CN111290010A - Device and method for detecting concentration of radioactive airborne effluents - Google Patents

Device and method for detecting concentration of radioactive airborne effluents Download PDF

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Publication number
CN111290010A
CN111290010A CN201811494376.7A CN201811494376A CN111290010A CN 111290010 A CN111290010 A CN 111290010A CN 201811494376 A CN201811494376 A CN 201811494376A CN 111290010 A CN111290010 A CN 111290010A
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China
Prior art keywords
sampling
filter box
radioactive
gas
throttle valve
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CN201811494376.7A
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Chinese (zh)
Inventor
王镇
王健
周成龙
敬加君
石秀高
刘国良
刘程远
刘恩鹏
张坤
杨庆祥
张亚超
程波波
王秋枫
汪南杰
陈勤
任正茂
李吉花
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404 Co Ltd China National Nuclear Corp
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404 Co Ltd China National Nuclear Corp
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Priority to CN201811494376.7A priority Critical patent/CN111290010A/en
Publication of CN111290010A publication Critical patent/CN111290010A/en
Pending legal-status Critical Current

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    • GPHYSICS
    • G01MEASURING; TESTING
    • G01TMEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T1/00Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
    • G01T1/16Measuring radiation intensity
    • G01T1/17Circuit arrangements not adapted to a particular type of detector
    • G01T1/178Circuit arrangements not adapted to a particular type of detector for measuring specific activity in the presence of other radioactive substances, e.g. natural, in the air or in liquids such as rain water

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  • Physics & Mathematics (AREA)
  • Health & Medical Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Physics & Mathematics (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Molecular Biology (AREA)
  • Spectroscopy & Molecular Physics (AREA)
  • Measurement Of Radiation (AREA)
  • Sampling And Sample Adjustment (AREA)

Abstract

The invention relates to the technical field of radioactive gas detection, and particularly discloses a radioactive gas carrying effluent concentration detection device and a method. The detection method comprises the following steps: the method comprises the following steps: filling filter paper; step two: starting the detection device; step three: setting sampling parameters; step four: and (4) processing the sample. The invention has simple operation, can continuously and stably run for a long time, completely avoids the problem of corrosion of acid gas in process exhaust on the probe of the monitor, and has accurate and reliable measurement data.

Description

Device and method for detecting concentration of radioactive airborne effluents
Technical Field
The invention belongs to the technical field of radioactive gas detection, and particularly relates to a device and a method for detecting the concentration of a radioactive gas carrier effluent.
Background
Factory radioactive gas carrying effluents mainly come from a process exhaust system and a factory exhaust system, and an energy discrimination method is usually adopted, namely an iCAM type aerosol continuous monitor is adopted to continuously monitor the radioactivity level of the discharged gas.
In addition, the iCAM type aerosol continuous monitor realizes the self-adaptive spectrum compensation of radon and thorium splinter elements by α spectrum analysis and correlation calculation β to deduct the influence of radon and thorium daughter on the measurement result in real time, and because the radon and the thorium daughter and the artificial radionuclide α have different particle energies, a semiconductor detector with energy resolution is adopted to screen the radon and the thorium and the daughter, such as a particle injection type silicon detector, and the contribution of the radon and the thorium and the daughter is deducted to obtain the concentration of the artificial radionuclide.
Disclosure of Invention
The invention aims to provide a radioactive gas carrying effluent concentration detection device and a method thereof, so as to ensure the discharge safety of radioactive gas.
The technical scheme of the invention is as follows:
a radioactive gas carrier effluent concentration detection device comprises a manual stop valve, a sampling filter box A, a sampling filter box B, a pressure gauge, a gas flowmeter, a manual throttle valve A, a sampling pump A, a check valve and a chimney;
the manual stop valve is arranged at the starting end of the pipeline, and a sampling filter box A, a sampling filter box B, a pressure gauge and a gas flowmeter are sequentially arranged behind the manual stop valve;
the radioactive gas enters the detection device through the manual stop valve;
a manual throttle valve A and a sampling pump A are sequentially connected to a pipeline behind the gas flowmeter;
the manual throttle valve A is used for adjusting the pressure and the gas flow of radioactive gas, and the sampling pump A is used for pumping the radioactive gas out;
the two branch pipes are connected with the check valve and the chimney in sequence after being converged, and the check valve is used for preventing radioactive gas from returning to a workshop through an original pipeline in the discharging process.
The sampling device is characterized by further comprising a branch pipe which is connected with the manual throttle valve A and the sampling pump A in parallel, the branch pipe is sequentially connected with the manual throttle valve B and the sampling pump B, and the branch pipe is used with the manual throttle valve A and the sampling pump A.
A radioactive airborne effluent concentration detection method based on the detection device comprises the following steps:
the method comprises the following steps: filling filter paper;
step two: starting the detection device;
step three: setting sampling parameters;
step four: and (4) processing the sample.
The method specifically comprises the following steps:
the method comprises the following steps: filling filter paper
Opening the box covers of the sampling filter box A and the sampling filter box B, respectively filling filter paper into the sampling filter box A and the sampling filter box B, closing the box covers of the sampling filter box A and the sampling filter box B, and locking;
step two: start detection device
Sequentially opening a manual throttle valve A, a manual stop valve and a sampling pump A, and introducing radioactive gas into a detection system;
the manual throttle valve B and the sampling pump B are in a standby state;
step three: setting sampling parameters
Setting the reading of a gas flowmeter to be 15-35L/min, sampling time to be 12-24h, and discharging the radioactive gas filtered by the sampling filter box A and the sampling filter box B in a high-altitude dilution mode through a chimney;
step four: sample processing
And respectively taking out the filter paper in the sampling filter box A and the sampling filter box B, putting the filter paper into a shielding container, naturally decaying for 4 days, and detecting the radioactivity of the filter paper by using a low-background aerosol measuring instrument.
The filter paper is WHATMAN type filter paper matched with the iCAM type aerosol continuous monitor.
Step three: the gas flow meter reading was set at 28L/min and the sampling time was 24 h.
In the fourth step, the low background aerosol measuring instrument conforms to GB11682-89 and FJ/T785-93 standards, the main high voltage and the conforming high voltage normal value are 750V/550V, and the positive and negative voltage does not exceed 2V.
And in the fourth step, carrying out sigma α and sigma β -gamma radioactivity detection on the filter paper by using a low-background aerosol measuring instrument.
The invention has the following remarkable effects:
(1) the invention has simple operation, can continuously and stably run for a long time, and completely avoids the problem that acid gas in process exhaust corrodes the probe of the monitor.
(2) The invention has accurate and reliable measured data.
Drawings
FIG. 1 is a schematic view of radioactive airborne effluent concentration detection.
In the figure: 1-a radioactive gas; 2-a manual stop valve; 3-sampling cartridge a; 4-sampling cartridge B; 5-a pressure gauge; 6-gas flow meter; 7-manual throttle valve A; 8-a sampling pump A; 9-manual throttle valve B; 10-sampling pump B; 11-a check valve; 12-chimney.
Detailed Description
The invention is described in further detail below with reference to the figures and the embodiments.
The radioactive gas-carried effluent concentration detection device shown in fig. 1 comprises a manual stop valve 2, a sampling filter box A3, a sampling filter box B4, a pressure gauge 5, a gas flowmeter 6, a manual throttle valve A7, a sampling pump A8, a manual throttle valve B9, a sampling pump B10, a check valve 11 and a chimney 12.
The manual stop valve 2 is arranged at the starting end of the pipeline, and a sampling filter box A3, a sampling filter box B4, a pressure gauge 5 and a gas flowmeter 6 are sequentially arranged behind the manual stop valve 2. The radioactive gas 1 enters the detection device through the manual stop valve 2.
And two branch pipes are connected in parallel on a pipeline behind the gas flowmeter 6, wherein one branch pipe is sequentially connected with a manual throttle valve A7 and a sampling pump A8, the other branch pipe is sequentially connected with a manual throttle valve B9 and a sampling pump B10, and the two branch pipes are used and prepared.
The manual throttle valve A7 and the manual throttle valve B9 are used for adjusting the pressure and the gas flow of the radioactive gas 1. The sampling pump A8 and the sampling pump B10 are used for pumping out the radioactive gas 1.
The two branch pipes are converged and then sequentially connected with a check valve 11 and a chimney 12. The check valve 11 is used for preventing the radioactive gas 1 from returning to the factory building through the original pipeline in the discharging process.
A radioactive airborne effluent concentration detection method is operated by adopting the detection device and comprises the following steps:
the method comprises the following steps: filling filter paper
Opening the box covers of the sampling filter box A3 and the sampling filter box B4, respectively filling WHATMAN type filter paper matched with the iCAM type aerosol continuous monitor into the sampling filter box A3 and the sampling filter box B4, closing the box covers of the sampling filter box A3 and the sampling filter box B4, and locking;
step two: start detection device
Sequentially opening a manual throttle valve A7 and a manual stop valve 2 on one branch pipe and a sampling pump A8 on the same branch pipe, and introducing the radioactive gas 1 into a detection system;
the manual throttle valve B9 and the sampling pump B10 on the other branch pipe are in a standby state;
step three: setting sampling parameters
The gas meter 6 is set to read 15-35L/min, typically 28L/min; the sampling time is 12-24h, usually 24 h;
the radioactive gas 1 filtered by the sampling filter box A3 and the sampling filter box B4 is discharged by high-altitude dilution through a chimney 12;
step four: sample processing
Respectively taking out the filter paper in the sampling filter box A3 and the sampling filter box B4, placing the filter paper in a shielding container, naturally decaying for 4 days, and carrying out sigma α and sigma β -gamma radioactivity detection on the filter paper by using a low-background aerosol measuring instrument;
the low-background aerosol measuring instrument conforms to GB11682-89 and FJ/T785-93 standards, the main high voltage and the conforming high voltage normal value are 750V/550V, and the positive and negative voltages do not exceed 2V.

Claims (8)

1. A radioactive airborne effluent concentration detection apparatus, characterized in that: the device comprises a manual stop valve (2), a sampling filter box A (3), a sampling filter box B (4), a pressure gauge (5), a gas flowmeter (6), a manual throttle valve A (7), a sampling pump A (8), a check valve (11) and a chimney (12);
the manual stop valve (2) is arranged at the starting end of the pipeline, and a sampling filter box A (3), a sampling filter box B (4), a pressure gauge (5) and a gas flowmeter (6) are sequentially arranged behind the manual stop valve (2);
the radioactive gas (1) enters the detection device through the manual stop valve (2);
a manual throttle valve A (7) and a sampling pump A (8) are sequentially connected to a pipeline behind the gas flowmeter (6);
the manual throttle valve A (7) is used for adjusting the pressure and the gas flow of the radioactive gas (1), and the sampling pump A (8) is used for pumping out the radioactive gas (1);
the two branch pipes are connected with the check valve (11) and the chimney (12) in sequence after being converged, and the check valve (11) is used for preventing the radioactive gas (1) from returning to a workshop through an original pipeline in the discharge process.
2. A radioactive airborne effluent concentration detection apparatus as claimed in claim 1, wherein: the automatic sampling device is characterized by further comprising a branch pipe which is connected with the manual throttle valve A (7) and the sampling pump A (8) in parallel and is provided with a branch pipe, the branch pipe is sequentially connected with the manual throttle valve B (9) and the sampling pump B (10), and the branch pipe is used with the manual throttle valve A (7) and the sampling pump A (8) in a standby mode.
3. A method for detecting a concentration of radioactive airborne effluents based on the detection device of claim 2, wherein: the method comprises the following steps:
the method comprises the following steps: filling filter paper;
step two: starting the detection device;
step three: setting sampling parameters;
step four: and (4) processing the sample.
4. A radioactive airborne effluent concentration detection method as claimed in claim 3, wherein: the method specifically comprises the following steps:
the method comprises the following steps: filling filter paper
Opening the box covers of the sampling filter box A (3) and the sampling filter box B (4), respectively filling filter paper into the sampling filter box A (3) and the sampling filter box B (4), closing the box covers of the sampling filter box A (3) and the sampling filter box B (4) and locking;
step two: start detection device
Opening a manual throttle valve A (7), a manual stop valve (2) and a sampling pump A (8) in sequence, and introducing the radioactive gas (1) into a detection system;
the manual throttle valve B (9) and the sampling pump B (10) are in a standby state;
step three: setting sampling parameters
Setting the reading of the gas flowmeter (6) to be 15-35L/min, the sampling time to be 12-24h, and diluting and discharging the radioactive gas (1) filtered by the sampling filter box A (3) and the sampling filter box B (4) in high altitude through a chimney (12);
step four: sample processing
And respectively taking out the filter paper in the sampling filter box A (3) and the sampling filter box B (4), putting the filter paper into a shielding container, naturally decaying for 4 days, and detecting the radioactivity of the filter paper by using a low-background aerosol measuring instrument.
5. A radioactive airborne effluent concentration detection method as claimed in claim 4, wherein: the filter paper is WHATMAN type filter paper matched with the iCAM type aerosol continuous monitor.
6. A radioactive airborne effluent concentration detection method as claimed in claim 5, wherein: step three: the reading of the gas flowmeter (6) is set to be 28L/min, and the sampling time is 24 h.
7. A radioactive airborne effluent concentration detection method as claimed in claim 6, wherein: in the fourth step, the low background aerosol measuring instrument conforms to GB11682-89 and FJ/T785-93 standards, the main high voltage and the conforming high voltage normal value are 750V/550V, and the positive and negative voltage does not exceed 2V.
8. The method for detecting the concentration of radioactive airborne effluents according to claim 7, wherein in step four, sigma α and sigma β -gamma radioactivity is detected on the filter paper by using a low background aerosol measuring instrument.
CN201811494376.7A 2018-12-07 2018-12-07 Device and method for detecting concentration of radioactive airborne effluents Pending CN111290010A (en)

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CN111290010A true CN111290010A (en) 2020-06-16

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Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2013134204A (en) * 2011-12-27 2013-07-08 Mitsubishi Electric Corp Condenser exhaust gas monitor
CN104360371A (en) * 2014-11-12 2015-02-18 中国人民解放军63653部队 High-sensitivity radioactive aerosol continuous monitor
CN104570040A (en) * 2015-01-21 2015-04-29 中国科学院上海应用物理研究所 On-line monitoring system and method for radioactive gas and radioactive aerosol
CN105301624A (en) * 2015-11-25 2016-02-03 深圳中广核工程设计有限公司 Nuclear power plant radioactive exudation monitoring system
CN205384375U (en) * 2015-12-14 2016-07-13 中国船舶重工集团公司第七一九研究所 Online real -time outdoor aerosol monitoring devices
CN106093313A (en) * 2016-08-10 2016-11-09 河南核净洁净技术有限公司 The silicon dioxide of nuclear power station water filter filter element separates out detection method and the dedicated test system thereof of performance
CN106816197A (en) * 2015-11-30 2017-06-09 江苏核电有限公司 One kind is used for nuclear power plant's Spent Radioactive gas processing system dehumidifying cooling device
CN107402170A (en) * 2016-05-19 2017-11-28 中国辐射防护研究院 A kind of the radioaerosol continuous monitoring device and method of the corrosion of acid-resistance material

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2013134204A (en) * 2011-12-27 2013-07-08 Mitsubishi Electric Corp Condenser exhaust gas monitor
CN104360371A (en) * 2014-11-12 2015-02-18 中国人民解放军63653部队 High-sensitivity radioactive aerosol continuous monitor
CN104570040A (en) * 2015-01-21 2015-04-29 中国科学院上海应用物理研究所 On-line monitoring system and method for radioactive gas and radioactive aerosol
CN105301624A (en) * 2015-11-25 2016-02-03 深圳中广核工程设计有限公司 Nuclear power plant radioactive exudation monitoring system
CN106816197A (en) * 2015-11-30 2017-06-09 江苏核电有限公司 One kind is used for nuclear power plant's Spent Radioactive gas processing system dehumidifying cooling device
CN205384375U (en) * 2015-12-14 2016-07-13 中国船舶重工集团公司第七一九研究所 Online real -time outdoor aerosol monitoring devices
CN107402170A (en) * 2016-05-19 2017-11-28 中国辐射防护研究院 A kind of the radioaerosol continuous monitoring device and method of the corrosion of acid-resistance material
CN106093313A (en) * 2016-08-10 2016-11-09 河南核净洁净技术有限公司 The silicon dioxide of nuclear power station water filter filter element separates out detection method and the dedicated test system thereof of performance

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
牟长丽;黄子瀚;徐宏坤;边江;殷荫;王戈;: "新型放射性气溶胶连续监测仪的研制" *

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Application publication date: 20200616