convert the voltage level from a low voltage to a high voltage, and an output end of the power conversion circuit 113 is electrically connected to an input end of the first counting tube detector 114, so that the high voltage drives the first counting tube detector 114 to convert the counting ray signals collected by the multifunctional detector 13 into current signals, the current signals are amplified by the amplification circuit 115 and then transmitted to the micro control circuit 116 for signal processing, and measured values obtained after the processing are displayed on an OLED display screen of the display terminal, thereby obtaining a radiation dose value of the radiation source to be measured.
Fig. 4 is a block diagram of a first probe according to an embodiment of the present invention, as shown in fig. 4, the first probe 131 of the present invention specifically includes: a first scintillator detector 1311, a first photomultiplier transistor 1312, a first pulse width discriminator 1313, a second counter detector 1314, and a first signal processor 1315; the first scintillator detector 1311 is configured to detect a dose value of an α particle and a β particle, the second counting tube detector 1314 is configured to detect a dose value of a γ particle, and the first scintillator detector 1311 and the second counting tube detector 1314 are arranged in parallel to each other along a detection axis direction; the first scintillator detector 1311 is electrically connected to an input of the first photomultiplier transistor 1312, an output of the first photomultiplier transistor 1312 is electrically connected to an input of the first pulse width discriminator 1313, and an output of the first pulse width discriminator 1313 and the second counter detector 1314 are electrically connected to the first signal processor 1315, respectively.
The first scintillator detector 1311 is configured to receive radiation rays emitted by the radiation source, and react with a scintillator in the first scintillator detector 1311, where the scintillator is ionized or excited to generate photons; the first photomultiplier 1312 is for performing photoelectric conversion and secondary electron multiplication on photons generated from the scintillator to amplify a weak signal, providing excellent photoelectric characteristics; the first pulse width discriminator 1313 is used for discriminating alpha rays and beta rays so as to realize automatic discrimination and measurement of the alpha rays and the beta rays, manual frequent switching of baffle materials is not needed, and operation complexity is reduced; the second counting tube detector 1314 is a geiger miller counting tube detector, is a nuclear radiation detector with simple structure, economy and practicality, and has the function of recording the number of ray particles and facilitating statistics.
For example, referring to fig. 4, in the process of measuring the dose value of the radiation source to be measured by using the first probe 131, the first scintillator detector 1311 and the second counting tube detector 1314 in the first probe 131 are arranged in parallel to each other along the detection axis direction, so that the two detectors can measure the dose value of the radiation source to be measured at the same time, where the first scintillator detector 1311 is configured to detect the dose values of α particles and β particles at the same time, at this time, α rays and β rays emitted by the radiation source to be measured react with the first scintillator detector 1311 in the measurement end window, the scintillator generates photons after ionization or excitation, then a high voltage drives the first photomultiplier 1312 to turn on, the photons perform photoelectric conversion and secondary electron multiplication on the photons generated by the scintillator after passing through the first photomultiplier 1312, finally form a pulse current output, the output end of the first photomultiplier is electrically connected to the input end of the first pulse width discriminator 1313, so that the output end of the pulse current through the first pulse width discriminator 1313 can perform photoelectric conversion and secondary electron multiplication on the photons generated by the α particles, and the pulse width information is transmitted to the host 1315, and then the pulse width information is shaped and transmitted to the host. Meanwhile, the second count tube detector 1314 in the first probe 131 also detects the dose value of the γ particles, and is electrically connected to the first signal processor 1315 through the output end of the second count tube detector 1314, so that the output pulse current signal is filtered, shaped, amplified, counted by the first signal processor 1315, and then the count information is also transmitted to the host 11.
Optionally, the first scintillator detector 1311 includes a plastic scintillator, and the surface of the plastic scintillator is coated with a film layer formed of a silver-doped zinc sulfide material. For example, in the measurement of α particles and β particles, α particles and β particles are simultaneously detected using a plastic scintillator coated with ZnS (Ag) having a sensitive region diameter of 50 mm.
Fig. 5 is a block diagram of a second probe according to an embodiment of the present invention, as shown in fig. 5, the second probe 132 of the present invention specifically includes: a second scintillator detector 1321, a second photomultiplier 1322, a second pulse width discriminator 1323, a third count tube detector 1324, a first inorganic crystal detector 1326, and a second signal processor 1325; a second scintillator detector 1321 for detecting the dose value of the β particles, a third counting tube detector 1324 and a first inorganic crystal detector 1326 for detecting the dose value of the γ particles; the second scintillator detector 1321 is electrically connected to an input terminal of the second photomultiplier 1322, an output terminal of the second photomultiplier 1322 is electrically connected to an input terminal of the second pulse width discriminator 1323, and an output terminal of the second pulse width discriminator 1323, the third count tube detector 1324, and the first inorganic crystal detector 1326 are electrically connected to the signal processor 1325, respectively.
It should be noted that, refer to fig. 2, in order to solve the inconvenient measuring problem in narrow and small space that exists in the reality application scene, the utility model discloses in, the volume that can set up second probe 132 is less than the volume of first probe 131, consequently can the adaptive occupation space that reduces third count tubular detector 1324 for third count tubular detector 1324 cooperates the dosage value of surveying gamma particle with the first inorganic crystal detector 1326 that occupation space is littleer jointly, so that measure the radiation value of the radiation source that awaits measuring in the narrow and small space, satisfy more and more complicated application scenes.
The structural functions of the second probe 132 are the same as those of the first probe 131, so that the same technical effects can be achieved, and will not be described in detail herein.
For example, referring to fig. 5, in the process of measuring the dose value of the radiation source to be measured in the narrow space by using the second probe 132, the second scintillator detector 1321 is configured to detect the dose value of the β particle, at this time, the β ray emitted by the radiation source to be measured reacts with the second scintillator detector 1321 in the measurement end window, the scintillator generates a photon after being ionized or excited, then the high voltage drives the second photomultiplier 1322 to turn on, the photon passes through the second photomultiplier 1322 to perform photoelectric conversion and secondary electron multiplication on the photon generated by the scintillator, and finally forms a pulse current output, the output end of the second photomultiplier is electrically connected with the input end of the second pulse width discriminator 1323, so that the output pulse current passes through the second pulse width discriminator 1323 to discriminate the β particle, and the data information of the β particle obtained after discrimination is sent to the second signal processor 1325 electrically connected with the output end of the second pulse width discriminator 1323 to perform filtering, amplification, shaping, and transmitting the information obtained after the shaping to the host computer to obtain the counting information. Meanwhile, the third count tube detector 1324 and the first inorganic crystal detector 1326 in the second probe 132 cooperate with each other to detect the dose value of the γ particles, the output end of the third count tube detector 1324 is electrically connected to the input end of the first inorganic crystal detector 1326, the output end of the third count tube detector 1324 and the output end of the first inorganic crystal detector 1326 are electrically connected to the signal processor 1325, respectively, so that the output pulse current signal is subjected to filtering, shaping, amplification and counting by the second signal processor 1325, and then the counting information is also transmitted to the host 11.
Optionally, the second scintillator detector 1321 includes a plastic scintillator, and the surface of the plastic scintillator is coated with a film layer formed of a silver-doped zinc sulfide material. For example, in the measurement of β particles, a plastic scintillator coated with ZnS (Ag) having a sensitive region of 40mm in diameter is used to detect the β particles.
Optionally, the first inorganic crystal detector 1326 is a bismuth germanate crystal detector, and the bismuth germanate crystal is a scintillation crystal made of a single crystal, and the scintillation crystal has high detection efficiency on high-energy gamma rays and good resolution, and can be used for counting gamma rays and energy spectrum analysis. Of course, the first inorganic crystal detector 1326 may also be a crystal detector made of other materials, and the present invention is not limited to the type of the first inorganic crystal detector.
Fig. 6 is a block diagram of a third probe according to an embodiment of the present invention, as shown in fig. 6, the third probe 133 of the present invention specifically includes: a second inorganic crystal detector 1331, a third photomultiplier transistor 1332, and a third signal processor 1333; a second inorganic crystal detector 1331 for detecting the dosage value of neutrons; the second inorganic crystal detector 1331 is electrically connected to an input of a third photomultiplier transistor 1332, and an output of the third photomultiplier transistor 1332 is electrically connected to a third signal processor 1333.
The second inorganic crystal detector 1331 is a CLYC scintillation crystal detector, which is a novel scintillator for detecting neutrons and gamma rays at the same time, and has the advantages of small slowing volume, high energy resolution, high detection efficiency, wide range of detectable neutron energy, and the like. Of course, the second inorganic crystal detector 1331 may be a crystal detector made of other materials, and the present invention is not limited to the type of the second inorganic crystal detector.
Exemplarily, referring to fig. 6, in the process of measuring the dose value of the radiation source to be measured by using the third probe 133, the second inorganic crystal detector 1331 is used for detecting the dose value of neutrons, at this time, neutron rays emitted by the radiation source to be measured react with the second inorganic crystal detector 1331 in the measurement end window, photons are generated after the scintillator is ionized or excited, then the third photomultiplier transistor 1332 is driven to turn on by high voltage, the photons perform photoelectric conversion and secondary electron multiplication on the photons generated by the scintillator after passing through the third photomultiplier transistor 1332, finally, a pulse current output is formed, the output current signal is subjected to filtering, shaping, amplifying, shaping, and signal discrimination by the third signal processor 1333, the conditioned rectangular wave signal is subjected to pulse counting and data processing, and the data is transmitted to the host 11.
It should be noted that the utility model discloses an adopt the photoelectric signal conversion scheme of second inorganic crystal detector and third photomultiplier transistor in the third probe, reduced the volume and the weight of detector, compare in prior art, neutron measuring apparatu generally uses 3 He tube or BF 3 The pipe measurement technique, there is the great, heavier problem of weight of the body volume of slowing down, the technical scheme of the utility model greatly reduced the volume and the weight of measuring apparatu, portable.
It should be noted that the foregoing is only a preferred embodiment of the present invention and the technical principles applied. It will be understood by those skilled in the art that the present invention is not limited to the particular embodiments described herein, but is capable of various obvious changes, rearrangements and substitutions as will now become apparent to those skilled in the art without departing from the scope of the invention. Therefore, although the present invention has been described in greater detail with reference to the above embodiments, the present invention is not limited to the above embodiments, and may include other equivalent embodiments without departing from the scope of the present invention.
Claims (10)
1. A portable radiation measuring instrument, comprising: the multifunctional detector comprises a host, a connecting mechanism and a multifunctional detector, wherein the connecting mechanism comprises a data transmission line and a telescopic extension rod;
the two ends of the data transmission line are respectively and electrically connected with the host and the multifunctional detector and are used for providing voltage and transmitting communication signals;
the first end of the telescopic extension rod is fixedly connected with the host, and the second end of the telescopic extension rod is detachably connected with the multifunctional detector;
the multifunctional detector is used for measuring the dosage value of the radiation source to be measured;
the multifunctional detector comprises a first probe, a second probe and a third probe; the first probe is used for detecting alpha rays, beta rays and gamma rays, the second probe is used for detecting the beta rays and the gamma rays, and the third probe is used for detecting neutron rays.
2. The portable radiation measuring instrument of claim 1, wherein the host computer comprises: the device comprises a rechargeable battery, a main control circuit, a power supply conversion circuit, a first counting tube detector, an amplifying circuit, a micro control circuit and a display terminal;
the rechargeable battery is electrically connected with the input end of the main control circuit, the output end of the main control circuit is electrically connected with the input end of the power supply conversion circuit, the output end of the power supply conversion circuit is electrically connected with the input end of the first counting tube detector, the output end of the first counting tube detector is electrically connected with the amplifying circuit, and the amplifying circuit is connected with the display terminal through the micro control circuit.
3. The portable radiation measuring instrument of claim 1, wherein said first probe comprises: the detector comprises a first scintillator detector, a first photomultiplier transistor, a first pulse width discriminator, a second counting tube detector and a first signal processor;
the first scintillator detector is used for detecting the dosage values of alpha particles and beta particles, the second counting tube detector is used for detecting the dosage values of gamma particles, and the first scintillator detector and the second counting tube detector are arranged in parallel to each other along the detection axis direction;
the first scintillator detector is electrically connected with the input end of the first photomultiplier, the output end of the first photomultiplier is electrically connected with the input end of the first pulse width discriminator, and the output end of the first pulse width discriminator and the second counting tube detector are respectively electrically connected with the first signal processor.
4. The portable radiation measuring instrument of claim 1, wherein the second probe comprises: the detector comprises a second scintillator detector, a second photomultiplier transistor, a second pulse width discriminator, a third counting tube detector, a first inorganic crystal detector and a second signal processor;
the second scintillator detector is used for detecting the dosage value of beta particles, and the third counting tube detector and the first inorganic crystal detector are used for detecting the dosage value of gamma particles;
the second scintillator detector is electrically connected with the input end of the second photomultiplier, the output end of the second photomultiplier is electrically connected with the input end of the second pulse width discriminator, and the output end of the second pulse width discriminator, the third counting tube detector and the first inorganic crystal detector are respectively electrically connected with the signal processor.
5. The portable radiation measuring instrument of claim 1, wherein the third probe comprises: a second inorganic crystal detector, a third photomultiplier transistor, and a third signal processor;
the second inorganic crystal detector is used for detecting the dosage value of neutrons;
the second inorganic crystal detector is electrically connected with the input end of the third photomultiplier transistor, and the output end of the third photomultiplier transistor is electrically connected with the third signal processor.
6. The portable radiation measuring instrument of claim 3, wherein the first scintillator detector comprises a plastic scintillator, and a surface of the plastic scintillator is coated with a film layer formed of a silver-doped zinc sulfide material.
7. The portable radiation measuring instrument of claim 4, wherein the second scintillator detector comprises a plastic scintillator, and a surface of the plastic scintillator is coated with a film layer formed of a silver-doped zinc sulfide material.
8. The portable radiation measuring instrument of claim 4, wherein the first inorganic crystal detector is a bismuth germanate crystal detector.
9. The portable radiometer of claim 1, wherein the host computer provides a dc voltage of 5V to the multifunction detector.
10. The portable radiation measuring apparatus of claim 1, wherein the host computer and the multifunctional detector communicate with each other based on RS485 protocol.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202221885713.7U CN218412918U (en) | 2022-07-20 | 2022-07-20 | Portable radiation measuring instrument |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202221885713.7U CN218412918U (en) | 2022-07-20 | 2022-07-20 | Portable radiation measuring instrument |
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| CN218412918U true CN218412918U (en) | 2023-01-31 |
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| CN202221885713.7U Active CN218412918U (en) | 2022-07-20 | 2022-07-20 | Portable radiation measuring instrument |
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