CN112857696A - Leakage detection device and detection method for radioactive gas sealed container - Google Patents
Leakage detection device and detection method for radioactive gas sealed container Download PDFInfo
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- CN112857696A CN112857696A CN202110145566.3A CN202110145566A CN112857696A CN 112857696 A CN112857696 A CN 112857696A CN 202110145566 A CN202110145566 A CN 202110145566A CN 112857696 A CN112857696 A CN 112857696A
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01M—TESTING STATIC OR DYNAMIC BALANCE OF MACHINES OR STRUCTURES; TESTING OF STRUCTURES OR APPARATUS, NOT OTHERWISE PROVIDED FOR
- G01M3/00—Investigating fluid-tightness of structures
- G01M3/02—Investigating fluid-tightness of structures by using fluid or vacuum
- G01M3/04—Investigating fluid-tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point
- G01M3/20—Investigating fluid-tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using special tracer materials, e.g. dye, fluorescent material, radioactive material
- G01M3/22—Investigating fluid-tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using special tracer materials, e.g. dye, fluorescent material, radioactive material for pipes, cables or tubes; for pipe joints or seals; for valves; for welds; for containers, e.g. radiators
- G01M3/226—Investigating fluid-tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using special tracer materials, e.g. dye, fluorescent material, radioactive material for pipes, cables or tubes; for pipe joints or seals; for valves; for welds; for containers, e.g. radiators for containers, e.g. radiators
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01M—TESTING STATIC OR DYNAMIC BALANCE OF MACHINES OR STRUCTURES; TESTING OF STRUCTURES OR APPARATUS, NOT OTHERWISE PROVIDED FOR
- G01M3/00—Investigating fluid-tightness of structures
- G01M3/02—Investigating fluid-tightness of structures by using fluid or vacuum
- G01M3/26—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors
- G01M3/32—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors for containers, e.g. radiators
- G01M3/3281—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors for containers, e.g. radiators removably mounted in a test cell
- G01M3/329—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors for containers, e.g. radiators removably mounted in a test cell for verifying the internal pressure of closed containers
Abstract
The invention discloses a leakage detection device and a detection method of a radioactive gas sealed container, wherein the leakage detection device comprises a pipeline, a valve, a shielding chamber, a pressure gauge, a radioactive gas detector, a circulating pump and a pressure regulator, wherein the valve is arranged on each of two sides of the shielding chamber, and the valve, the shielding chamber, the radioactive gas detector and the circulating pump are connected in series through the pipeline to form a detection pipeline; the shielding chamber is used for placing the radioactive gas sealed container to be detected; the pressure gauge is used for detecting the pressure in the shielding chamber; the circulating pump is used for realizing the circulating flow of the gas in the detection pipeline; the pressure regulator is used for regulating the pressure in the shielding chamber; the radioactive gas detector is used for detecting the content of radioactive gas in the detection pipeline. The scheme is simple and easy to operate, the possible leakage rate and the leakage total amount of the radioactive gas sealed container can be accurately calculated, meanwhile, the safety of operators can be improved, and the environment pollution caused by leakage is avoided.
Description
Technical Field
The invention belongs to the technical field of radioactive gas leakage detection, and particularly relates to a leakage detection device and a detection method for a radioactive gas sealed container.
Background
If the radioactive gas sealed container such as a thickness measuring source leaks, environmental pollution can be caused, the dose of the irradiated personnel exceeds the standard, and environmental and personnel safety accidents are caused. Therefore, leak testing of hermetically stored radioactive gas sources and hermetically sealed radioactive gas sources is one of the important safety measures for storing and using radionuclides, particularly gaseous radionuclides.
With respect to leak testing methods for sealed radioactive gas sources, such as thickness measuring sources, both radioactive and non-radioactive testing methods are generally used. The radioactive inspection method mainly comprises a soaking inspection method and a gas injection inspection method, and the non-radioactive inspection method comprises helium mass spectrometer leak inspection and bubbling method leak inspection.
The principle of the immersion test method is to measure the leakage of the containment radioactive gas according to how much the immersion solution adsorbs the dissolved radioactive mass. Because different radionuclides have different solubilities in a solution and are difficult to quantify, the method can only qualitatively analyze the leakage condition; in addition, once the generated soaking solution contains radioactive substances, the generated soaking solution needs to be treated as radioactive waste liquid, and the radioactive waste liquid treatment process has the disadvantages of complicated treatment flow, high cost and easy pollution.
The principle of the gas-jet inspection method is to measure the leakage of radioactive gas according to the adsorption quantity of leaked radioactive nuclide by the solid adsorbent. The solid adsorbent is low in adsorption efficiency and easy to release into the air, and the leakage condition can only be qualitatively analyzed according to the measurement result. In addition, the requirement on the measurement time is strict, the radioactive activity of the adsorbent is measured immediately when the radioactive source is required to be taken out, the release condition of the radioactive gas of the adsorbent is difficult to accurately judge, and the safety risk is high for personnel engaged in operation measurement.
The plastic scintillation counting method is a method for analyzing the activity of gas in a sealed chamber, and because the detection efficiency of a plastic scintillator is low, migration, diffusion and self-absorption of radioactive gas in a small chamber are difficult, so that the leakage rate of the sealed radioactive gas is difficult to accurately estimate.
The helium mass spectrometer leak detection method adopts simulation non-radioactive sample detection, and cannot correctly reflect the actual sample leak rate condition containing radioactive gas.
The leakage inspection by the bubbling method needs to be soaked in a solution, so that the surface cleaning treatment needs to be carried out on the sealed radioactive gas containing container no matter whether the leakage exists or not; the method needs heating, so that the internal pressure of the container is increased, unsafe factors exist, the pressure is easily increased and exceeds the design pressure limit of the container, or the container is cracked and leaked from a weak point to form the unsafe factors; the bubbling method analyzes the leakage condition by calculating the bubble overflow rate, and the bubble overflow rate is influenced by various factors such as internal pressure, temperature, bubble size, solution medium type and the like, so that the leakage rate is difficult to accurately obtain.
Disclosure of Invention
In view of the above, the present invention discloses a leak detection apparatus and a leak detection method for radioactive gas sealed containers, which overcome or at least partially solve the above problems.
In order to achieve the purpose, the invention adopts the following technical scheme:
the embodiment of the invention discloses a leakage detection device of a radioactive gas sealed container, which comprises a pipeline, valves, a shielding chamber, a pressure gauge, a radioactive gas detector, a circulating pump and a pressure regulator, wherein the valves are arranged on two sides of the shielding chamber, and the valves, the shielding chamber, the radioactive gas detector and the circulating pump are connected in series through the pipeline to form a detection pipeline;
the shielding chamber is used for placing the radioactive gas sealed container to be detected;
the pressure gauge is used for detecting the pressure in the shielding chamber;
the circulating pump is used for realizing the circulating flow of the gas in the detection pipeline;
the pressure regulator is used for regulating the pressure in the shielding chamber;
the radioactive gas detector is used for detecting the content of the radioactive gas in the detection pipeline.
Optionally, the pressure regulator comprises a vacuum pump, and the vacuum pump regulates the pressure in the detection pipeline to be lower than the pressure in the radioactive gas sealed container, so that the radioactive gas in the radioactive gas sealed container leaks out, wherein the pressure difference is in a range of 20-40kPa, and/or,
the detection pipeline also comprises an inflation pipeline for inflating the detection pipeline, and the inflation pipeline is used for supplementing gas to the detection pipeline according to the requirement during detection.
Optionally, the number of the shielding chambers is several, and valves are arranged on two sides of each shielding chamber.
Optionally, the shielding body of the shielding chamber is formed by laminating at least three layers of materials, and sequentially comprises from inside to outside: aluminum layer, lead layer, stainless steel layer.
Optionally, be provided with the access on the shielded room radioactive gas sealed container's window, be provided with the sealed window on the window, the sealed window periphery is provided with the silica gel sealing washer, the sealed window is in through the lock hoop closure on the shielded room.
Optionally, the leakage detection device is connected by a welding mode and/or a vacuum connection radial seal VCR joint, the pipe is made of stainless steel, and the inner surface of the pipe is subjected to mirror polishing treatment.
Optionally, the leakage detection device further comprises a gas recovery container, the gas recovery container can be communicated with the detection pipeline, and a radioactive gas adsorption material is arranged in the gas recovery container.
Optionally, the volume of the detection line and the radioactive gas detector are calibrated for measurement and/or metering.
The embodiment of the invention also discloses a detection method for detecting radioactive gas leakage by adopting any one of the detection devices, which comprises the following steps:
step 2, closing valves on two sides of the shielding chamber, adjusting the pressure in the shielding chamber by using the pressure adjusting device, and stopping adjusting the pressure in the shielding chamber when the difference value of the pressure value in the shielding chamber, which is displayed by the pressure measuring meter and is smaller than the pressure value in the radioactive gas sealed container, reaches a preset pressure difference value range value;
step 3, after the radioactive gas sealed container is kept still in the shielding chamber for a preset time period, opening valves on two sides of the shielding chamber, the circulating pump and the radioactive gas detector to enable leaked radioactive gas to circulate in the detection pipeline;
step 4, after circulation of a preset time length, reading a pressure value of the pressure gauge, reading a radioactive gas concentration value of the radioactive gas detector, and calculating to obtain a leakage amount according to an ideal gas equation and a volume value of the detection pipeline; and/or obtaining the leakage rate according to the leakage amount and the standing preset time.
Optionally, the leakage detection apparatus further includes a gas recovery container, the gas recovery container is communicated with the detection pipeline, and the detection method further includes:
step 6, after the gas in the detection pipeline reaches the discharge standard, discharging the gas in the detection pipeline;
and 7, closing the valve, the circulating pump, the radioactive gas detector, the pressure gauge and the pressure regulator.
The invention has the advantages and beneficial effects that:
the sealed radioactive gas leakage inspection device has a gas closed circulation function, ensures that gas does not contact any equipment or medium in the external environment in the measurement process, reduces the loss of gas to be measured, and improves the measurement accuracy;
the device does not need soaking solution, does not need temperature rise and constant temperature treatment, and realizes clean, pollution-free, rapid and simple sealed radioactive gas leakage inspection;
the device belongs to the direct measurement of radioactive gas leakage, and avoids the defect that the leakage rate of a sample containing the actual radioactive gas cannot be correctly reflected by adopting a simulated non-radioactive sample inspection method in a helium mass spectrometer leakage inspection method;
furthermore, the device designs a detection pipeline for realizing gas circulation, is provided with a high-precision pressure sensor, adopts a standard container and a detection instrument which are calibrated by a measuring institute, accurately calibrates the volume of the pipeline of the circulation system, accurately obtains the gas flow rate in unit time in the system by combining a flow pump capable of setting the gas flow rate, and can accurately obtain the total gas content by utilizing an ideal gas state equation;
the device can make all leaked gas pass through the radioactive gas detector on the premise of not taking out the radioactive gas sealed container, thereby effectively avoiding the influence of the adsorption efficiency of the adsorbent in the gas-jet inspection method and the influence of the solid plastic scintillation detector on the diffusion and migration of the radioactive gas, and avoiding the harm of the leaked gas to the air; the operation is simple, the safety of personnel is improved, the accuracy is improved due to the fact that all leaked gas is detected, and the leakage rate of radioactive gas can be quantitatively analyzed.
The device is provided with a gas recovery container, and aiming at various radioactive gases (such as common inert radioactive gases like krypton-85, xenon-133, radon-222 and the like and active radioactive gases like tritium which are easy to generate chemical reaction), an active porous adsorbent is adopted in combination with a low-temperature adsorption method, so that the recycle gas recovery of more than 99.5 percent is realized, the gas emission is effectively reduced, and the environmental pollution event is avoided;
the device designs a radioactive shielding chamber, and adopts a layout mode of combining an inner layer low atomic number material such as aluminum and an outer layer high atomic number material such as lead steel and the like according to the decay characteristics of the gas radioactive nuclide, so that the harm of bremsstrahlung X rays, gamma rays and the like caused by the gas radioactive nuclide to personnel is effectively reduced;
the shielding chamber has a simple structure, adopts a large-opening access window and adopts a silica gel simple sealing mode, is easy to operate and replace the radioactive gas sealing container for storage and taking;
the pipeline is made of stainless steel materials with mirror polished inner walls, such as 316L, so that the measurement error caused by gas adsorption is reduced;
an imported radioactive gas detector such as ASM-4 is adopted, and the radioactive concentration of different flows of gas passing through an ionization chamber of the detector can be directly measured by using an inert gas probe, so that the accurate measurement of the leakage rate is realized;
the device adopts a plurality of stations, such as six stations, and can independently or simultaneously carry out leakage detection; the same radioactive gas or a plurality of different radioactive gas sealed containers can be tested simultaneously (the detection is different);
calibration instrument for measuring institutions: kr-85 gas with standard concentration is adopted, and the gas concentration is respectively 3.4E +6Bq/m3，7.8E+6Bq/m3,1.7E+7Bq/m3,3.2E+7Bq/m3,5.7E+7Bq/m3，1.9E+8Bq/m3Measuring the corresponding counting rate of the readings of the radioactive gas detector, which are respectively 1.417E-5/s/Bq/m3，1.418E-5/s/Bq/m3，1.410E-5/s/Bq/m3，1.384E-5/s/Bq/m3，1.396E-5/s/Bq/m3，1.396E-5/s/Bq/m3It can be known that the linearity of the response of the radioactive gas detector ASM-4 to gas is 98.6%;
by adopting the inspection method, the gas is leaked out by keeping a certain internal and external pressure difference, but the radioactive gas is not leaked out by changing the temperature; a circulation method is innovatively adopted, so that leaked gas is diluted and uniformly mixed, and the testing accuracy is ensured.
Drawings
Various other advantages and benefits will become apparent to those of ordinary skill in the art upon reading the following detailed description of the preferred embodiments. The drawings are only for purposes of illustrating the preferred embodiments and are not to be construed as limiting the invention. Also, like reference numerals are used to refer to like parts throughout the drawings. In the drawings:
FIG. 1 is a schematic diagram of a leak detection apparatus for radioactive gas containment in accordance with an embodiment of the present invention;
FIG. 2(a) is a front view of a shielded room in one embodiment of the invention;
FIG. 2(b) is a left side view of a shielded room in one embodiment of the invention;
fig. 3 is an overall flow chart of a leak detection method of a radioactive gas sealed container in an embodiment of the present invention.
In the figure: 1 is a vacuum pump; 2-20 is a valve; 21-26 are shielding chambers; 27 is a pipeline; 28 is a circulating pump; 29 is a radioactive gas detector; 30 is a gas recovery container; 31-36 are pressure gauges; 37 is an inflation inlet;
2101 is an air inlet; 2102 is a locking collar; 2103 is an access window; 2104 is an air outlet; 2105 is a weld; 2106 sealing the window; 2107 is a shield.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the technical solutions of the present invention will be described in detail and fully with reference to the accompanying drawings. It is to be understood that the described embodiments are merely exemplary of the invention, and not restrictive of the full scope of the invention. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
It is to be understood that the terms "comprises/comprising," "consisting of … …," or any other variation, are intended to cover a non-exclusive inclusion, such that a product, device, process, or method that comprises a list of elements does not include only those elements but may include other elements not expressly listed or inherent to such product, device, process, or method if desired. Without further limitation, an element defined by the phrases "comprising/including … …," "consisting of … …," or "comprising" does not exclude the presence of other like elements in a product, device, process, or method that comprises the element.
It will be further understood that the terms "upper," "lower," "front," "rear," "left," "right," "top," "bottom," "inner," "outer," and the like, refer to an orientation or positional relationship as shown in the drawings, which is meant only to facilitate describing the invention and to simplify the description, and do not indicate or imply that the referenced device, component, or structure must have a particular orientation, be constructed or operated in a particular orientation, and is not to be construed as limiting the invention.
In the present invention, unless otherwise expressly stated or limited, the terms "mounted," "connected," "secured," and the like are to be construed broadly and can, for example, be fixedly connected, detachably connected, or integrally formed; can be mechanically or electrically connected; either directly or indirectly through intervening media, either internally or in any other relationship. The specific meanings of the above terms in the present invention can be understood by those skilled in the art according to specific situations.
The technical solutions provided by the embodiments of the present invention are described in detail below with reference to the accompanying drawings.
Example 1
Referring to fig. 1, an embodiment 1 of the present invention discloses a leakage detection apparatus for a radioactive gas sealed container, which includes a pipeline 27, valves 2 to 20, one or more shielding chambers 21 to 26, pressure gauges 31 to 36, a radioactive gas detector 29, a circulation pump 28, and a pressure regulator, wherein the valves 6 to 17 are disposed on both sides of the shielding chambers 21 to 26, and the valves, the shielding chambers, the radioactive gas detector 29, and the circulation pump 28 are connected in series through the pipeline 27 to form a detection pipeline; preferably, the valves on the two sides are respectively arranged close to the shielding chamber, so that the shielding chamber can be controlled conveniently without causing damage to other parts of the detection pipeline by radioactive gas which may leak.
Specifically, the shielding chambers are used for placing the radioactive gas sealed container to be detected, as shown in fig. 1, preferably, the number of the shielding chambers is 6, and valves 6 to 17 are arranged on two sides of each of the shielding chambers 21 to 26.
The conduit 27 is made of 316L stainless steel with a mirror-polished inner surface, although materials of similar materials are within the scope of the present invention. Preferably, the outer diameter of the pipeline is 6mm, the wall thickness is 1.5mm, and the connection mode adopts a Vacuum coupling radial Seal (VCR) joint with surface sealing to ensure the sealing property.
Referring to fig. 2, the shielding chamber has an air inlet 2101 at the upper end, an air outlet 2104 at the lower end, a window 2103 for accessing the sealed container is arranged at the front side, the window is welded on a shielding body 2107 by welding, and a sealed window 2106 is arranged on the window, and the sealed window 2106 is locked on the window 2103 by a locking hoop 2102.
In order to prevent the leakage of radioactive gas possibly existing in the shielding chamber, the shielding body of the shielding chamber is formed by laminating at least three layers of materials, and a layout mode of combining an inner layer of low atomic number material such as aluminum and an outer layer of high atomic number material such as lead steel is adopted, so that the injury to personnel caused by bremsstrahlung X rays, gamma rays and the like caused by gas radioactive nuclides is effectively reduced. Preferably, the shield 2107 comprises, in order from the inside to the outside: aluminum layer, lead layer, stainless steel layer.
In addition, the pressure gauges 31-36 are used for detecting the pressure in the shielding chambers 21-26, preferably, the inlet pressure gauge has a display value of 0-100kPa, and the interface between the pressure gauge and the pipeline is a VCR joint so as to ensure the sealing property and improve the detection precision.
The pressure regulator is used for regulating the pressure in the shielding chamber, and the pressure measuring meter and the pressure regulator are matched, so that the pressure in the shielding chamber is adjusted to be suitable for the degree that radioactive gas in a sealed container such as a thickness measuring source is easy to release, and detection is convenient to carry out.
Specifically, the pressure regulator includes a vacuum pump 1, an inflator (not shown) or an inflation port 37 to inflate or deflate the test line as needed for testing, and to regulate the pressure in the shield room or the test line. Preferably, the pressure in the radioactive gas containment vessel is 20-40kPa greater than the pressure in the shielded chamber, thereby facilitating leakage during standing of the shielded chamber if there is leakage from the radioactive containment vessel.
The circulating pump 28 is used for realizing the circulating flow of the gas in the detection pipeline, so that the gas to be detected is uniformly mixed and filled in the volume of the whole detection pipeline. Preferably, the flow rate of the circulating pump is adjustable, the flow rate range of the circulating pump at least comprises 10-15L/min, and when the detected flow rate is low, the cleaning gas can be quantitatively input through the inflating pump or the inflating opening 37, so that the gas circulation and filling are convenient.
The reflective gas detector 29 is used for detecting the content of the radioactive gas in the detection pipeline. Preferably, the radioactive gas detector is an inlet detector ASM-4 comprising 2 5cm diameter proportional counter tube detectors (closed, working gas Ar/CO)2) The 4 π efficiency was 6.4% (Kr-85). In particular, to ensure the detection accuracy, the detector may be calibrated by a measuring yard, for example, after the inlet detector is calibrated, the detection efficiency of the detector for Kr-85 gas is determined to be 6.2%. The gas detector can monitor the concentration of radioactive gas flowing through the monitor, and the display value is Bq/L.
The volume of the detection pipeline and the radioactive gas detector 29 detect the radioactive gas according to the volume of the detection pipeline and the detection instrument which are accurately measured and calibrated through measurement and/or metering calibration, so that the detection precision is ensured. Specifically, a standard container calibrated by a measuring yard is adopted to accurately calibrate the volume of a circulating system pipeline, and the sum value range of the volumes of all pipelines and a single gas shielding chamber at the circulating section is preferably 2-3L after calibration.
Further, the leakage detection device further comprises a gas recovery container 30, the gas recovery container 30 can be communicated with the detection pipeline, a radioactive gas adsorption material is arranged in the gas recovery container, and the gas recovery container can be placed in a cooling medium such as liquid nitrogen during adsorption, so that the radioactive gas is automatically adsorbed into the gas recovery container.
The design of the gas recovery container is adjusted according to different radionuclides, when the nuclides are inert radioactive gases, activated carbon is filled in the gas recovery container, the gas recovery container is soaked in liquid nitrogen during recovery, when the concentration of the radioactive gases in the radioactive gas leakage inspection device is higher, the gas recovery container is soaked in the liquid nitrogen, and then the radioactive gases in the radioactive gas leakage inspection device are recovered into the gas recovery container by utilizing the principles of physical adsorption of the high specific surface area of the activated carbon and expansion and contraction of the gases, so that the radioactive gases are ensured not to be leaked; when the nuclide is active radioactive gas, various materials which are easy to have physical and chemical reactions with the nuclide are adopted for adsorption, and the adsorption efficiency reaches over 99.5 percent.
Example 2
Referring to the overall flow of the detection method shown in fig. 3, embodiment 2 of the present invention discloses a detection method for detecting radioactive gas leakage by using any one of the detection apparatuses described above, where the detection method includes:
step 2, closing valves 6 and 7 at two sides of the shielding chamber, adjusting the pressure in the shielding chamber 21 to 5Pa by using the pressure adjusting device 1, and stopping adjusting the pressure in the shielding chamber when the difference value, which is displayed by the pressure gauge 31, of the pressure value in the shielding chamber 21 and is smaller than the pressure value in the radioactive gas sealed container reaches a preset pressure difference value range value, such as 20-40 kPa;
step 3, after the radioactive gas sealed container is kept still in the shielding chamber 21 for a preset time period such as 8-24 hours, opening valves 6-7 at two sides of the shielding chamber, the circulating pump 28 and the radioactive gas detector 29 to enable leaked radioactive gas to circulate in the detection pipeline, so that the radioactive gas is diffused and balanced, and the concentration is uniform; it should be noted that if the pressure of the gas in the detection pipeline is too low to facilitate the circulation of the gas in the pipeline, a certain amount of gas can be supplied through the gas charging port 37.
And 4, after circulation for a preset time period such as 5-10min, reading the pressure value of the pressure gauge 31, reading the radioactive gas concentration value C of the radioactive gas detector 29, multiplying the value by the circulation volume V of the device to obtain the radioactive amount M of the leaked gas, and calculating the leakage rate V through standing time.
Preferably, the leakage detection apparatus further includes a gas recovery container 30, the gas recovery container 30 is communicated with the detection pipeline, and the detection method further includes:
step 6, after the gas in the detection pipeline reaches the emission standard, opening valves 4 and 5, and discharging the gas in the detection pipeline through a vacuum pump 1;
and 7, closing the valve and each instrument, then closing the power supply, and finishing the detection.
Compared with the existing leakage detection method, the method provided by the invention obviously overcomes the defects that the existing detection method is complex in measurement process, low in measurement accuracy, incapable of quantitative analysis and only capable of qualitative analysis, and meanwhile, the potential hazard that the existing detection method cannot avoid radioactive irradiation dose to operators and releases radioactive gas to the environment is avoided, and the safety of people and the environment is improved:
1. the leakage inspection device disclosed by the embodiment realizes the complete measurement of radioactive gas, and avoids the defect that the adsorption sampling efficiency is difficult to estimate by the existing inspection method; in addition, in the operation process, the operation processes of soaking solution, heating and constant temperature system, adsorbent and the like required by the existing detection method are omitted;
2. the detection device realizes gas circulation and radioactive gas recovery in the detection pipeline, so that the gas to be detected can be completely recovered to the gas recovery container, and meanwhile, the shielding chamber is provided with a plurality of shielding layers, so that the harm of radioactive gas radiation dose to human bodies is obviously reduced;
3. according to the scheme, the radioactive gas detector calibrated by a measuring hospital is adopted, and compared with the existing detection method which can only qualitatively analyze and evaluate the leakage condition, the total leakage amount and the leakage rate can be quantitatively analyzed;
4. the detection method has strong operability and simple operation, and can meet the leakage detection and measurement of various radioactive gases;
5. the device can simultaneously detect a plurality of types and a plurality of radioactive gases, has high detection efficiency, and particularly has extremely high detection sensitivity for Kr-85 and Xe-133;
6. through six-station design, the detection capability and the detection speed are improved, and the defect that the traditional detection method only can be used for one-by-one detection is overcome.
The above description is only an embodiment of the present invention, and is not intended to limit the scope of the present invention. Any modification, equivalent replacement, improvement, extension, etc. made within the spirit and principle of the present invention are included in the protection scope of the present invention.
Claims (10)
1. The leakage detection device of the radioactive gas sealed container is characterized by comprising a pipeline, valves, a shielding chamber, a pressure measuring meter, a radioactive gas detector, a circulating pump and a pressure regulator, wherein the valves are arranged on two sides of the shielding chamber, and the valves, the shielding chamber, the radioactive gas detector and the circulating pump are connected in series through the pipeline to form a detection pipeline;
the shielding chamber is used for placing the radioactive gas sealed container to be detected;
the pressure gauge is used for detecting the pressure in the shielding chamber;
the circulating pump is used for realizing the circulating flow of the gas in the detection pipeline;
the pressure regulator is used for regulating the pressure in the shielding chamber;
the radioactive gas detector is used for detecting the content of the radioactive gas in the detection pipeline.
2. The leak detection apparatus as defined in claim 1, wherein the pressure regulator comprises a vacuum pump that regulates the pressure in the detection line to be less than the pressure in the radioactive gas containment vessel such that the radioactive gas in the radioactive gas containment vessel leaks out, wherein the pressure difference is in the range of 20-40kPa, and/or,
the detection pipeline also comprises an inflation pipeline for inflating the detection pipeline, and the inflation pipeline is used for supplementing gas to the detection pipeline according to the requirement during detection.
3. The leak detection apparatus according to claim 1, wherein the number of the shield rooms is plural, and a valve is provided on both sides of each of the shield rooms.
4. A leak testing device according to any of claims 1-3, wherein the shielding body of the shielding chamber is formed by laminating at least three layers of materials, and comprises, in order from the inside to the outside: aluminum layer, lead layer, stainless steel layer.
5. The leak detection device according to any one of claims 1 to 3, wherein the shielding chamber is provided with a window for storing and taking the radioactive gas sealed container, the window is provided with a sealing window, a silica gel sealing ring is arranged on the periphery of the sealing window, and the sealing window is locked on the shielding chamber through a locking hoop.
6. The leak testing apparatus of claim 1 wherein said leak testing apparatus is connected by welding and/or vacuum connection radial seal VCR joints, said tubing is made of stainless steel, and the inner surface of said tubing is mirror polished.
7. The leak detection apparatus as defined in claim 1, further comprising a gas recovery vessel communicable with the detection conduit, the gas recovery vessel having a radioactive gas adsorbing material disposed therein.
8. The leak detection apparatus as recited in claim 1, wherein the volume of the detection line and the radioactive gas detector are calibrated for measurement and/or metering.
9. A method of detecting a radioactive gas leak using the detection apparatus according to any one of claims 1 to 8, wherein the detection method comprises:
step 1, placing the radioactive gas sealed container in the shielding chamber;
step 2, closing valves on two sides of the shielding chamber, adjusting the pressure in the shielding chamber by using the pressure adjusting device, and stopping adjusting the pressure in the shielding chamber when the difference value of the pressure value in the shielding chamber, which is displayed by the pressure measuring meter and is smaller than the pressure value in the radioactive gas sealed container, reaches a preset pressure difference value range value;
step 3, after the radioactive gas sealed container is kept still in the shielding chamber for a preset time period, opening valves on two sides of the shielding chamber, the circulating pump and the radioactive gas detector to enable leaked radioactive gas to circulate in the detection pipeline;
step 4, after circulation of a preset time length, reading a pressure value of the pressure gauge, reading a radioactive gas concentration value of the radioactive gas detector, and calculating to obtain a leakage amount according to an ideal gas equation and a volume value of the detection pipeline; and/or obtaining the leakage rate according to the leakage amount and the standing preset time.
10. The testing method of claim 9, wherein the leak testing apparatus further comprises a gas recovery vessel in communication with the test line, the testing method further comprising:
step 5, judging whether the leakage amount reaches a preset threshold value, if so, communicating the detection pipeline with the gas recovery container, and soaking the gas recovery container in a cooling medium to enable the gas in the detection pipeline to enter the gas recovery container;
step 6, after the gas in the detection pipeline reaches the discharge standard, discharging the gas in the detection pipeline;
and 7, closing the valve, the circulating pump, the radioactive gas detector, the pressure gauge and the pressure regulator.
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| CN202110145566.3A CN112857696A (en) | 2021-02-02 | 2021-02-02 | Leakage detection device and detection method for radioactive gas sealed container |
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| CN202110145566.3A Pending CN112857696A (en) | 2021-02-02 | 2021-02-02 | Leakage detection device and detection method for radioactive gas sealed container |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN114235308A (en) * | 2021-12-09 | 2022-03-25 | 武汉欧格莱液压动力设备有限公司 | Method for testing sealing performance of hydraulic element |
| CN114739586A (en) * | 2022-04-19 | 2022-07-12 | 吉林大学 | Leakage detection equipment for radioactive substance cleaning box |
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| CN114739586A (en) * | 2022-04-19 | 2022-07-12 | 吉林大学 | Leakage detection equipment for radioactive substance cleaning box |
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