Miniature dosimeter detection device

Abstract

The utility model discloses a miniature dosimeter detection device which comprises a nuclear radiation monitoring assembly, a Geiger counting tube, a cover plate, a main shell and an upper computer server. The nuclear radiation monitoring assembly and the Geiger counting tube are fixed in the main shell; the nuclear radiation monitoring assembly comprises a main control board and a high-voltage board. The main control board comprises a low-voltage power supply, a main control chip, a signal processing module, a serial port conversion chip and a Type-c interface; the high-voltage board comprises a high-voltage bias power supply which is electrically connected with the main control board and the Geiger counting tube; the Geiger counting tube comprises a low-range Geiger counting tube and a high-range Geiger counting tube which are electrically connected with the main control board and the high-voltage board respectively; the Type-c interface is electrically connected with the main control board, and communication and power supply integrated transmission is achieved through the Type-c interface and an upper computer server. The device is low in power consumption, small in size, convenient to carry and flexible and simple to operate.

Description

TECHNICAL FIELD

[0001] The utility model relates to the field of nuclear radiation detection, and particularly relates to a microdosimeter detection device. BACKGROUND

[0002] Radiation environment monitoring and measurement is a protective measure necessarily used in the fields of nuclear energy, radiotherapy, nuclear medicine and the like, and the measurement methods include various methods such as a scintillation detector, an ionization chamber and a semiconductor detector. A Geiger counter tube is a commonly used nuclear radiation detector, and since its advent, it has become the most widely used nuclear radiation detector due to its outstanding characteristics such as simple manufacturing, high cost performance, good environmental adaptability, large output pulse amplitude and easy operation. However, the Geiger counter tube also has obvious disadvantages, such as a plateau curve, dead time and failure time of the counter tube, inability to distinguish the type and energy of particles, pulse overlap and the like, so that its use is limited to a very narrow range. The conventional measurement method cannot fundamentally solve the problem caused by the dead time, thereby causing measurement error and leading to reduced measurement efficiency. SUMMARY

[0003] The utility model aims at overcoming the above-mentioned problems, and provides a microdosimeter detection device, which has the advantages of small size, convenience in carrying and good flexibility, and solves the inconvenience in carrying and moving of the existing fixed nuclear radiation detection and sampling device.

[0004] The utility model discloses a microdosimeter detection device, which has the advantages of small size, convenience in carrying and good flexibility, and solves the inconvenience in carrying and moving of the existing fixed nuclear radiation detection and sampling device.

[0005] The utility model discloses a microdosimeter detection device, which has the advantages of small size, convenience in carrying and good flexibility, and solves the inconvenience in carrying and moving of the existing fixed nuclear radiation detection and sampling device.

[0006] The working principle of the microdosimeter detection device is as follows:

[0007] In operation, the dosimeter probe is designed with a Type-c interface, and communication and power supply are transmitted integrally, facilitating system integration, and the interface obtains +5V voltage to supply power to the whole dosimeter probe, and the signal processing module, serial conversion chip, high-voltage bias power supply and low-voltage power supply required by the main control board are obtained through the power conversion circuit. The Geiger-Muller tube converts the detected gamma rays into original nuclear pulse signals. Then the signal amplitude is amplified without distortion and with high signal-to-noise ratio, and then the nuclear pulse signal is converted into a square wave pulse through waveform conversion and sent to the signal acquisition port of the main control board for pulse counting and other data processing. Through standard radioactive source calibration, the functional relationship between pulse count and radiation dose is obtained, so as to realize the conversion of pulse count to dose rate. Finally, data transmission is performed with the host computer server through the Type-c interface.

[0008] In an preferred embodiment of the present application, the Geiger-Muller tube includes a low-range Geiger-Muller tube and a high-range Geiger-Muller tube, thereby meeting the wide-range measurement range.

[0009] In an preferred embodiment of the present application, the main control board and the high-voltage board are fixed through three positioning holes.

[0010] In an preferred embodiment of the present application, the main housing and the cover plate are made of resin material, and the cover plate is further provided with three threaded studs for mounting and fixing the main control board.

[0011] In a further technical solution of the present application, the cover plate is provided with a Type-c slot opening for placing the Type-c interface on the main control board.

[0012] In a further technical solution of the present application, the cover plate is further provided with a power indicator light and a communication indicator light, which are electrically connected with the main control board respectively.

[0013] In a further technical solution of the present application, the cover plate is further provided with four M2.5 longitudinal positioning holes for mounting and fixing with the main housing.

[0014] In an preferred embodiment of the present application, the main housing is provided with a partition cylinder, and the partition cylinder is provided with a first storage cavity for placing the low-range Geiger-Muller tube and a second storage cavity for placing the high-range Geiger-Muller tube.

[0015] Compared with the prior art, the present application has the following advantages:

[0016] The miniature dosimeter probe device of the present application is integrated with communication and power supply through the Type-c interface, has small volume, is convenient to carry, is convenient to install on various additional equipment, and has good flexibility.

[0017] The microdosimeter detection device of the utility model discloses a low range and high range two models of g-M counter tube combination use mode, thereby improving the measurement range, so as to satisfy the test environment of various conditions. BRIEF DESCRIPTION OF DRAWINGS

[0018] Figure 1 It is the whole schematic diagram of the microdosimeter detection device of the utility model.

[0019] Figure 2 It is the three-dimensional structure explosion schematic diagram of the microdosimeter detection system of the utility model. DETAILED DESCRIPTION

[0020] In order to make those skilled in the art well understand the technical scheme of the utility model, the utility model is further described below in combination with examples and drawings, but the implementation of the utility model is not limited to this.

[0021] As Figures 1-2 The microdosimeter detection device of the embodiment includes nuclear radiation monitoring assembly, g-M counter tube, cover plate 3, main shell 1 and host computer server 19, and the host computer server 19 is composed of working computer.

[0022] As Figures 1-2 The nuclear radiation monitoring assembly and g-M counter tube are all arranged in the main shell 1, the nuclear radiation monitoring assembly includes main control board 8 and high voltage plate 14, and the g-M counter tube includes low range g-M counter tube 16 and high range g-M counter tube 17.

[0023] As Figures 1-2 The shell includes shell cover 3 and main shell 1, and the shell cover 3 and main shell 1 are made of resin material.

[0024] As Figures 1-2 The main shell is provided with a separation cylinder, a first storage cavity 18-1 for placing low range g-M counter tube 16 and a second storage cavity 18-2 for placing high range g-M counter tube 17.

[0025] Among them, g-M counter tube is favored with its high sensitivity, good environmental adaptability, large output pulse amplitude, easy operation and economical and practical price, especially suitable for measuring radiation environmental dose rate, characterizing the strength of radiation field, and is the most widely used nuclear radiation detector at present.

[0026] As Figures 1-2 The cover plate 3 is installed and fixed with the main shell 1 through four positioning holes 2 of M2.5.

[0027] Further, the cover plate 3 is also provided with three stud bolts 6, and the stud bolts 6 are used for installing and fixing the main control board (8).

[0028] Furthermore, the cover plate 3 is also equipped with a power indicator light 5-1 and a communication indicator light 5-2, which are electrically connected to the main control board 8 respectively.

[0029] like Figure 2 As shown, the main control board 14 includes a Type-C interface 7, a low-voltage power management circuit 9, a main control chip 10, a signal processing module 11, and a serial port conversion chip 12; the high-voltage board 14 includes a high-voltage bias power supply 15, which is electrically connected to the main control board 8 and the Geiger counter tube; the Type-C interface 7 is electrically connected to the main control board 8.

[0030] Specifically, the Type-C interface 7 is powered by 5V, which is stepped down to 3.3V through the low-voltage power management circuit 9 to power the main control chip 10, signal processing module 11, serial port conversion chip 12, and other low-voltage components. The main control chip 10 is an STM32F103 series microcontroller, which in this device receives pulse signals, records time data, controls high-low voltage conversion, and communicates with the host computer 19.

[0031] See Figures 1-2 The working principle of the miniature dosimeter detection device in this embodiment is as follows:

[0032] During operation, the dosimeter detection design utilizes a Type-C interface 7, integrating communication and power supply for convenient system integration. The interface provides +5V to power the entire dosimeter detection device, which is then supplied via a low-voltage power management circuit 9 to the signal processing module 11, serial port conversion chip 12, high-voltage bias power supply 13, and the low-voltage power required by the main control board. The Geiger counter converts the detected gamma rays into raw nuclear pulse signals. The signal processing module then amplifies the signal amplitude without distortion and with a high signal-to-noise ratio. After waveform transformation, the nuclear pulse signal is converted into a square wave pulse and sent to the signal acquisition port of the main control board 8 for pulse counting and other data processing. Dose calibration is performed using a standard radiation source to obtain the functional relationship between pulse count and radiation dose, thus realizing the conversion from pulse count to dose rate. Finally, data is transmitted to the host computer server 19 via the Type-C interface 7.

[0033] After receiving the detection data, the host computer server 19 can perform functions such as data storage, real-time data processing, pulse counting, dose conversion calculation, and dose mapping.

[0034] The above are preferred embodiments of the present utility model, but the embodiments of the present utility model are not limited to the above content. Any changes, modifications, substitutions, combinations, or simplifications made without departing from the spirit and principle of the present utility model shall be considered equivalent substitutions and shall be included within the protection scope of the present utility model.

Claims

1. A microdosimeter detection device, characterized by: It includes nuclear radiation monitoring components, Geiger counter, cover plate (3), main shell (1) and host computer server (19); The nuclear radiation monitoring components and the Geiger counter are arranged in the main shell (1); the nuclear radiation monitoring components include a main control board (8) and a high-voltage board (14); the main control board (14) includes a Type-c interface (7), a low-voltage power management circuit (9), a main control chip (10), a signal processing module (11), and a serial port conversion chip (12); the high-voltage board (14) includes a high-voltage bias power supply (15) and is electrically connected with the main control board (8) and the Geiger counter; the Type-c interface (7) is electrically connected with the main control board (8), and the Type-c interface (7) and the host computer server (19) realize integrated transmission of communication and power supply.

2. The microdosimeter probe of claim 1, wherein: The Geiger counter includes a low-range Geiger counter (16) and a high-range Geiger counter (17).

3. The microdosimeter probe of claim 1, wherein: The main control board (8) and the high-voltage board (14) are fixed through three positioning holes (13).

4. The microdosimeter probe of claim 1, wherein: The main shell (1) and the cover plate (3) are made of resin material.

5. The microdosimeter probe of claim 1, wherein: The cover plate (3) is provided with a Type-c card slot (4) for placing the Type-c interface (7) on the main control board (8).

6. The microdosimeter probe of claim 4, wherein: The cover plate (3) is also provided with a power indicator light (5-1) and a communication indicator light (5-2), which are electrically connected with the main control board (8), respectively.

7. The microdosimeter probe of claim 4, wherein: The cover plate (3) is also provided with three threaded studs (6) for mounting and fixing the main control board (8).

8. The microdosimeter probe of claim 4, wherein: The cover plate (3) is mounted and fixed with the main shell (1) through four M2.5 positioning holes (2).

9. The microdosimeter probe of claim 4, wherein: The main shell is provided with a separation cylinder, and the separation cylinder is provided with a first receiving cavity (18-1) for placing the low-range Geiger counter (16) and a second receiving cavity (18-2) for placing the high-range Geiger counter (17).

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