56 results about "Radioactive gas" patented technology

The invention discloses radioactive gas separation and purification equipment, a radioactive gas separation and purification method, a radioactive gas separation and purification medium and radioactive gas separation and purification equipment, and relates to the technical field of radioactive gas separation and purification. The radioactive gas separation and purification equipment comprises a first separation column, a second separation column, a carrier gas container, a quantitative structure, a chromatographic column, a detection assembly, a first control valve, a storage container, a temperature controller and a to-be-treated gas container. The carrier gas container is connected with the first control valve, and the to-be-treated gas container, the quantitative structure, the first control valve, the first separation column, the second separation column, the chromatographic column and the storage container are sequentially connected. The first separation column, the second separation column and the chromatographic column are all filled with stationary phases which are all used for purifying target substances in the to-be-treated gas based on different adsorption rates of the stationary phases relative to different substances. Therefore, due to the arrangement of the first separation column, the second separation column and other structures, large-volume ambient air or gaseous effluent can be purified, and subsequent radioactive substance concentration measurement is facilitated.

The protective transportation device for the medical radiopharmaceuticals comprises a protective barrel, a protective cover and a plurality of adsorption assemblies arranged in the protective barrel, storage grooves are formed among the adsorption assemblies, the adsorption assemblies are distributed in the circumferential direction of an inner cavity of the protective barrel at equal angles, and the radial sections of the adsorption assemblies are each of a 90-degree fan-shaped structure; each adsorption assembly comprises a plurality of splicing frames, every two adjacent splicing frames are tightly attached, circulating holes are formed in the circumferential outer walls of the splicing frames, the multiple adsorption assemblies distributed in the circumferential direction at equal angles are arranged in the protection barrel, the radial section of each adsorption assembly is of a 90-degree fan-shaped structure, and the multiple adsorption assemblies are formed by stacking the multiple splicing frames; the circulation holes of the adjacent splicing frames are formed in a staggered mode to form a continuous snake-shaped airflow channel, the structure remarkably prolongs the escape path of radioactive gas, the gas is forced to undergo multiple times of steering and diffusion resistance when passing through the multiple adsorption layers, and therefore the leakage risk is effectively reduced.

The utility model provides a gas purification system of a reactor. The gas purification system comprises a purification pipeline, and an inert gas adsorber, an iodine adsorber, a polonium processor, a filter and a radioactivity analyzer which are arranged on the purification pipeline. And the inert gas adsorber is used for removing inert gas in the mixed gas. The iodine adsorber is used for removing iodine in the mixed gas. The polonium processor is used for removing polonium in the mixed gas. And the filter is used for removing small particles in the mixed gas. And the radioactivity analyzer is used for detecting the radioactivity of the mixed gas. According to the gas purification system, aiming at the characteristics of radioactive substances of the metal fast reactor, a four-stage purification treatment device is arranged to remove radioactive gas in the mixed gas, and in addition, a radioactivity analyzer is further arranged and used for detecting and judging whether the radioactivity in the gas meets the emission standard or not; and the problem of radioactive substance release caused by leakage of the containment is effectively avoided.

The invention provides a molten salt reactor radioactive gas removal device which comprises a main loop module, a gas injection module, a tail gas analysis and treatment module and an observation module, one end of the main loop module is connected with the gas injection module, the other end of the main loop module is connected with the tail gas analysis and treatment module, and the observation module is connected with the tail gas analysis and treatment module. The main loop module comprises a bubbler and a separator, the bubbler is filled with liquid for dissolving gas, and the observation module is arranged at a visual window on the side of a body of the bubbler and the separator; when the radioactive gas is removed, cavitation microbubbles and carrier gas microbubbles which are used for dissolving the radioactive gas are separated out by the bubbler, the cavitation microbubbles and the carrier gas microbubbles form a gas core by the separator, and the gas core is treated by the tail gas analysis and treatment module. According to the invention, deep dissolution and gas removal can be realized, the system sealing performance is good, the gas can be ensured not to leak, and the safety of operators and the environment is ensured.

The invention relates to the technical field of isotope batteries and discloses a nanopore-containing power generation assembly. The nanopore-containing power generation assembly comprises a transduction layer, the loading layer is arranged on the surface of the transduction layer in advance, and the loading layer is provided with preset nanopores. The technical problem that in the preparation process of the radioactive source in the isotope battery, due to the fact that the hydrogen absorption temperature of a hydrogen storage material is high, large thermal mismatching exists between a transducer device and the hydrogen storage material, growth stress is generated in the phase change process, and consequently the transducer device may have serious structural damage can be solved; the loading layer arranged on the surface of the transduction layer in advance is adopted, and the loading layer is provided with the nanopore structure, so that when the loading layer serves as a basic structure for preparing the isotope power generation assembly, for example, nanopores are filled with radioactive gas such as tritium, the loading layer structure is stable, and the isotope power generation assembly is prepared. The probability that the energy conversion layer structure is damaged due to growth stress generated in the phase change process can be reduced, and then it is guaranteed that the structure of the prepared isotope power generation assembly is stable.

To provide a radioactive substance removal device capable of enhancing efficiency of moisture removal as pretreatment of radioactive gas.SOLUTION: And a radioactive substance remover 3 that removes a radioactive substance from the gas from which moisture has been removed by the moisture remover 2, in which the moisture remover 2 has a flow path through which the gas flows, and removes moisture by cooling the gas in the flow path to frost moisture on a predetermined portion, and the flow path has a narrower flow path cross-sectional area or a shorter cooling wall surface distance on a downstream side than on an upstream side.SELECTED DRAWING: Figure 1

The embodiment of the invention relates to a radioactive gas measuring device, comprising: a chamber body, in which a gas chamber for accommodating gas to be measured is formed, and the chamber body is provided with a mounting port communicated with the gas chamber; the detector is arranged at the mounting opening, the detection surface of the detector faces the interior of the air chamber, and the detector blocks the mounting opening to form a sealing boundary of the air chamber; wherein the chamber body or the detector is provided with an air inlet channel and an air outlet channel which are communicated with the air chamber. The PIPS detector directly blocks the mounting port and forms a sealed boundary, so that the direct contact between the detection surface and the detected gas is realized, the attenuation of a window material to alpha particles or low-energy beta particles is eliminated, the measurement sensitivity is improved, and the limitation that the detector in the traditional measurement device needs to be placed in an independent sleeve or measured through a protection window is overcome; meanwhile, the detector serves as the top wall of the cavity body and is matched with the air inlet channel and the air outlet channel which are integrated on the cavity body or the detector, so that the whole device is more compact in structure.

The utility model relates to a high-sensitivity radioactive gas activity measuring device which comprises a set of double-beta plastic scintillator detector, two sets of gamma detectors, an anti-cosmic ray detector group and a digital coincidence circuit. The double-beta plastic scintillator detector and the gamma detectors are arranged in the lead shielding chamber, the double-beta plastic scintillator detector is arranged between the two gamma detectors, and mutual interference among radioactive gases in the double-beta plastic scintillator detector can be eliminated through coincidence and anticoincidence among four paths of signals; and the anti-cosmic ray detector group is used for shielding coincidence signals generated by cosmic rays in the double-beta plastic scintillator detector and the gamma detector. According to the utility model, a gamma detector original spectrum, an anti-cosmic ray gamma spectrum, a beta-gamma coincidence spectrum and an anti-cosmic ray beta-gamma coincidence spectrum, wherein the beta-gamma coincidence spectrum and the anti-cosmic ray beta-gamma coincidence spectrum are used for eliminating mutual influence among different radioactive gases. According to the utility model, synchronous measurement of different radioactive gases can be realized, and the detection sensitivity of the radioactive gases can be greatly improved.

The invention relates to the technical field of air purification devices in the nuclear field, and discloses an air purification device for emergency treatment of radioactive gas in a nuclear power plant, the air purification device comprises a base, a backflushing mechanism is arranged above the base, a bombardment mechanism is arranged above the base, the backflushing mechanism comprises a tower body, and the bottom surface of the tower body is fixedly connected with the upper surface of the base; an activated carbon bed layer is clamped in the tower body, a treatment box is fixedly mounted on the upper surface of the base, the end, close to the tower body, of the treatment box penetrates into the tower body, a filter screen is fixedly mounted on the inner wall of the treatment box, and an electrostatic dust collector is fixedly mounted on the inner wall of the treatment box. According to the air purification device for emergency treatment of the radioactive gas in the nuclear power station, the backflushing mechanism is arranged, nitrogen in the storage box is sprayed to the activated carbon bed layer through the air pump after passing through the conveying pipe and the spray head, and therefore cakes on the activated carbon bed layer are blown off through airflow; the problem that the purification efficiency of radioactive gas is reduced because a large number of cakes adhere to the activated carbon bed layer is avoided.

The invention discloses an ultrahigh pressure air valve component unit performance test device and method, and the device comprises an ultrahigh pressure compression closed circulation system which comprises an ultrahigh pressure air cylinder, a plunger and an ultrahigh pressure air valve test component, and ultrahigh pressure air enters an air cylinder compression cavity through an air inlet pipeline along an air inlet channel; ultrahigh-pressure gas in the gas cavity compression cavity is exhausted to the ultrahigh-pressure pressure relief device through an exhaust channel, the ultrahigh-pressure pressure relief device is connected to the gas inlet pipeline through a bypass pipeline, and a cyclotron is arranged on the gas inlet pipeline, prepares the ultrahigh-pressure gas into radioactive gas and introduces the radioactive gas into the ultrahigh-pressure cylinder; a scintillation detector array is arranged outside the ultrahigh-pressure cylinder, covers the whole ultrahigh-pressure cylinder and is used for capturing the flowing range of radioactive gas in the ultrahigh-pressure cylinder. The device has the functions of accurate ultrahigh-pressure gas loading, adjustable cycle frequency, working performance monitoring and the like, so that effective experimental means and technical guarantee are provided for localization of key parts.

The utility model provides a kind of safety shell ring corridor's ventilation system, the safety shell ring corridor's ventilation system includes the first exhaust system, second exhaust system and third exhaust system for gas flow of safety shell ring corridor and safety shell outside. Among them, first exhaust system is set in first fire compartment, second exhaust system is set in second fire compartment, and first fire compartment and second fire compartment are physically separated. By designing two independent and mutually redundant first exhaust system and second exhaust system, for accident condition, collect the gas leakage from inner layer safety shell to safety shell ring corridor and the gas flow in safety shell ring corridor from outer layer safety shell, to reduce the radioactive gas leakage amount in safety shell ring corridor as far as possible, ensure the working stability of entire ventilation system. While third exhaust system maintains the negative pressure in safety shell ring corridor not less than design reference under normal condition.

1. The name of the design product: source box. 2. The use of the design product: encapsulation container of radioactive gas. 3. The design points of the design product: in shape. 4. The picture or photo that best indicates the design points: perspective view 1.

This invention discloses a radioactive waste liquid sampling and measurement device and system, belonging to the field of waste liquid sampling and measurement technology. The invention includes a sealed chassis with a rotating top plate on top. A top frame and a gas storage bladder frame are located at the center of the top of the rotating top plate. A sampling column and a cap-removing cylinder are sleeved on the top frame. A push rod is slidably sleeved inside the cap-removing cylinder, and a sleeve plate extending into the sealed chassis is located at the bottom of the push rod. The device, through the construction of a sealed environment, the double-fixed opening and closing of the sealed cover, and the quantitative sealing design of the sampling cylinder, prevents waste liquid leakage, splashing, and radioactive gas diffusion during sampling. The system relies on multi-module collaboration to achieve multi-dimensional data acquisition. By quantifying corrosion, leakage, and sampling exposure risks, it intelligently generates risk warnings, and the data is traceable, significantly improving sampling safety, reliability, and the standardization of nuclear facility waste liquid management.

The present application relates to radioactive gas detection and sandstone type uranium exploration technical field, especially a soil radon emission rate measuring device and its sandstone type uranium ore prospecting method, including gas collecting mechanism, including PVC gas collecting cylinder, the top of PVC gas collecting cylinder is provided with sealing cover, the top of sealing cover is provided with atmospheric temperature and humidity pressure sensor and internet of things antenna respectively, the bottom of PVC gas collecting cylinder is installed with soil temperature and humidity sensor;Detection mechanism, it is cylindrical sealing mechanism, including chip storage module, photon counter.The present application realizes the underground in-situ stable measurement of soil radon emission rate by vertically burying PVC gas collecting cylinder in a certain depth under the ground, makes radon diffuse and accumulate naturally in the relatively closed and stable space from bottom to top, avoids the sealing problem and wind field interference under the open environment condition of the ground.In addition, cooperating with internet of things remote transmission technology, long-term continuous automatic observation and unattended can be realized, which significantly improves the field exploration efficiency.

The utility model is applicable to the technical field of air purifiers, and discloses a circulating type toxic gas purifier which is applicable to purification of one or more gases such as radioactive gases, acid gases, alkaline gases, hydrogen sulfide, mercury vapor and the like. The modified activated carbon or the modified nano carbon fiber is used as an adsorption purification material of the purification module, so that the new purification module has higher adsorption capacity and adsorption selectivity, the purification efficiency of the purification machine can be improved, and the purification module can stably play a purification role when the purification machine is used for a long time in a high-humidity environment. The pulse discharge mechanism is arranged above the first air outlet of the air inlet fan, and the pulse discharge mechanism can be periodically started, so that air entering the machine shell can be ionized before entering the purification module, and when the ionized air enters the purification module, the air can be purified by the pulse discharge mechanism. The germs adsorbed on the modified activated carbon and the modified nano carbon fiber can be killed.

The application provides a method and system for real-time evaluation of adsorbent performance for radioactive gas treatment, and relates to the technical field of environmental monitoring. The method comprises the following steps: deploying a plurality of radioactivity sensors, temperature sensors and humidity sensors at different depths in the axial and radial directions of the adsorbent bed layer, collecting the radioactivity concentration, temperature and humidity at each position in real time through the sensors; and arranging ventilation impedance sensors and organic volatile sensors at the inlet and outlet of the adsorption unit and inside the bed layer, and synchronously collecting the ventilation impedance and the concentration of organic volatiles. The application realizes the global three-dimensional monitoring of the adsorption performance of the adsorbent, the accurate correction of multiple factors and the automatic discrimination of the safety threshold.

The invention relates to a radioactive gas extraction device with an external irradiation shielding function and a manufacturing and using method thereof. The device comprises a shell (1), a gas guide joint nut (2), a gas guide tube (3), a gas outlet joint (4), a gas outlet joint nut (5), a heating layer (6) and an external shielding layer (7), a radioactive gas to-be-extracted product is arranged in the shell (1), the gas guide connector nut (2) is communicated with the interior of the shell (1) through the gas guide pipe (3), the gas outlet connector nut (5) is communicated with the interior of the shell (1) through the gas outlet connector (4), and a heating layer (6) and an outer shielding layer (7) are sequentially arranged on the outer side of the shell (1). Compared with the prior art, the external radiation shielding function of the device is expected to achieve the effects of a traditional extraction hot chamber and an extraction furnace, and meanwhile, conditions can be created for continuous extraction of radioactive gas.

The utility model discloses a gas collection type toxic gas purifier which comprises a shell, a moving arm, a gas collection hood, a purification mechanism, a suction fan and a suction hood, wherein the purification mechanism, the suction fan and the suction hood are arranged in the shell; an exhaust outlet is formed in the side wall of the shell, and the suction fan is used for sucking outside air into the moving arm from the air collecting hood, then sucking the outside air into the shell, sucking the air purified by the purification mechanism into the air suction hood and then exhausting the air from the exhaust outlet; the moving arm comprises a plurality of sections of arm bodies, cylinders arranged at the end parts of the arm bodies, and rotating shafts for rotationally connecting the adjacent cylinders; and inner cavities of the arm body and the cylinder body are communicated with each other. By arranging the multiple sections of arm bodies capable of freely rotating and extending, the gas collecting hood can be close to places where gas pollutants are generated as much as possible to cover pollution sources at different positions, overflow of the gas pollutants is avoided to the maximum extent, and the air quality of a laboratory is ensured. The purifier is suitable for purifying radioactive gas, acid gas, alkaline gas, hydrogen sulfide, mercury steam and VOC organic gas.

The application discloses a surface pollution simulation detection method, device and system, and relates to the technical field of pollution simulation detection. The method comprises the following steps: constructing a fluid diffusion area three-dimensional space model according to space parameters of a to-be-detected area, and dividing the three-dimensional space model into a fluid domain space body grid and a ground surface boundary layer grid; adding radioactive gas particles, and setting the density and leakage rate of the radioactive gas particles; calculating the deposition velocity of the radioactive gas particles in the fluid domain space body grid and the particle concentration of the radioactive gas particles in the ground surface boundary layer grid according to a computational fluid dynamics method; further calculating the deposition flux and the deposition activity; assigning the deposition activity to NFC tags corresponding to the ground surface boundary layer grid, and detecting the NFC tags to complete surface pollution simulation detection. The embodiment of the application can more accurately predict the diffusion trend and deposition condition of radioactive pollutants, and improves the simulation accuracy.

The invention discloses an oxyhydrogen monitoring device for a radioactive container of a nuclear power plant, and relates to the field of radioactive gas detection.The oxyhydrogen monitoring device for the radioactive container of the nuclear power plant comprises a gas container, a gas pump, a detection assembly and a warning assembly, and the gas pump is used for pumping gas from the gas container receiving oxyhydrogen-containing radioactive waste gas; the gas container comprises a gas inlet pipe, a gas outlet pipe and a gas guide pipe, the gas guide pipe is connected with the gas inlet pipe and the gas outlet pipe, the gas guide pipe is provided with a flow dividing port, and the flow dividing port is communicated with the gas inlet pipe and the gas outlet pipe. The gas pump comprises a first connecting pipe fixedly connected with the flow dividing opening of the gas guide pipe and a second connecting pipe arranged at an outlet of the gas pump, the detection assembly comprises a hydrogen monitor, an oxygen monitor and a nitrogen electric valve fixedly connected with the gas guide pipe, and the hydrogen monitor and the oxygen monitor are arranged on the second connecting pipe in sequence; the warning assembly comprises an in-vitro oxyhydrogen monitor arranged on the outer surface of the gas container and a warning lamp electrically connected with the in-vitro oxyhydrogen monitor.

The invention provides a target design for preparing Ac-225 through irradiation of Ra-226 by an accelerator, and particularly provides an application of a metal niobium film in preparation of medical isotope actinide 225, the niobium metal film is selected as a covering material to cover radioactive radium deposited on a target, and therefore radioactive gas is prevented from polluting a target chamber and the environment. In addition, the annular groove is machined in the target piece base body, so that the upper surface of the target piece is kept flat after the niobium film is added, and installation of the target piece on an accelerator is facilitated.

The invention provides a ground alpha radioactive contamination efficient cleaning decontamination and waste liquid recovery device which comprises a cleaning disc shell, a cleaning disc, a waste liquid recovery device and a waste liquid recovery device, and the cleaning disc shell is internally provided with a cleaning cavity; the cleaning assembly is arranged in the cleaning cavity and used for cleaning the ground facing the cleaning cavity; on one hand, a gridding cleaning and decontamination operation mode is originally created, operation is carried out with a cleaning cavity coverage area as an independent grid, physical isolation from surrounding facilities and equipment is achieved, a cleaning assembly composed of atomized high-pressure water, compression type bristles and the like is originally created, efficient removal of various kinds of alpha radioactive pollutants on the ground is ensured, and the cleaning efficiency is improved; meanwhile, the generation amount of radioactive gas, liquid and solid waste is greatly reduced, and secondary pollution diffusion of radioactive waste water, radioactive dust (aerosol) and the like is reduced; and on the other hand, the remote operation mode of cleaning and decontamination operation is realized for the first time through visual remote control operation, and the physical and psychological health of operators is greatly protected.

The utility model discloses a nuclear power plant radioactive waste gas measuring cabinet, it includes cabinet body, side edge shock attenuation support subassembly, bottom shock attenuation support subassembly and gas measurement sampling subassembly. This nuclear power plant radioactive waste gas measuring cabinet is through the side edge shock attenuation support subassembly and bottom shock attenuation support subassembly of distribution setting, when the cabinet body inclines and swings, can slow down and absorb the impact force from the displacement of longitudinal, transverse and oblique direction, thereby guaranteeing the normal operation of cabinet body and internal components, to reach the effect of preventing inclination swing, maintaining normal operation of device. And through setting nitrogen gas purging pipeline, tee, sample gas inlet pipeline, sample gas inlet pipeline, sample gas outlet pipeline and gas sensor, can realize radioactive gas on -line real -time sampling function, avoid the irradiation risk that personnel and radioactive material contact bring, also realized nitrogen gas purging function, avoid the explosion risk that the higher concentration of flammable and explosive gas of airtight pipeline produces.

The invention discloses a radioactive gas collection and detection system for concealed rare metal ore exploration, and relates to the field of rare metal ore exploration, a gas collection bottle and a radioactive gas photoelectric detection device are both placed in a shading box, the gas collection bottle is made of a transparent material and used for containing scintillation aerogel, the gas collection bottle is provided with an exhaust port, and the exhaust port is communicated with the radioactive gas photoelectric detection device. An optical window of the radioactive gas photoelectric detection device is arranged opposite to the gas collection bottle; the radioactive gas collection device comprises a sampling mechanism and a gas extraction mechanism, the sampling mechanism comprises a sampling pipe and a filter, a plurality of gas inlet holes are formed in the side wall of the sampling pipe, the filter is fixed to the top of the sampling pipe and corresponds to the gas outlet in position, and one end of the gas extraction mechanism is connected with an outlet of the filter. And the other end of the air exhaust mechanism extends into the scintillation aerogel in the gas collection bottle. The radioactive gas collection and detection system solves the problem that a traditional exploration method is difficult to discover hidden rare metal ores in a thick-layer coverage area, and improves the detection efficiency and accuracy of the hidden rare metal ores.

The invention provides a medical radioactive isotope production device, and relates to the technical field of isotope preparation, the medical radioactive isotope production device comprises a support, the top of the support is provided with an air cylinder, the bottom is provided with a supporting table, the side wall is provided with a first through hole, one end of the air cylinder is provided with a communicated tank body, and the interior of the air cylinder is slidably connected with a cutting mechanism extending into the tank body; the air storage mechanism is located on the supporting table and communicates with the interior of the air cylinder; the sample injector is communicated with one end of the tank body, the free end of the sample injector is inserted with a fixing assembly for fixing an irradiation target, and the other end of the tank body is communicated with the dissolving bottle; and the supporting assembly is arranged on the side wall of the tank body and is used for adjusting the cutting length of the irradiation target. According to the irradiation target cutting device, a plurality of irradiation targets can be cut at the same time, the cutting process of the irradiation targets is closed, radioactive gas is prevented from overflowing, chipless cutting is achieved in an extrusion cutting mode, and the problems that chippings and residues fly upwards, and when the irradiation targets are cut, cut block wires are not broken and prone to deformation are directly avoided.

A detection probe (1), comprising an inorganic scintillator material (4), configured to generate photons, in an emission spectral band, under the effect of irradiation by alpha radiation; a photodetector (3), optically coupled to a coupling face (4r) of the scintillator material, and configured to generate a detection signal dependent on a number of photons generated in the scintillator material; an opaque envelope (5), disposed around the scintillator material, on either side of the coupling face; the probe being characterized in that it comprises an opaque, porous membrane (6), disposed facing the scintillator material, so as to allow migration, towards the scintillator material, through the membrane, of a radioactive gas, the membrane extending to a thickness greater than 100 µm.

The application relates to the technical field of radioisotope preparation, and particularly discloses a preparation device and method for radioisotope iodine-131; the preparation device comprises a dry distillation furnace, the dry distillation furnace comprises a heating furnace and a furnace pipe; the heating furnace comprises a heating furnace body and a furnace cover, a furnace cavity is formed in the heating furnace body, an opening for realizing the communication between the furnace cavity and an external space is arranged on the heating furnace body, and the furnace cover is detachably connected with the heating furnace body to realize the sealing of the opening; the furnace pipe is arranged in the furnace cavity, and the furnace pipe comprises a containing pipe body and a furnace pipe cover; the containing pipe body is used for placing a boat, a taking and placing opening for taking and placing the boat is arranged on the containing pipe body, and the furnace pipe cover is detachably connected with the containing pipe body to realize the sealing of the taking and placing opening. The application not only can meet the needs of mass production, has high production efficiency, and has simple structure and easy operation, can reduce the equipment size, and effectively reduces the risk of leakage of the present radioactive gas.

The present application discloses a radioactive gas detection device and a detection method. The radioactive gas detection device is used for detection of a radioactive gas containing a target nuclide, and comprises: an adsorption assembly, a sampling assembly, a monitoring assembly, a desorption assembly, a detection assembly, a first control valve set and a controller, wherein the sampling assembly, the adsorption assembly, and the monitoring assembly are sequentially communicated; the adsorption assembly is further communicated with the detection assembly; and the controller is configured to: when the monitoring assembly detects that the radioactive gas passing through the adsorption assembly contains the target nuclide, control the first control valve set to enable the adsorption assembly to be disconnected from the sampling assembly and the adsorption assembly to be disconnected from the monitoring assembly and enable the adsorption assembly to be communicated with the detection assembly, and control the detection assembly to perform a detection operation on the target nuclide released from the adsorption assembly to obtain the content of the target nuclide. The radioactive gas detection device can improve the detection accuracy of the target nuclide in the radioactive gas.

The utility model belongs to the technical field of radioactive gas-liquid sampling of nuclear power plants, and particularly relates to an anti-drop and anti-blocking radioactive gas-liquid sampling needle which comprises a needle seat, a connecting part, a needle tube and a sheath, the connecting part is arranged at the top end of the needle seat, the needle tube is connected with the connecting part, and the sheath wraps the needle tube and is used for protecting the needle tube; the top end of the needle tube is provided with an inclined needle tip cut, and the upper section is provided with a side hole. The needle base of the sampling needle is made of metal copper, the needle tube is made of 304 stainless steel, it is ensured that the needle base and an injector are fixed more firmly, the needle tube of the sampling needle is mechanically flared, and the needle tube and the needle base are transversely polished, so that the purpose of mechanically preventing the needle base and the needle tube from falling off is achieved, and it is ensured that the needle tube of the sampling needle and the needle base are not separated under the tensile force of 100 N or below. Meanwhile, the needle tube is provided with the side hole, so that the sampling pad cannot be blocked when the sampling pad is punctured, and the sampling efficiency is improved.

This invention relates to a method from 177 Lu / 176 Separation of Yb mixture 177 Lu's method belongs to the field of medical radioisotope separation and purification technology, and solves one of the problems of existing methods requiring the addition of additional DGA resin for acid adjustment, resulting in high cost and complex processes. The method of this invention uses three TK resin columns connected in series for separation. 177 Lu, and the first TK resin column and the second TK resin column are respectively suitable for different acidities. 177 Lu / 176 Yb mixture liquid 177 Lu separation: the first and second TK resin columns serve as the separation components, while the third TK resin column only serves as the final separation component. 177 The method of this invention does not require additional DGA resin for acid adjustment, making the entire process simpler, reducing costs, and preventing radioactive gas leakage; furthermore, the method of this invention improves… 177 Lu recovery rate.