CN201600459U - Digital gamma radiation detector - Google Patents
Digital gamma radiation detector Download PDFInfo
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- CN201600459U CN201600459U CN2010201156175U CN201020115617U CN201600459U CN 201600459 U CN201600459 U CN 201600459U CN 2010201156175 U CN2010201156175 U CN 2010201156175U CN 201020115617 U CN201020115617 U CN 201020115617U CN 201600459 U CN201600459 U CN 201600459U
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Abstract
A digital gamma radiation detector comprises a high-voltage adjusting unit, a data processing unit and a communication unit which are sequentially connected. The high-voltage adjusting unit is respectively connected with two detection sensors with different measuring ranges; the detection sensors with different measuring ranges are used for measuring respective dose fields and transmitting measuring signals to the high-voltage adjusting unit; the high-voltage adjusting unit used for receiving the signals transmitted by the detection sensors adjusts and processes the received signals and transmits the processed signals to the data processing unit; the data processing unit used for receiving the signals transmitted by the high-voltage adjusting unit digitally processes the received signals to form digital data and transmits the digital data to the communication unit; and the communication unit used for receiving the digital data transmitted by the data processing unit transmits the digital data outwards through a data interface. The detector is used for measuring different dose fields, and broadens the measuring ranges of detectors.
Description
Technical field
The utility model product belongs to a kind of detector in the nuclear detection technology field, and concrete function is a kind of digital gamma radiation detector.
Background technology
In the utilization and storing process of nuclear matter, the nuclear radiation that can produce various dose for effectively control and protection nuclear radiation, needs the dosage of nuclear radiation is monitored.At present, the detector of monitoring nuclear radiation dosage is the different low dose of detector of range ability, when nuclear radiation dosage is big, can only be with the combinations of detectors of two different range abilities, realizing measurement than wide-range, and, the lower range detector can only be used for low dose of, the high range detector can only be used for heavy dose of, can not exchange: measure if the lower range detector is applied to heavy dose of, then can cause the infringement that can not repair to the acquisition sensor of detector inside; If the detector with high range carries out the low dosage measurement, then detector sensitivity is not enough.Existing detector exists mostly that sensitivity is low, problems such as response speed is slow, stability and poor reliability.
Summary of the invention
In order to overcome above-mentioned problems of the prior art, the purpose of this utility model provides a kind of digital gamma radiation detector, has the range of broad and higher sensitivity, can be used for the measurement of various dose field.
The technical scheme that the utility model adopted is, the numeral gamma radiation detector comprises high pressure adjustment unit 3, data processing unit 4 and the communication unit 5 that is connected successively, high pressure adjustment unit 3 also is connected with the acquisition sensor of two different ranges respectively, wherein
The acquisition sensor of two different ranges is used for the measurement of corresponding dosage field, and measuring-signal is transferred to high pressure adjustment unit 3;
High pressure adjustment unit 3 is used to receive the signal that acquisition sensor transmits, and adjust processing to the received signal, and the signal after will handling transfers to data processing unit 4;
Communication unit 5 is used to receive the numerical data that data processing unit 4 transmits, and this numerical data is outwards transmitted by data-interface.
The acquisition sensor of described two different ranges is a high range acquisition sensor and a lower range acquisition sensor.
The data processing unit processor that described data processing unit 4 adopts master chip W77E516 to be formed.
Described communication unit 5 adopts the communication unit of communication with MAX485 chip communication mode.
Described data-interface adopts RS485.
The acquisition sensor of built-in two the different ranges of the utility model detector, can be used for the measurement of various dose field, avoid lower range detector measurement heavy dose to cause acquisition sensor can not repair the problem of infringement and high range detector measurement low dosage insufficient sensitivity.Realized surveying widening of range, have highly sensitive, response speed is fast, reliability is high and the characteristics of good stability.
Description of drawings
Fig. 1 is the structural representation of a kind of embodiment of the utility model detector.
Among the figure, 1. first acquisition sensor, 2. second acquisition sensor, 3. high pressure adjustment unit, 4. data processing unit, 5. communication unit.
Embodiment
Below in conjunction with the drawings and specific embodiments the utility model is elaborated.
As shown in Figure 1, the structure of the utility model detector comprises the high pressure adjustment unit 3, data processing unit 4 and the communication unit 5 that are connected successively, and high pressure adjustment unit 3 also is connected with second acquisition sensor 2 with first acquisition sensor 1 respectively.
First acquisition sensor 1 adopts the lower range acquisition sensor, is used for the measurement of corresponding dosage field, and measuring-signal is transferred to high pressure adjustment unit 3;
Second acquisition sensor 2 adopts the high range acquisition sensor, is used for the measurement of corresponding dosage field, and measuring-signal is transferred to high pressure adjustment unit 3;
High pressure adjustment unit 3 is used to receive the signal that first acquisition sensor 1 and second acquisition sensor 2 transmit, and adjust processing to the received signal, and the signal after will handling transfers to data processing unit 4;
Communication unit 5 adopts the communication unit of communication with MAX485 chip communication mode, is used to receive the numerical data that data processing unit 4 transmits, and this numerical data is outwards transmitted by the RS485 data-interface.
The utility model detector operation process:
This detector is placed the dosage field that needs measurement, and single-chip microcomputer is adjusted which acquisition sensor of use automatically by the size of actual measurement counting, earlier from extracting the counting of lower range sensor.Acquisition sensor is converted to signal with measurement result, and this signal transferred to high pressure adjustment unit 3, high pressure adjustment unit 3 is adjusted processing with the signal that receives, and the signal after will handling transfers to data processing unit 4, data processing unit 4 carries out digitized processing to the received signal, form numerical data, and this numerical data is passed to communication unit 5, communication unit 5 outwards transmits the numerical data that receives by data-interface.
The acquisition sensor of built-in two the different ranges of the utility model detector, by corresponding " survey and switch " and data processing, widened the range ability of detector, measurement result is carried out digitized processing, carry out telecommunication by the RS485 data-interface, realize digitized processing detectable signal.Have highly sensitive, response speed is fast, reliability is high and the characteristics of good stability, when not only having avoided the lower range detector measurement heavy dose of, inner acquisition sensor is caused the phenomenon that to repair infringement, when also having avoided high range detector measurement low dosage simultaneously, measure the problem of insufficient sensitivity.
The utility model detector is used for the environment place, and its range is 0.01～1 * 10
7μ Sv/h is used to examine application places, and its range is 0.05～1 * 10
7μ Sv/h.
Claims (5)
1. digital gamma radiation detector is characterized in that, comprises the high pressure adjustment unit (3), data processing unit (4) and the communication unit (5) that are connected successively, and high pressure adjustment unit (3) also is connected with the acquisition sensor of two different ranges respectively, wherein,
The acquisition sensor of two different ranges is used for the measurement of corresponding dosage field, and measuring-signal is transferred to high pressure adjustment unit (3);
High pressure adjustment unit (3) is used to receive the signal that acquisition sensor transmits, and adjust processing to the received signal, and the signal after will handling transfers to data processing unit (4);
Data processing unit (4) is used to receive the signal that high pressure adjustment unit (3) transmits, and carries out digitized processing to the received signal, forms numerical data, and with this digital data transmission to communication unit (5);
Communication unit (5) is used to receive the numerical data that data processing unit (4) transmits, and this numerical data is outwards transmitted by data-interface.
2. detector according to claim 1 is characterized in that, the acquisition sensor of described two different ranges is a high range acquisition sensor and a lower range acquisition sensor.
3. detector according to claim 1 is characterized in that, the data processing unit processor that described data processing unit (4) adopts master chip W77E516 to be formed.
4. detector according to claim 1 is characterized in that, described communication unit (5) adopts the communication unit of communication with MAX485 chip communication mode.
5. detector according to claim 1 is characterized in that, described data-interface adopts RS485.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2010201156175U CN201600459U (en) | 2010-02-10 | 2010-02-10 | Digital gamma radiation detector |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2010201156175U CN201600459U (en) | 2010-02-10 | 2010-02-10 | Digital gamma radiation detector |
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| CN201600459U true CN201600459U (en) | 2010-10-06 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN2010201156175U Expired - Fee Related CN201600459U (en) | 2010-02-10 | 2010-02-10 | Digital gamma radiation detector |
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Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103163545A (en) * | 2013-02-26 | 2013-06-19 | 河北省电力公司电力科学研究院 | Radial measuring instrument for measuring radial dosage |
| CN106662656A (en) * | 2014-08-26 | 2017-05-10 | 三菱电机株式会社 | Dose rate measurement device |
| CN106814387A (en) * | 2017-01-24 | 2017-06-09 | 陕西卫峰核电子有限公司 | A kind of nuclear critical accident detector |
| CN106842279A (en) * | 2017-01-24 | 2017-06-13 | 陕西卫峰核电子有限公司 | The detection method and detector of a kind of nuclear critical accident |
| CN108158597A (en) * | 2016-12-07 | 2018-06-15 | 北京东软医疗设备有限公司 | Determine the method, apparatus and CT equipment of original X-rays energy datum |
| CN112415569A (en) * | 2020-10-30 | 2021-02-26 | 湖北锐世数字医学影像科技有限公司 | Energy correction method, device, equipment, system and computer readable storage medium |
-
2010
- 2010-02-10 CN CN2010201156175U patent/CN201600459U/en not_active Expired - Fee Related
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103163545A (en) * | 2013-02-26 | 2013-06-19 | 河北省电力公司电力科学研究院 | Radial measuring instrument for measuring radial dosage |
| CN103163545B (en) * | 2013-02-26 | 2015-09-30 | 国电锅炉压力容器检验中心 | A kind of ray meter measuring roentgen dose X |
| CN106662656A (en) * | 2014-08-26 | 2017-05-10 | 三菱电机株式会社 | Dose rate measurement device |
| CN106662656B (en) * | 2014-08-26 | 2019-01-08 | 三菱电机株式会社 | Dosage rate measurement device |
| CN108158597A (en) * | 2016-12-07 | 2018-06-15 | 北京东软医疗设备有限公司 | Determine the method, apparatus and CT equipment of original X-rays energy datum |
| CN108158597B (en) * | 2016-12-07 | 2021-08-06 | 北京东软医疗设备有限公司 | Method and device for determining original X-ray energy data and CT (computed tomography) equipment |
| CN106814387A (en) * | 2017-01-24 | 2017-06-09 | 陕西卫峰核电子有限公司 | A kind of nuclear critical accident detector |
| CN106842279A (en) * | 2017-01-24 | 2017-06-13 | 陕西卫峰核电子有限公司 | The detection method and detector of a kind of nuclear critical accident |
| CN112415569A (en) * | 2020-10-30 | 2021-02-26 | 湖北锐世数字医学影像科技有限公司 | Energy correction method, device, equipment, system and computer readable storage medium |
| CN112415569B (en) * | 2020-10-30 | 2022-06-17 | 湖北锐世数字医学影像科技有限公司 | Energy correction method, device, equipment, system and computer readable storage medium |
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Legal Events
| Date | Code | Title | Description |
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| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| C17 | Cessation of patent right | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20101006 Termination date: 20140210 |