CN108572388B - Device and method for calibrating nuclear facility liquid effluent gamma monitor - Google Patents
Device and method for calibrating nuclear facility liquid effluent gamma monitor Download PDFInfo
- Publication number
- CN108572388B CN108572388B CN201710131253.6A CN201710131253A CN108572388B CN 108572388 B CN108572388 B CN 108572388B CN 201710131253 A CN201710131253 A CN 201710131253A CN 108572388 B CN108572388 B CN 108572388B
- Authority
- CN
- China
- Prior art keywords
- pipeline
- calibration
- circulating
- monitor
- gamma
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Images
Classifications
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T7/00—Details of radiation-measuring instruments
- G01T7/005—Details of radiation-measuring instruments calibration techniques
Abstract
The invention belongs to the technical field of radiation monitoring, and relates to a device and a method for calibrating a liquid effluent gamma monitor of nuclear facilities. The device comprises a calibration pipeline and a circulating system, wherein the circulating system comprises a circulating pipeline and a circulating pump connected to the circulating pipeline, and two ends of the circulating pipeline are respectively connected with the calibration pipeline; the radionuclide standard solution with known activity concentration flows in the circulating pipeline and the calibration pipeline by the power applied by the circulating pump, so as to realize circulation between the circulating pipeline and the calibration pipeline; the side wall of the calibration pipeline is provided with an opening for connecting a probe of the gamma monitor to calibrate the gamma monitor. The device and the method can conveniently and accurately calibrate the gamma monitor for the liquid effluent of the nuclear facility.
Description
Technical Field
The invention belongs to the technical field of radiation monitoring, and relates to a device and a method for calibrating a liquid effluent gamma monitor of nuclear facilities.
Background
The calibration of the gamma monitor for liquid effluents has been a difficult problem due to the complex structure, the heavy and difficult disassembly of the lead shielding layer and the irregular shape of the solution to be monitored. The calibration of the instrument is basically in a preliminary exploration stage at home and abroad, a method for checking the calibration by using a check source is mainly adopted, but the convenience and the accuracy of the calibration are not satisfactory at present.
Disclosure of Invention
The primary object of the present invention is to provide a device for calibrating a gamma monitor for nuclear plant liquid effluent, with which the calibration of the gamma monitor for nuclear plant liquid effluent can be conveniently and accurately performed.
To achieve this object, in a basic embodiment, the present invention provides an apparatus for calibrating a liquid effluent gamma monitor of a nuclear plant, the apparatus comprising a calibration pipe, a circulation system,
the circulating system comprises a circulating pipeline and a circulating pump connected to the circulating pipeline, and two ends of the circulating pipeline are respectively connected with the calibration pipeline;
the radionuclide standard solution with known activity concentration flows in the circulating pipeline and the calibration pipeline by the power applied by the circulating pump, so as to realize circulation between the circulating pipeline and the calibration pipeline;
the side wall of the calibration pipeline is provided with an opening for connecting a probe of the gamma monitor to calibrate the gamma monitor.
In a preferred embodiment, the invention provides an apparatus for calibrating a liquid effluent gamma monitor of a nuclear plant, wherein the apparatus further comprises a sealing member and an evacuation conduit,
one end of the calibration pipe is sealed by the sealing component;
the other end opening of the calibration pipeline is connected with the emptying pipeline and used for discharging liquid in the calibration pipeline.
In a preferred embodiment, the invention provides a device for calibrating a liquid effluent gamma monitor of a nuclear facility, wherein the sealing component is a sealing cover with a sealing ring.
In a preferred embodiment, the invention provides a device for calibrating a liquid effluent gamma monitor of a nuclear facility, wherein the sealing cover is fixed with one end of the calibration pipeline by a bolt.
In a preferred embodiment, the invention provides a device for calibrating a liquid effluent gamma monitor of a nuclear facility, wherein one end of the calibration pipeline, which is connected with the emptying pipeline, is provided with an arc-shaped bottom.
In a preferred embodiment, the invention provides a device for calibrating a liquid effluent gamma monitor of a nuclear facility, wherein the circulating system further comprises a flow meter arranged on the circulating pipeline.
In a preferred embodiment, the present invention provides an apparatus for calibrating a liquid effluent gamma monitor for a nuclear plant, wherein the flow meter is a turbine flow meter.
In a preferred embodiment, the invention provides a device for calibrating a liquid effluent gamma monitor of a nuclear facility, wherein the device further comprises a liquid level meter arranged on the calibration pipeline and used for measuring the liquid level in the calibration pipeline.
In a preferred embodiment, the invention provides a device for calibrating a liquid effluent gamma monitor of a nuclear facility, wherein the calibration pipeline is vertically arranged, and the bottom of the calibration pipeline is supported by a support frame.
In a preferred embodiment, the invention provides a device for calibrating a liquid effluent gamma monitor of a nuclear facility, wherein the flow rate of the radionuclide standard solution with the known activity concentration circulating in the circulating pipeline is 10-80L/min.
A second object of the present invention is to provide a method for calibrating a gamma monitor using the above apparatus, so that the calibration of a gamma monitor for liquid effluents of nuclear facilities can be conveniently and accurately performed using the method.
To achieve this object, in a basic embodiment, the present invention provides a method for calibrating a gamma monitor using the apparatus as above, comprising the steps of:
1) adding said standard solution of radionuclide at a known activity concentration to said calibration line;
2) starting the circulating pump to circulate the radionuclide standard solution with known activity concentration between the calibration pipeline and the circulating system;
3) and placing a probe of the gamma monitor in the opening of the side wall of the calibration pipeline to calibrate the gamma monitor.
The device and the method have the advantages that the gamma monitor for the liquid effluent of the nuclear facility can be conveniently and accurately calibrated.
Drawings
FIG. 1 is a block diagram of an exemplary apparatus of the present invention for calibrating a nuclear facility liquid effluent gamma monitor.
Detailed Description
The following further describes embodiments of the present invention with reference to the accompanying drawings.
An exemplary device for calibrating a gamma monitor for liquid effluent of a nuclear facility, disclosed by the invention, is shown in fig. 1 and comprises a calibration pipeline 1, a sealing cover 2, a liquid level meter 3, a gamma monitor probe inlet 4, a supporting frame 5, an emptying pipeline 6, an emptying valve 7, a circulating system 8, a circulating pipeline 9, a circulating pump 10 and a turbine flowmeter 11.
The calibration pipeline 1 is made of stainless steel and is vertically placed, the inner diameter of the pipeline is 21.26cm, and the outer diameter of the pipeline is 21.92 cm. The bottom of the calibration pipeline 1 is supported by a support frame 5 (a triangular support is adopted, the support legs are fixed on the lower half part of the calibration pipeline 1 through fastening rings, the support frame 5 is used for keeping the calibration pipeline vertical), the top of the calibration pipeline is sealed by a sealing cover 2 with a sealing ring, and the sealing cover 2 and the calibration pipeline 1 are fixed through bolts. A level gauge 3 using the principle of a communicating vessel is arranged on the side wall of the calibration pipe 1 for measuring the liquid level in the calibration pipe 1. And a gamma monitor probe access port 4 is formed in the side wall of the calibration pipeline and is used for accessing the probe of the gamma monitor to calibrate the gamma monitor. The circular arc-shaped bottom of the calibration pipeline 1 is connected with a tee joint through a pipeline, one side of the tee joint is connected with a circulating pipeline 9, and the other side of the tee joint is connected with an exhaust pipeline 6. The emptying pipe 6 is provided with an emptying valve 7 for controlling the opening and closing of the liquid in the calibration pipe 1.
The circulation system 8 includes a circulation pipe 9, a circulation pump 10 connected to the circulation pipe 9, and a turbine flowmeter 11 connected to the circulation pipe 9. One end of the circulating pipeline 9 is connected with the side wall of the calibration pipeline 1 (the connection point is located at the position 20cm away from the top of the side wall of the calibration pipeline 1 and is connected in a welding mode), and the other end of the circulating pipeline is connected with the tee joint connected with the arc-shaped bottom of the calibration pipeline 1.
The radionuclide standard solution with known activity concentration flows in the circulating pipeline 9 and the calibration pipeline 1 by the power applied by the circulating pump 10, so as to realize circulation between the circulating pipeline 9 and the calibration pipeline 1, and the circulating flow is 10-80L/min.
The method for calibrating the gamma monitor by using the device for calibrating the nuclear facility liquid effluent gamma monitor of the invention comprises the following steps:
(1) experiment for calibrating pipeline tightness
After the whole set of device is built, a pipeline tightness calibration experiment is required to be carried out. The emptying valve 7 is closed, the sealing cover 2 is opened, and the power supply of the circulating pump 10 is communicated, so that the circulating pump operates under lower power. And (3) injecting clean water into the calibration pipeline 1 from the top of the calibration pipeline 1 to the water surface to submerge the probe access port 4 of the gamma monitor of the calibration pipeline 1. The power supply of the circulation pump 10 is turned off and the sealing cover 2 is sealed. At this time, the liquid in the calibration pipe 1 is in a full state, and the state is kept for 15 days, if no water leakage phenomenon exists, the sealing performance of the calibration pipe in a static state is good. And a power supply of the circulating pump 10 is communicated, so that the circulating pump operates under normal working power and keeps operating for one day, and if no water leakage phenomenon exists, the sealing performance of the calibration pipeline is good in an operating state.
(2) Experiment of sealing performance of circulating system
The volume of the circulating system 8 is 80L, under the condition that all valves of the circulating system are in an open state, clear water is filled, the power supply of the circulating pump 10 is connected, the circulating pump is kept running for a week, and if no water leakage phenomenon exists, the sealing performance of the circulating system in the running state is good. And (3) turning off the power supply of the circulating pump 10, keeping the circulating system in a water state for three months, and if the water leakage phenomenon does not exist, proving that the circulating system is well sealed in a static state.
(3) Gamma monitor calibration
After the calibration purpose is determined, the calibration work of the gamma monitor can be carried out. The power supply of the circulating pump 10 is switched on, and the power of the circulating pump is adjusted to enable the flow rate to be a small (20-30L/min) level. The sealing cap 2 is opened and the radioactive solution of known activity concentration is added to the calibration pipe 1. The liquid level was observed and the addition of solution was stopped when the liquid level exceeded the height of the gamma monitor probe access port 4. The circulation pump 10 was kept running for 3min, at which point the radioactive solution was considered to have been evenly distributed throughout the entire set of equipment.
When the calibration work is carried out, the probe of the calibrated gamma monitor is inserted from the probe access port 4 of the gamma monitor to align to the center of the calibration pipeline 1, and the front surface of the probe is 3mm away from the outer wall of the calibration pipeline 1. The flow rate of the liquid in the whole device is measured by the turbine flowmeter 11, and the power of the circulating pump 10 is adjusted to make the flow rate consistent with the required flow rate. And (3) observing the reading number or the full-energy peak counting number of the gamma monitor in real time, recording data when the reading number of the gamma monitor is stable or the full-energy peak counting number meets the requirement, and carrying out the next experiment. The various coefficients of the monitor can be calibrated at different flow rates and with different radionuclide solutions.
(4) Radioactive solution evacuation and device cleaning
After the calibration experiment is completed, the radioactive solution in the whole set of apparatus needs to be discharged if other similar experiments do not need to be performed. At this point, the drain valve 7 should be opened to drain the radioactive solution through the drain line 6 into the waste disposal system. After the inside of the whole device is cleaned in a soaking mode by adopting clean water, the cleaned wastewater is also discharged to a waste liquid disposal system.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is intended to include such modifications and variations. The foregoing examples or embodiments are merely illustrative of the present invention, which may be embodied in other specific forms or in other specific forms without departing from the spirit or essential characteristics thereof. The described embodiments are, therefore, to be considered in all respects as illustrative and not restrictive. The scope of the invention should be indicated by the appended claims, and any changes that are equivalent to the intent and scope of the claims should be construed to be included therein.
Claims (10)
1. The device for calibrating the gamma monitor for the liquid effluent of the nuclear facility is characterized by comprising a calibration pipeline and a circulating system,
the circulating system comprises a circulating pipeline and a circulating pump connected to the circulating pipeline, and two ends of the circulating pipeline are respectively connected with the calibration pipeline;
the radionuclide standard solution with known activity concentration flows in the circulating pipeline and the calibration pipeline by the power applied by the circulating pump, so as to realize circulation between the circulating pipeline and the calibration pipeline;
the side wall of the calibration pipeline is provided with an opening for connecting a probe of the gamma monitor to calibrate the gamma monitor.
2. The apparatus of claim 1, wherein: the device also comprises a sealing component and an emptying pipeline,
one end of the calibration pipe is sealed by the sealing component;
the other end opening of the calibration pipeline is connected with the emptying pipeline and used for discharging liquid in the calibration pipeline.
3. The apparatus of claim 2, wherein: the sealing component is a sealing cover with a sealing ring.
4. The apparatus of claim 3, wherein: the sealing cover is fixed with one end of the calibration pipeline through a bolt.
5. The apparatus of claim 2, wherein: the calibration pipeline and the end connected with the emptying pipeline are arc-shaped bottoms.
6. The apparatus of claim 1, wherein: the circulating system also comprises a flowmeter which is arranged on the circulating pipeline.
7. The apparatus of claim 6, wherein: the flowmeter is a turbine flowmeter.
8. The apparatus of claim 1, wherein: the device also comprises a liquid level meter which is arranged on the calibration pipeline and is used for measuring the liquid level in the calibration pipeline.
9. The apparatus of claim 1, wherein: the calibration pipeline is vertically arranged, and the bottom of the calibration pipeline is supported by a support frame.
10. A method of calibrating a gamma monitor using the apparatus of any one of claims 1 to 9, comprising the steps of:
1) adding said standard solution of radionuclide at a known activity concentration to said calibration line;
2) starting the circulating pump to circulate the radionuclide standard solution with known activity concentration between the calibration pipeline and the circulating system;
3) and placing a probe of the gamma monitor in the opening of the side wall of the calibration pipeline to calibrate the gamma monitor.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710131253.6A CN108572388B (en) | 2017-03-07 | 2017-03-07 | Device and method for calibrating nuclear facility liquid effluent gamma monitor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710131253.6A CN108572388B (en) | 2017-03-07 | 2017-03-07 | Device and method for calibrating nuclear facility liquid effluent gamma monitor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN108572388A CN108572388A (en) | 2018-09-25 |
| CN108572388B true CN108572388B (en) | 2022-04-19 |
Family
ID=63577406
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201710131253.6A Active CN108572388B (en) | 2017-03-07 | 2017-03-07 | Device and method for calibrating nuclear facility liquid effluent gamma monitor |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN108572388B (en) |
Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101535835A (en) * | 2006-08-28 | 2009-09-16 | 热费希尔科学公司 | Methods and apparatus for performance verification and stabilization of radiation detection devices |
| CN103267974A (en) * | 2013-04-24 | 2013-08-28 | 清华大学 | Improved Marin cup type automatic monitoring device for water body radionuclide gamma radiation |
| CN203773060U (en) * | 2013-12-30 | 2014-08-13 | 中国辐射防护研究院 | Tool used for calibration of surface pollution monitor |
| CN104637564A (en) * | 2013-11-11 | 2015-05-20 | 中国辐射防护研究院 | Attenuation type automatic multi-range gamma irradiation device |
| CN105203717A (en) * | 2015-10-22 | 2015-12-30 | 中国核动力研究设计院 | Inert gas monitor field calibration device and application method thereof |
| 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 |
| CN106054237A (en) * | 2016-07-28 | 2016-10-26 | 中国船舶重工集团公司第七〇九研究所 | System platform for calibrating radioactive aerosol monitoring equipment and working method thereof |
| CN106443759A (en) * | 2016-08-26 | 2017-02-22 | 中国原子能科学研究院 | Gamma ray irradiation device used for thermoluminescence personal dosimeter calibration |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2014064295A1 (en) * | 2012-10-26 | 2014-05-01 | Universiteit Gent | Calibration of monolithic crystal-based detectors |
| EP3289387A4 (en) * | 2015-04-30 | 2018-12-26 | VPI Engineering, Inc. | Method and system for calibrating gamma radiation flux levels in a solid state gamma radiation detection system |
-
2017
- 2017-03-07 CN CN201710131253.6A patent/CN108572388B/en active Active
Patent Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101535835A (en) * | 2006-08-28 | 2009-09-16 | 热费希尔科学公司 | Methods and apparatus for performance verification and stabilization of radiation detection devices |
| CN103267974A (en) * | 2013-04-24 | 2013-08-28 | 清华大学 | Improved Marin cup type automatic monitoring device for water body radionuclide gamma radiation |
| CN104637564A (en) * | 2013-11-11 | 2015-05-20 | 中国辐射防护研究院 | Attenuation type automatic multi-range gamma irradiation device |
| CN203773060U (en) * | 2013-12-30 | 2014-08-13 | 中国辐射防护研究院 | Tool used for calibration of surface pollution monitor |
| CN105203717A (en) * | 2015-10-22 | 2015-12-30 | 中国核动力研究设计院 | Inert gas monitor field calibration device and application method thereof |
| 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 |
| CN106054237A (en) * | 2016-07-28 | 2016-10-26 | 中国船舶重工集团公司第七〇九研究所 | System platform for calibrating radioactive aerosol monitoring equipment and working method thereof |
| CN106443759A (en) * | 2016-08-26 | 2017-02-22 | 中国原子能科学研究院 | Gamma ray irradiation device used for thermoluminescence personal dosimeter calibration |
Non-Patent Citations (2)
| Title |
|---|
| 核电站流出物监测仪的校准;黄鸿，章文华;《原子能科学技术》;19940531;第28卷(第3期);第277-279页 * |
| 核设施液态流出物非介入式连续监测仪校准技术研究;谢文明，唐智辉 等;《原子能科学技术》;20161130;第50卷(第11期);第2060-2066页 * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN108572388A (en) | 2018-09-25 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN102252720B (en) | Mass flow meter based on weighing method | |
| CN102004142A (en) | Water quality parameter measuring instrument arranged in super buoy and water quality parameter measuring method | |
| CN109212580B (en) | Method for measuring radium concentration in water by open-loop type electrostatic collection two-stage method | |
| CN109655863B (en) | Method for measuring radium concentration in water in two cycles of closed-loop electrostatic collection | |
| CN105203717B (en) | Inert gas monitor field calibration device and its application process | |
| CN109655868B (en) | Method for rapidly measuring radium concentration in water by closed-loop electrostatic collection method | |
| US11371873B2 (en) | Vehicle based fluid meter tester | |
| CN101923042A (en) | Test method for simulating couple corrosion in seawater scouring environment | |
| CN108572388B (en) | Device and method for calibrating nuclear facility liquid effluent gamma monitor | |
| JP2020501106A (en) | Monitoring system for liquid leaks from spent fuel pools | |
| TW416003B (en) | Method and device for void fraction measurement and adverse output signal mitigation on pressure-base instruments | |
| RU91779U1 (en) | GAS GAS MEDIA DETECTION DETECTION DEVICE AND SPECTOMETRIC GAS GAMMA RADIATION MONITOR | |
| CN108572386B (en) | Device and method for calibrating nuclear facility liquid effluent gamma monitor | |
| CN107422360A (en) | Online fluid radiation monitor for nuclear power station | |
| CN106338357A (en) | Inverted-U-shaped-tube differential pressure gauge | |
| KR101710517B1 (en) | Water meter box for preventing vain metering | |
| CN205749519U (en) | A kind of test(ing) medium catching device | |
| CN209927244U (en) | Quick calibration equipment of flowmeter | |
| CN210376043U (en) | Testing device for measuring dissolution rate of salt rock | |
| CN109655869B (en) | Method for rapidly measuring radium concentration in water in closed-loop two-period mode | |
| Band et al. | The Daya Bay antineutrino detector filling system and liquid mass measurement | |
| CN206258168U (en) | A kind of simulation test device of portable liquid level monitoring device and flow switch | |
| CN205982226U (en) | Ph meter measuring device | |
| CN219456527U (en) | Gaseous iodine-129 continuous monitoring device | |
| CN211926972U (en) | Metal tube float flowmeter |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |