CN204575860U - Portable gamma-ray spectrometer - Google Patents
Portable gamma-ray spectrometer Download PDFInfo
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- CN204575860U CN204575860U CN201520230114.5U CN201520230114U CN204575860U CN 204575860 U CN204575860 U CN 204575860U CN 201520230114 U CN201520230114 U CN 201520230114U CN 204575860 U CN204575860 U CN 204575860U
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Abstract
The utility model discloses a kind of portable gamma-ray spectrometer, comprise natural nuclide module, detector, photomultiplier, emitter follower, processing unit, display unit, high-voltage power supply and power supply unit; Detector and photomultiplier are of coupled connections by couplant; Photomultiplier connects emitter follower and high-voltage power supply; Emitter follower connection handling unit; Processing unit is connected with display unit; Power supply unit connects display unit and processing unit; Detector comprises metal shell, flicker crystalline solid and plastic protection layer; flicker crystalline solid is placed in metal shell; plastic protection layer is wrapped in outside metal shell; metal shell is provided with detection mouth; detection mouth is just to natural nuclide module, and natural nuclide module is less than the surface area of detection mouth towards the obverse area detecting mouth.The utility model adopts built-in pure potassium nitrate in natural nuclide module to carry out spectrum stabilization, improves the security of operating process, overcomes the problem producing temperature drift phenomenon.
Description
Technical field
The utility model relates to nucleic and detects analysis technical field, relates in particular to a kind of portable gamma-ray spectrometer.
Background technology
Along with the popularization and application of nuclear technology, people more or less can touch artificial radioactivity material in life, so in environmental monitoring, inspection and quarantining for import/export, the healthy prevention and core anti-terrorism etc., all will relate to the identification of radioactive nuclide.Portable gamma spectrometer outside Present Domestic mainly comprises the Portable nuclide identification instrument and electroluminescent cold pured germanium crystal spectrometer that adopt sodium iodide (NaI) scintillator.But sodium iodide scintillator temperature influence is larger, causes spectrometer instability, there is temperature drift phenomenon, need extra built-in nucleic to carry out the stable of spectrogram.The mode of this endoprosthetic's radioactive source also exists risk to a certain degree.And the technology of electroluminescent cold pured germanium crystal spectrometer exists size comparatively greatly, portable inconvenience, expensive problem, is difficult to popularize at industry-by-industry.In sum, how designing a kind of portable gamma spectrometer overcoming above-mentioned technical barrier is the problem that those skilled in the art need solution badly.
Utility model content
For solving the problem, the utility model provides a kind of portable gamma-ray spectrometer.
Concrete technical scheme of the present utility model is as follows:
A kind of portable gamma-ray spectrometer, comprises natural nuclide module, detector, photomultiplier, emitter follower, processing unit, display unit, high-voltage power supply and power supply unit; Described detector and photomultiplier are of coupled connections by couplant; Described photomultiplier connects emitter follower and high-voltage power supply respectively; Described emitter follower connection handling unit; Described processing unit is connected with display unit; Described power supply unit connects display unit and processing unit; Described detector comprises metal shell, flicker crystalline solid and plastic protection layer; described flicker crystalline solid is placed in metal shell; described plastic protection layer is wrapped in outside metal shell; described metal shell is provided with spy lateral opening; described detection mouth is just to natural nuclide module, and described natural nuclide module is less than towards the obverse area of detection mouth the surface area detecting mouth.
By adopting this technical scheme: utilize the natural nuclide module being positioned at detector outside to realize spectrum stabilization, evaded the problem that man-made source is built in detector by conventional portable gamma-ray spectrometer, improve the security of operating process.
Preferably, in above-mentioned portable gamma-ray spectrometer: described natural nuclide module comprises screening can, window and pure potassium nitrate; Described screening can and window form an airtight cavity, and described pure potassium nitrate is placed in this airtight cavity; Described window is relative with detection mouth.
By adopting this technical scheme: adopt built-in pure potassium nitrate in natural nuclide module to carry out spectrum stabilization, it is safer, stable that pure potassium nitrate compares artificial radionuclide spectrum stabilization.
It is further preferred that in above-mentioned portable gamma-ray spectrometer: described screening can adopts radiation shielding material to form, described window adopts organic film to form, and described flicker crystalline solid adopts CsI scintillator.
By adopting this technical scheme: using CsI scintillator as gamma detecting element, utilize it sensitive to gamma radiation response, measurement environment ambient radiation level, or accumulative radiation dose, CsI scintillator is less sensitive to temperature relative to NaI scintillation crystal simultaneously, overcomes the problem producing temperature drift phenomenon.
Compared with prior art, the utility model adopts built-in pure potassium nitrate in natural nuclide module to carry out spectrum stabilization, evade the problem that man-made source is built in detector by conventional portable gamma-ray spectrometer, improve the security of operating process, overcome the problem producing temperature drift phenomenon.
Accompanying drawing explanation
Fig. 1 is the structural representation of the utility model embodiment 1;
Fig. 2 is the structural representation of natural nuclide module in Fig. 1;
Fig. 3 is the structural representation of detector in Fig. 1.
In above-mentioned accompanying drawing, the corresponding relation of each parts and Reference numeral is as follows:
1, natural nuclide module; 2, detector; 3, photomultiplier; 4, emitter follower; 5, processing unit; 6, display unit; 7, high-voltage power supply; 8, power supply unit; 11, screening can; 12, window; 13, pure potassium nitrate; 21, metal shell; 22, plastic protection layer; 23, scintillation crystal; 211, mouth is detected.
Embodiment
In order to be illustrated more clearly in the technical solution of the utility model, below in conjunction with accompanying drawing, the utility model is further described.
The utility model embodiment 1 as Figure 1-3:
A kind of portable gamma-ray spectrometer, comprises natural nuclide module 1, detector 2, photomultiplier 3, emitter follower 4, processing unit 5, display unit 6, high-voltage power supply 7 and power supply unit 8; Described detector 2 is of coupled connections by couplant with photomultiplier 3; Described photomultiplier 3 connects emitter follower 4 and high-voltage power supply 7 respectively; Described emitter follower 4 connection handling unit 5; Described processing unit 5 is connected with display unit 6; Described power supply unit 8 connects display unit 6 and processing unit 5; Described detector 2 comprises metal shell 21, flicker crystalline solid 22 and plastic protection layer 23, and described flicker crystalline solid 22 adopts CsI scintillator.This CsI scintillator is placed in metal shell 21, and described plastic protection layer 23 is wrapped in outside metal shell 21, and described metal shell 21 is provided with visits lateral opening 211.Described detection mouth 211 is just to natural nuclide module 1, and described natural nuclide module 1 is less than towards the obverse area of detection mouth 211 surface area detecting mouth 211.Described natural nuclide module 1 comprises screening can 11, window 12 and pure potassium nitrate 13; Described screening can 11 adopts radiation shielding material to form, and described window 12 adopts organic film to form.Described screening can 11 and window 12 form an airtight cavity, and described pure potassium nitrate 13 is placed in this airtight cavity; Described window 12 is relative with spy lateral opening 211.
The said goods is adopted to carry out corresponding experiment measuring, under 137Cs source, the gamma sensitivity recorded is for being greater than 2000 CPS/(μ Sv.h-1), the index of above sensitivity is all in forward level in same quasi-instrument, Radionuclide analysis is no more than 100 seconds in background situation, carries out spectrum stabilization by natural nuclide.Gamma-ray spectrometry identifier of the present utility model successfully achieves natural nuclide spectrum stabilization, the advantage such as highly sensitive, portable simultaneously.
The above; be only specific embodiment of the utility model; but protection domain of the present utility model is not limited thereto; the technician of any skilled is in technical scope disclosed in the utility model; the change that can expect easily or replacement, all should be encompassed within protection domain of the present utility model.Protection domain of the present utility model is as the criterion with the protection domain of claims.
Claims (4)
1. a portable gamma-ray spectrometer, is characterized in that: comprise natural nuclide module (1), detector (2), photomultiplier (3), emitter follower (4), processing unit (5), display unit (6), high-voltage power supply (7) and power supply unit (8); Described detector (2) and photomultiplier (3) are of coupled connections by couplant; Described photomultiplier (3) connects emitter follower (4) and high-voltage power supply (7) respectively; Described emitter follower (4) connection handling unit (5); Described processing unit (5) is connected with display unit (6); Described power supply unit (8) connects display unit (6) and processing unit (5); Described detector (2) comprises metal shell (21), flicker crystalline solid (22) and plastic protection layer (23); described flicker crystalline solid (22) is placed in metal shell (21); described plastic protection layer (23) is wrapped in metal shell (21) outside; described metal shell (21) is provided with visits lateral opening (211); described detection mouth (211) is just to natural nuclide module (1), and described natural nuclide module (1) is less than towards the obverse area of detection mouth (211) surface area detecting mouth (211).
2. a kind of portable gamma-ray spectrometer as claimed in claim 1, is characterized in that: described natural nuclide module (1) comprises screening can (11), window (12) and pure potassium nitrate (13); Described screening can (11) and window (12) form an airtight cavity, and described pure potassium nitrate (13) is placed in this airtight cavity; Described window (12) is relative with spy lateral opening (211).
3. a kind of portable gamma-ray spectrometer as claimed in claim 2, is characterized in that: described screening can (11) adopts radiation shielding material to form, and described window (12) adopts organic film to form.
4. a kind of portable gamma-ray spectrometer as claimed in claim 3, is characterized in that: described flicker crystalline solid (22) adopts cesium iodide (CsI) scintillator.
Priority Applications (1)
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CN201520230114.5U CN204575860U (en) | 2015-04-16 | 2015-04-16 | Portable gamma-ray spectrometer |
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CN201520230114.5U CN204575860U (en) | 2015-04-16 | 2015-04-16 | Portable gamma-ray spectrometer |
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CN201520230114.5U Expired - Fee Related CN204575860U (en) | 2015-04-16 | 2015-04-16 | Portable gamma-ray spectrometer |
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Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN105572715A (en) * | 2015-12-18 | 2016-05-11 | 山东省科学院海洋仪器仪表研究所 | Temperature drift self-correction method of sea radioactivity measurement sensor, and sensor |
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2015
- 2015-04-16 CN CN201520230114.5U patent/CN204575860U/en not_active Expired - Fee Related
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN105572715A (en) * | 2015-12-18 | 2016-05-11 | 山东省科学院海洋仪器仪表研究所 | Temperature drift self-correction method of sea radioactivity measurement sensor, and sensor |
CN105572715B (en) * | 2015-12-18 | 2018-10-26 | 山东省科学院海洋仪器仪表研究所 | The temperature drift automatic correcting method and sensor of Marine Radioactivity measurement sensor |
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CF01 | Termination of patent right due to non-payment of annual fee | ||
CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20150819 |