CN108572386B - 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
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- CN108572386B CN108572386B CN201710131000.9A CN201710131000A CN108572386B CN 108572386 B CN108572386 B CN 108572386B CN 201710131000 A CN201710131000 A CN 201710131000A CN 108572386 B CN108572386 B CN 108572386B
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- 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 circulating tank, a shielding layer, a circulating system and a gamma monitor calibration cup, wherein the circulating system comprises a circulating pipeline and a circulating pump connected to the circulating pipeline; the radionuclide standard solution with known activity and concentration flows in the circulating pipeline through the power applied by the circulating pump, so that the circulation in the circulating tank and the gamma monitor calibration cup connected with the circulating pipeline is realized; the shielding layer covers the periphery of the outer wall of the gamma monitor calibration cup and is used for shielding background radiation of the surrounding environment; the gamma monitor calibration cup is used for placing a probe of the gamma monitor in a circulating radionuclide standard solution with known activity concentration 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 liquid effluent gamma monitor has been a difficult problem due to the complex structure 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 calibration of a 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 calibration of a gamma monitor for liquid effluent from a nuclear plant, the apparatus comprising a recycle tank, a shield, a recycle system, a gamma monitor calibration cup,
the circulating system comprises a circulating pipeline and a circulating pump connected to the circulating pipeline;
the radionuclide standard solution with known activity concentration flows in the circulating pipeline by the power applied by a circulating pump, so that the circulation in the circulating tank and the gamma monitor calibration cup connected with the circulating pipeline is realized;
the shielding layer covers the periphery of the outer wall of the gamma monitor calibration cup and is used for shielding background radiation of the surrounding environment;
the gamma monitor calibration cup is used for placing a probe of the gamma monitor in a circulating radionuclide standard solution with known activity concentration 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 waste liquid storage tank for storing waste liquid discharged from the recycle tank and a connecting pipe for connecting the waste liquid storage tank and the recycle tank.
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 waste liquid discharge valve and a waste liquid discharge pump which are arranged on the connecting pipeline connecting the waste liquid storage tank and the circulating tank.
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 waste liquid storage tank emptying pipeline and a waste liquid storage tank emptying valve, and the bottom of the waste liquid storage tank is connected with the waste liquid storage tank emptying pipeline and the waste liquid storage tank emptying valve and is used for emptying waste liquid stored in the waste liquid storage tank under the condition that the waste liquid storage tank emptying valve is opened.
In a preferred embodiment, the invention provides a device for calibrating a liquid effluent gamma monitor of a nuclear facility, wherein the shielding layer is a lead shielding layer and has a thickness of 5-15 cm.
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 circulating system further comprises a circulating valve arranged on the circulating pipeline.
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 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 the standard solution of the radionuclide with the known activity concentration into the circulating tank;
2) starting the circulating pump to circulate the radionuclide standard solution with known activity and concentration among the circulating tank, the circulating system and the gamma monitor calibration cup;
3) and placing the probe of the gamma monitor in a circulating radionuclide standard solution with known activity and concentration in the gamma monitor calibration cup 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 waste liquid storage tank 1, a waste liquid storage tank emptying pipeline 2, a waste liquid storage tank emptying valve 3, a connecting pipeline 4, a circulating tank 5, a circulating pump 6, a circulating valve 7, a lead shielding layer 8, a circulating system 9, a gamma monitor calibration cup 10, a waste liquid discharge valve 11, a waste liquid discharge pump 12, a flowmeter 13, a shielding cover 14 and a circulating pipeline 15.
The gamma monitor calibration cup 10 (for the marlin cup) adopts stainless steel material, and the NaI probe 16 that the biggest size is 3 "can be laid to its concave surface, also can be through changing different shielding component in order to install the NaI probe 16 that the volume is different. The gamma monitor calibration cup 10 is used to calibrate the gamma monitor by placing the probe 16 of the gamma monitor in a standard solution of radionuclide circulating therein at a known activity concentration. The lead shielding layer 8 with the thickness of 10cm covers the periphery of the outer wall of the gamma monitor calibration cup 10 and is used for shielding background radiation of the surrounding environment, so that a low-background measurement environment is formed in the gamma monitor calibration cup 10. A shielding cover 14 is arranged on the upper side of the lead shielding layer 8 and outside a probe 16 of the gamma monitor.
The circulating system 9 comprises a circulating pipeline 15, a circulating pump 6 (formed by refitting a medical pump) connected to the circulating pipeline, a circulating valve 7 and a flowmeter 13 (a turbine flowmeter). The radionuclide standard solution with known activity and concentration flows in the circulating pipeline 15 by the power applied by the circulating pump 6, and the circulation in the circulating tank 5 and the gamma monitor calibration cup 10 connected with the circulating pipeline 15 is realized. The flow of the radionuclide standard solution with known activity concentration circulating in the circulating pipeline 15 is 10-80L/min by controlling the circulating pump 6 and the circulating valve 7 and displaying the flow through the flowmeter 13.
Waste liquid holding vessel 1 is stainless steel material, and the jar is dark 400mm, and the internal diameter is 308 mm. The waste liquid storage tank 1 is connected to the circulation tank 5 through a connection pipe 4, and a waste liquid discharge valve 11 and a waste liquid discharge pump 12 are provided on the connection pipe 4. The waste liquid storage tank 1 is used for storing the waste liquid discharged from the circulation tank 5. Waste liquid holding vessel evacuation pipeline 2 and waste liquid holding vessel evacuation valve 3 are connected to 1 bottom in waste liquid holding vessel for the waste liquid of storage in the waste liquid holding vessel 1 is evacuated under the condition of opening waste liquid holding vessel evacuation valve 2.
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) testing of sealing of a circulation system
The tightness of the circulation system 9 must first be tested. The volume of the circulating system 9 is 80L, tap water is filled under the condition that all circulating system valves are in an open state, the power supply of the circulating pump 6 is connected, the operation is maintained for a week, and if no water leakage phenomenon exists, the sealing performance of the circulating system 9 in the operating state is good. And (3) turning off the power supply of the circulating pump 6, keeping the whole device in a water state for three months, and if the water leakage phenomenon does not exist, proving that the circulating system 9 is well sealed in a static state.
(2) Gamma monitor calibration
Radioactive solution with known activity and concentration is added into the circulating tank 5, the circulating valve 7 is opened, the waste liquid discharge valve 11 is closed, and the power supply of the circulating pump 6 is switched on. At this point, the radioactive solution flows through the circulation line 15 and flows through the gamma monitor calibration cup 10. The placement of the probe 16 in the gamma monitor calibration cup 10 can be used for sampling for gamma monitor calibration experiments. At the moment, the flow of the solution in the whole device can be obtained by observing the readings of the flowmeter 13, and the flow is adjusted by adjusting the opening of the circulating valve 7, so that the flow required by the actual operation of the gamma monitor is achieved.
(3) 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 time, the circulation valve 7 is closed, the waste liquid discharge valve 11 is opened, the waste liquid discharge pump 12 is turned on, and the radioactive solution is discharged to the waste liquid storage tank 1 through the waste liquid discharge pump 12. The inside of the circulation device is cleaned in a soaking manner by using tap water, and then the waste water is discharged to the waste liquid storage tank 1. After the waste liquid storage tank 1 is full of waste liquid, the waste liquid treatment is carried out in a centralized manner (the waste liquid storage tank emptying valve 3 is opened for discharging).
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 circulating tank, a shielding layer, a circulating system and a gamma monitor calibrating cup,
the circulating system comprises a circulating pipeline and a circulating pump connected to the circulating pipeline;
the radionuclide standard solution with known activity concentration flows in the circulating pipeline by the power applied by a circulating pump, so that the circulation in the circulating tank and the gamma monitor calibration cup connected with the circulating pipeline is realized;
the shielding layer covers the periphery of the outer wall of the gamma monitor calibration cup and is used for shielding background radiation of the surrounding environment;
the gamma monitor calibration cup is used for placing a probe of the gamma monitor in a circulating radionuclide standard solution with known activity concentration to calibrate the gamma monitor.
2. The apparatus of claim 1, wherein: the device still include waste liquid holding vessel and be used for connecting the connecting tube of waste liquid holding vessel and circulating tank, the waste liquid holding vessel be used for storing circulating tank exhaust waste liquid.
3. The apparatus of claim 2, wherein: the device also comprises a waste liquid discharge valve and a waste liquid discharge pump which are arranged on the connecting pipeline connecting the waste liquid storage tank and the circulating tank.
4. The apparatus of claim 3, wherein: the device still include waste liquid holding vessel evacuation pipeline and waste liquid holding vessel evacuation valve, waste liquid holding vessel bottom connect waste liquid holding vessel evacuation pipeline and waste liquid holding vessel evacuation valve for the evacuation under the condition of opening waste liquid holding vessel evacuation valve the waste liquid holding vessel in the waste liquid of storage.
5. The apparatus of claim 1, wherein: the shielding layer is a lead shielding layer, and the thickness of the shielding layer is 5-15 cm.
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 circulating system also comprises a circulating valve which is arranged on the circulating pipeline.
9. The apparatus of claim 1, wherein: the flow rate of the radionuclide standard solution with known activity concentration circulating in the circulating pipeline is 10-80L/min.
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 the standard solution of the radionuclide with the known activity concentration into the circulating tank;
2) starting the circulating pump to circulate the radionuclide standard solution with known activity and concentration among the circulating tank, the circulating system and the gamma monitor calibration cup;
3) and placing the probe of the gamma monitor in a circulating radionuclide standard solution with known activity and concentration in the gamma monitor calibration cup to calibrate the gamma monitor.
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| CN201710131000.9A CN108572386B (en) | 2017-03-07 | 2017-03-07 | Device and method for calibrating nuclear facility liquid effluent gamma monitor |
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| CN201710131000.9A CN108572386B (en) | 2017-03-07 | 2017-03-07 | Device and method for calibrating nuclear facility liquid effluent gamma monitor |
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| CN108572386B true CN108572386B (en) | 2022-04-19 |
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| WO2016176655A2 (en) * | 2015-04-30 | 2016-11-03 | Vpi Engineering, Inc. | Method and system for calibrating gamma radiation flux levels in a solid state gamma radiation detection system |
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