97 results about "Hot cell" patented technology

The embodiment of the invention relates to the technical field of electrolytic production, recovery or refining of metal through a molten liquid electrolytic method, in particular to molten salt electrolytic refining equipment suitable for a hot chamber and a method for recovering uranium metal in spent fuel through molten salt electrolytic refining. The cathode and cathode transfer device is used for transferring the cathode into the electrolytic heating device or transferring the cathode away from the electrolytic heating device; the anode and anode transfer device is used for transferring the anode into the electrolytic heating device or transferring the anode away from the electrolytic heating device; the electrolytic product scraping and collecting device is used for carrying out scraping treatment on the cathode and collecting scraped objects; the electrolytic heating device moving assembly is used for enabling the electrolytic heating device to be moved to the hoisting station; and the cathode conductive device is connected with the cathode so as to electrify the cathode. According to the device provided by the embodiment of the invention, the electrolytic reaction can be continuously carried out, and the treatment requirement of the spent fuel is met.

The utility model relates to a high-efficiency air supply and exhaust device of an artificial nuclear medicine split charging hot chamber cabinet. The air supply and exhaust efficiency is improved. Comprising an air supply and exhaust top chamber and a shielding sub-packaging middle heat chamber shielding in-out lower heat chamber which is respectively provided with a sealing protection front door, a static pressure air supply box and an exhaust fan box which are arranged in the air supply and exhaust top chamber in parallel are respectively downwards communicated with an air supply port close to the sealing protection front door at the upper part in the shielding sub-packaging middle heat chamber shielding in-out lower heat chamber through a non-return air supply pipeline; and an exhaust outlet which is far away from the sealing protection front door and is provided with an activated carbon filter at the lower part in the shielding split charging middle hot chamber and the shielding in-out lower hot chamber is downwards communicated through a non-return exhaust pipeline. The device has the advantages that the quality of exhausted air is guaranteed, air in the hot chamber is prevented from overflowing when the door is opened, and nuclide pollution of the air in the hot chamber can be kept at a reasonable low level through adsorption of internal circulating airflow.

The utility model discloses a hot chamber shell hauling platform which penetrates through a plant opening of a plant and comprises an external base station arranged on the outer side of the plant opening and an internal rack arranged on the inner side of the plant opening, and two hauling rails arranged in parallel are fixedly laid at the top ends of the external base station and the internal rack. Hauling tankette groups are respectively and correspondingly arranged in the two hauling tracks, and hauling power devices are respectively and fixedly arranged at the end parts of the two hauling tracks on the built-in rack; during use, the hot chamber shell is hoisted to the hauling tankette group outside a workshop opening, the hauling power device is hooked on the hot chamber shell, the hauling power device is started, and the hot chamber shell can be slowly and stably moved into the workshop by means of moving cooperation of the hauling tankette group. And hoisting equipment in the plant is used for hoisting and mounting in place, so that the in-place of the hot chamber shell is not limited by the construction period of the plant any more, the consignment in-place efficiency is high, and the construction period of the hot chamber is shortened.

The invention relates to the technical field of radioactive metal waste treatment, and provides radioactive metal waste smelting equipment which comprises a crucible and a desalting device, and the crucible comprises a split crucible used for containing radioactive metal waste; the desalting device comprises a collecting cavity communicated with the split crucible, the collecting cavity is located above the split crucible, and the collecting cavity is used for collecting salt substances evaporated in the heating process of the radioactive metal waste; wherein the crucible is detachably connected with the desalting device. The crucible is detachably connected with the desalting device, after smelting is finished, the crucible can be separated from the desalting device, and a metal ingot can be conveniently taken out from the crucible, so that the crucible can be disassembled, assembled, loaded and unloaded through remote operation such as a mechanical arm in a hot chamber environment, and the desalting device can be used for collecting salt substances and removing salt substances. And the device can be used for sealing the split crucible and can be used for sealing the split crucible, the structure is simplified, desalting, melting, alloying, curing and other functions are integrated, and the technological process is simplified.

A sterilization system for a radiopharmaceutical product comprising a hot cell disposed within a clean room environment. A sterilization shaft extends between a first end and a second end and defines an interior. The first end of the shaft is disposed within the hot cell and the second end of the shaft is disposed externally to the clean room. An electron beam accelerator assembly is disposed within the interior of the sterilization shaft so that an emission end of the electron beam accelerator is adjacent the first end of the sterilization shaft.

The invention provides a preparation device of a heat source assembly. The heat source assembly includes a source core and a first enclosure including a first shell and a first cover. The preparation device comprises a rack, a measurement module, an assembly table, a welding module and a first transfer module. The measuring module is arranged on the rack and used for measuring the size of the source core. The assembling table is arranged on the rack, and a first shell is placed on the assembling table. The welding module is arranged on the rack and used for welding the assembled first shell and the first cover into a first cladding. And the first transfer module is movably arranged on the rack, and the first transfer module is used for transferring the measured source core into the first shell on the assembly table, assembling the first cover body and the first shell, and transferring the assembled first shell and the first cover body to the welding module. According to the preparation device, the automation degree of the preparation device can be improved, the production efficiency of the heat source assembly is improved, and the risk of large-scale radiation pollution on the surface of the hot chamber is reduced.

The utility model discloses small-sized automatic code spraying and labeling equipment for a nuclear-grade environment. The small-sized automatic code spraying and labeling equipment comprises a label paper mounting module, a label paper guide module, a label paper position detection sensor, a label stripping module, a labeling module, a traction module and a waste paper collecting module. The device is small and compact in appearance size and can be shrunk and enlarged according to the size of label paper, and the hot chamber installation requirement is met; a transmission structure of the equipment adopts a synchronous belt for transmission, and the synchronous belt adopts a polyurethane steel wire belt for transmission, so that the equipment has certain radiation resistance; the bottom paper of the label is made of PVC, and the bottom paper is transparent, so that the label is convenient to detect and has certain strength and flexibility; the labeling module adopts a V-shaped unilateral moving design and can be compatible with bottles of different specifications; the whole equipment is made of a material with relatively high radiation resistance, so that the equipment has certain radiation resistance; parts of parts of the equipment are made of aluminum materials for weight reduction design, and the equipment is lighter than ordinary equipment.

The present invention belongs to the technical field of spent fuel reprocessing, and specifically relates to a pulse backwash filtration device suitable for radioactive liquid, comprising a radioactive liquid feed section provided with a radioactive liquid storage tank (1) and a backwash water feed section provided with a backwash water storage tank (2), the radioactive liquid feed section and the backwash water feed section being respectively connected to a flocculation tank (3), the radioactive liquid feed section being able to filter the radioactive liquid sent from the flocculation tank (3) through the radioactive liquid storage tank (1) and then send it out, and the backwash water feed section being able to backwash the radioactive liquid storage tank (1) through the backwash water in the backwash water storage tank (2). The entire set of equipment of the present invention has no mechanical moving parts, is not easily damaged, has high reliability, is convenient to clean and maintain, and is suitable for installation in a radioactive hot cell.

This invention proposes a master-slave robotic arm control system and method for nuclear decommissioning operations. The system includes a data acquisition module that collects real-time posture data, corresponding communication delay data, and hot chamber environment data of the master and slave robotic arms; a data processing module that preprocesses the collected data, extracts standard feature information of the real-time posture of the master and slave robotic arms, standard feature information of the communication delay, and feature data of the hot chamber environment, and stores them in a motion information database; and a motion prediction module that constructs a trajectory prediction model for the slave robotic arm based on a neural network and outputs the predicted motion trajectory information of the slave robotic arm. In the nuclear decommissioning hot chamber environment, this system enhances the environmental adaptability of the system by collecting real-time posture data, communication delay data, and hot chamber environment data of the master and slave robotic arms, and combining them with a neural network to construct a high-precision trajectory prediction model for the slave robotic arm, thereby improving the accuracy and stability of the slave robotic arm in following the master arm's movements and ensuring precise synchronous operation of the master and slave robotic arms in complex environments.

A radiopharmaceutical dispensing device for controlling waste liquid splashing, relating to the technical field of radiopharmaceutical dispensing equipment, employs a shell, a protective support, and a retraction device. The shell has a notch on its side wall. The protective support is located at the notch and extends into the shell. The protective support includes two side plates and a base plate and a back plate disposed between the two side plates. The base plate, back plate, and two side plates form a side opening corresponding to the notch. The retraction device is disposed between the two side plates and includes a base on the base plate. A platform is slidably connected to the base, and the platform is equipped with an anti-tipping device. This invention allows the sliding platform to retract the waste liquid bottle into the protective support, preventing waste liquid from splashing into the protective support, avoiding contamination of the hot chamber, and eliminating safety risks. When the waste liquid bottle is full, it can be pulled out for easy replacement.

The utility model provides a power manipulator recovery mechanism and a nuclear decommissioning component dismantling device, and relates to the technical field of nuclear decommissioning treatment.The power manipulator recovery mechanism comprises a guide rail, a pushing piece, a pulling assembly and a connecting rope, the guide rail is horizontally arranged in a hot chamber, one end of the guide rail extends out of the hot chamber, and the guide rail is used for supporting a power manipulator to walk; the pushing piece is arranged on the guide rail in a sliding mode and located at the end, located in the hot chamber, of the guide rail, and the pushing piece is used for making contact with the power mechanical arm and pushing the power mechanical arm out of the hot chamber through the guide rail. According to the utility model, through the arrangement of the pulling assembly, when the power manipulator needs to be recycled, the connecting rope is wound through the pulling assembly, the pushing piece is driven to move on the guide rail, and the pushing piece pushes the power manipulator to move, so that the power manipulator is transferred from a hot chamber to an overhaul chamber; and the recovery operation of the power manipulator is completed.

A device converts a temperature difference into electric power by a Peltier element. The device includes at least one cold chamber closed by walls and at least one heat chamber open to the outside towards a heating-up area. The heat and cold chambers adjoin one another by one of these walls. This wall includes a Peltier element. A bell surrounds all cold chambers and heat chambers and separates the heating-up area from the external environment. At least three of the cold chambers each have the shape of a three-sided isosceles prism and touch each other at an axis of symmetry. The cold chambers are symmetrically distributed over 360°. At least three of the open heat chambers extend between the cold chambers. These cold and heat chambers form a first floor of the device. The walls have cooling fins on both sides of the walls.

The utility model relates to the technical field of tools, in particular to a quick-change tool for a sample clamp in a hot chamber, which comprises a machine body base, a machine body shell and a cutting component, wherein the machine body shell and the cutting component are arranged on the machine body base; a three-jaw chuck is detachably mounted at the end part of the rotating shaft through a quick release mechanism; the sliding block is controlled to be close to the clamp base through the bolt so that clamping force can be generated when a workpiece is clamped, the clamp base is a supporting structure of the clamp and can enable the clamp body to be kept stable when the clamp body is used, and when the bolt is tightened, the sliding block can extrude inwards to form the clamping force so that the workpiece can be clamped between the clamp base and the sliding block. The bolt achieves the purpose of clamping the workpieces by adjusting the distance between the clamp base and the sliding block, the clamp can clamp the workpieces of various shapes and sizes, high adaptability is achieved, the clamping force can be accurately controlled by adjusting the bolt, and different machining requirements are met.

The invention belongs to the technical field of radioactive hot cells, particularly relates to a radioactive hot cell of an intelligent control system and a working method of the radioactive hot cell, and aims to solve the problem that an existing radioactive hot cell lacks cleaning measures for medicine residues scattered on a tray. The inner wall of the notch is fixedly connected with an inner container, the inner wall of the bottom of the inner container is fixedly connected with an inner container tray, and the inner wall of the notch is connected with an isolation door through a hinge. According to the radioactive hot cell of the intelligent control system and the working method of the radioactive hot cell, after the radioactive drugs are prepared, drug residues scattered on the surface of the inner container tray in the hot cell body in a closed state can be cleaned in time; therefore, the influence of radioactive residues in the hot chamber body on subsequent medicine preparation is avoided, the harm of the residues to equipment or workers is reduced, the purity of the prepared medicine is improved, and the safety is improved.

The application provides a sample storage conveying system, which comprises a fixed frame, a heat accumulator fixedly installed on one side of the heat accumulator, mounting holes formed in the two sides of the fixed frame, an installation door hingedly connected to the inner wall surface of the mounting hole, and a semiconductor sample arranged in the fixed frame; and a temperature control assembly arranged in the fixed frame and used for controlling the temperature of the semiconductor sample. The fixed frame is composed of a heating chamber and a central isolation chamber and a cooling chamber, so that the heat carried by the conveying system between the heating chamber and the cooling chamber is reduced when the semiconductor sample is conveyed, thereby improving the practicability of the conveying system. The fan can be installed through the fixed hole, so that the conveying system can be circulated and cooled by the fan, air is blown from the lower structure, and air circulation is realized through a separate heat exchanger.

The present invention designs and develops a synthesis hot chamber system and synthesis method for the production of radioactive drugs. The synthesis hot chamber system includes a shielding box, an exhaust device, a fresh air device, a laminar flow device, a drug loading device, a radioactive drawer device, an activity well device, and a non-drawer device. The synthesis method is completed in the synthesis hot chamber system. The present invention adopts a Class A laminar flow design to ensure a clean environment for the production of radioactive drugs. In order to minimize the risk of personnel contact with radioactive materials, different transfer channels are designed in this patent for the transfer of radioactive and non-radioactive materials, and they are managed in different areas. Non-radioactive materials are transferred at the front of the shielding box to facilitate personnel operation, and radioactive materials are transferred at the back of the shielding box to reduce the risk of co-operators being irradiated.

The invention discloses an isotope production method of a pneumatic conveying type coating target material ball. The method comprises the following steps: putting a coating target ball into an absorption ball pore channel of a reflecting layer of a pebble-bed high-temperature gas cooled reactor for irradiation; after irradiation is completed, the coating target balls are conveyed back to the ball storage tank through a pneumatic conveying system; transferring the coated target balls after irradiation in the ball storage tank to a post-treatment hot chamber; and in a post-treatment hot chamber, dissolving and separating the coating of the coating target ball containing the target isotope to obtain a dissolving solution, and purifying the dissolving solution to obtain an isotope solution. Based on an existing secondary shut-down system engineering design scheme and a remote control technology, full-sealing and remote automatic operation of a target ball are achieved for isotope production, the risk that personnel make contact with radioactivity is reduced to the maximum extent, and normal power generation operation of the pebble-bed high-temperature gas cooled reactor is not affected.

The utility model relates to container transfer technology field, concretely is a kind of multifunctional container transfer device, including base, still include: travelling mechanism, the travelling mechanism is set on base;Lifting mechanism, the lifting mechanism is set on the top of base;Uncovering mechanism, the uncovering mechanism is set on base, and the sealing cover compatible with the open upper end of container is connected in the execution end of uncovering mechanism;The utility model is by the cooperation of travelling mechanism, lifting mechanism, uncovering mechanism and sealing cover, constitute the multifunctional transfer device with moving, sealing, uncovering, lifting, not only can independently move in hot chamber, still can carry out plugging to the open upper end of container, effectively avoid the radioactive material splashing caused by vibration, jolt, greatly reduce hot chamber environment and equipment pollution risk;When reaching specified position, first remove sealing cover by uncovering mechanism, then utilize lifting mechanism to drive container to move upwards to complete height adjustment, save waiting link, greatly shorten operation cycle.

The embodiment of the invention provides a production line and method for radioactive liquid medicine, the production line comprises a receiving hot chamber, a dilution hot chamber and a split charging hot chamber, and an uncovering mechanism for opening a raw material bottle and a first manipulator for transferring the raw material bottle to a first transfer channel are arranged in the receiving hot chamber; a second manipulator and a dilution assembly are arranged in the dilution hot chamber, and the second manipulator transfers the raw material bottles into the dilution hot chamber; the diluting assembly is used for diluting raw materials in the raw material bottle to obtain a diluent; a split charging station used for split charging of diluent is arranged in the split charging hot chamber, and the split charging station is communicated with the dilution assembly through a capillary pipeline. Corresponding devices are arranged in a plurality of hot chambers with different functions, introduction, dilution, sampling, split charging and discharging of radiopharmaceuticals are achieved, the whole production process is carried out under protection of the high-protection hot chambers, dependence on production personnel is reduced, and therefore consistency of production efficiency and product quality is guaranteed, and personnel burden and risks are reduced.

The utility model belongs to the technical field of mechanical design, and particularly relates to a quick replacement tool for a tail end hot chamber line illumination lamp. The device comprises a handle, a steel wire winch assembly, a hook and a telescopic rod, the handle is connected with the steel wire winch assembly, the steel wire winch assembly is connected with the telescopic rod, the hook is fixedly installed at the front end of the telescopic rod, and a steel wire cable is arranged between the hook and the steel wire winch assembly. According to the invention, the maintenance personnel can complete the replacement and maintenance work of the fixed lamp in the hot chamber without entering the upper box body of the hot chamber, so that the danger coefficient of the maintenance work is greatly reduced, the safety of the maintenance personnel is guaranteed, and the maintenance work efficiency is improved.

The invention provides a radioactive sample storage device which comprises a box body assembly and a box cover assembly, the box body assembly comprises a box body part and a box cover part, a sample storage groove, an air inlet and an air outlet are formed in the box body part, the box cover part is hinged to the box body part and used for opening or covering a groove opening of the sample storage groove, and under the condition that the box cover part covers the groove opening of the sample storage groove, the box cover part is hinged to the box body part; the box body part and the box cover part are in sealing fit; the gas supply assembly is connected to the box body assembly and is used for conveying inert gas into the sample storage tank through the gas inlet; the electromagnetic valve is arranged on the box body part and is used for opening or closing the exhaust port; the control assembly is connected to the electromagnetic valve and used for controlling operation of the electromagnetic valve; wherein the box assembly is used for being arranged in a hot chamber, and the air supply assembly and the control assembly are used for being arranged outside the hot chamber.

The present application belongs to the technical field of radioactive hot cell equipment and instruments, and particularly relates to a multifunctional sample rack suitable for a radioactive hot cell, which comprises a rotatable tray system capable of placing sample bottles, rabbit bottles and waste liquid bottles, a sampling needle (24) for sampling operation on the sample bottles, the rabbit bottles and the waste liquid bottles, and a needle changing barrel (17) for replacing the sampling needle (24), and the tray system and the needle changing barrel (17) can be operated by a manipulator in the radioactive hot cell. The sample rack provided by the present application can accurately switch and position different bottle positions, the sampling needle (24) is liftable and replaceable, can be connected with other flow path equipment for subsequent sampling analysis, the whole bracket is made of full stainless steel material, has a simple structure, is firm and stable, is high in functionality, is simple to operate, and is more suitable for being operated by a manipulator in a hot cell environment with strong acid and strong radiation.

The embodiment of the invention relates to the technical field of radioactive substance sorting, in particular to a method for sorting samples in a hot cell, the samples have high radioactivity, and the method comprises the steps that feature images of simulation samples without radioactivity are obtained, the feature image of the simulation sample without radioactivity is similar to the feature image of the sample with high radioactivity; dispersing the mixed samples; obtaining an image of the dispersed sample; according to the obtained feature image, identifying an image with a predetermined feature from the obtained image of the sample; a sample corresponding to the image of the predetermined feature is picked up and placed at a predetermined position. By means of the method, multiple kinds of high-radioactivity samples can be accurately recognized and sorted in the high-radioactivity environment in the hot chamber, compared with an existing sorting mode, the accuracy and efficiency are higher, the radiation risk existing in manual operation can be avoided, and the sorting efficiency is improved. And the sorting safety is effectively improved.

The utility model relates to a cantilever belt cover assembly for sealing and isolating the inside and the outside of a hot chamber, which at least comprises a cantilever belt cover (101), a rotating unit (102) and a lifting unit (103), the cantilever belt cover (101) is arranged on a hot chamber transfer channel, and a sealing ring (201), a barrel guide pin (202) and a guide flange (208) are arranged on the cantilever belt cover (101); a pull rod assembly (209) is installed in the supporting arm assembly (206), a balance weight (210) is installed on the tail portion of the supporting arm assembly (206), one end of the pull rod assembly (209) is connected with the six-claw shaft (207), and the other end of the pull rod assembly (209) is connected with the rotating unit (102) through a small rotating shaft (301). The radioactive substances are butted and transferred between the shielding operation room and the raw material cutting line operation room.

The utility model relates to dry equipment technical field, specifically disclose a closed cycle type drying equipment, including drying chamber, the upper portion of drying chamber is connected with condensation chamber through conical gas collecting hood, the right side of condensation chamber is connected with heat storage room through pipeline, the lower portion of heat storage room is provided with electric auxiliary heating chamber, the right side of drying chamber is provided with the circulating fan that exports and drying chamber intercommunication, through the wet heat steam in drying chamber through conical gas collecting hood enters the condensation chamber, realizes the first grade sensible heat recovery and dehumidification through condensation chamber, realizes two secondary latent heat storage and release through heat storage room, realizes three grade heat energy compensation through electric auxiliary heating chamber, finally by high temperature resistant circulating fan after heating drying air is sent back drying chamber completes circulation, and then through drying chamber, dehumidification, condensation dehumidification, waste heat recovery, heat energy compensation, drying chamber reheats, form "heat energy cascade utilization and humidity step by step remove" closed loop system, realize energy maximization utilization.

The invention relates to the field of building external window detection, in particular to a detection device for detecting the solar heat gain coefficient of a building external window, which comprises an environment control chamber, a hot chamber and a cold chamber which are arranged in parallel are arranged in the environment control chamber, and a building external window test piece is detachably fixed between the hot chamber and the cold chamber. A total radiation meter A is arranged at the position, close to the building outer window test piece, of the hot chamber, a total radiation meter B is arranged at the position, close to the building outer window test piece, of the cold chamber, an artificial light source, a hot chamber air conditioner and a temperature sensor A are arranged in the hot chamber, and a temperature sensor and a cold chamber air conditioner are arranged in the cold chamber. A data processing system and an environment control room air conditioner are arranged in the environment control room, and data measured by the total radiation meter A and the total radiation meter B are transmitted to the data processing system for data processing. The method can carry out targeted solar heat gain coefficient detection on building external windows, light-transmitting curtain walls and the like, guarantees the accuracy and stability of data, and does not affect the detection of shading coefficients at the same time.

The invention relates to the technical field of isotope production hot chambers, in particular to a target station hot chamber system for isotope production and an operation process of the target station hot chamber system. The target station hot chamber system comprises an operation hot chamber used for executing a target feeding process, a target discharging process and a discharging process; the irradiation chamber is used for executing an irradiation process; the target vehicle channel is used for communicating the irradiation chamber with the operation hot chamber; wherein the target vehicle channel comprises a track and a target vehicle, the track extends from the operation hot chamber to the irradiation chamber, and the target vehicle conveys a target container along the track. According to the invention, through functional partition design and system arrangement of the hot chamber, the target vehicle is used for operating the target device between the irradiation chamber and the operation hot chamber, and meanwhile, the automatic system in the operation hot chamber is used for carrying out target loading and unloading operation, so that batch cross-hot-chamber transfer of the target sheets can be realized; and the process target loading and unloading requirements and the high-efficiency circulation of materials in the hot chamber can be met, and the requirements of isotope batch production are met.

The application belongs to the technical field of radionuclide measurement, and particularly relates to a constant-temperature high-precision radioactivity micro-heat device capable of rapid measurement, which comprises a high-precision constant-temperature unit and a rapid calorimetry unit. The high-precision constant-temperature unit comprises a shell, a constant-temperature water bath layer, an adiabatic layer and a temperature control layer, and is used for keeping a constant-temperature environment and reducing the influence of external environmental temperature fluctuation. The rapid calorimetry unit is located in the high-precision constant-temperature unit and comprises a calorimetry chamber and a calorimetry cup group and a thermocouple group arranged in the calorimetry chamber. The application adopts a double-cup type isothermal heat flow design to eliminate the fluctuation of parasitic potential, the refrigeration device can controllably adjust the cold end temperature, the adiabatic layer and the temperature control layer are arranged alternately to effectively improve the temperature control precision, the unique heat conduction insulation design between the calorimetry cup groups and the high-thermal-conductivity liquid strategy greatly reduce the heat balance time. The application has the characteristics of high-precision constant-temperature and rapid calorimetry, and is very suitable for precise measurement of medical isotope activity.

The invention belongs to the technical field of nuclear power, and particularly relates to a fuel assembly grillwork defect underwater sampling device and method based on electric spark cutting. According to the technical scheme, the positioning system, the electric spark cutting module, the suction module and the collecting container are used for forming underwater sampling of the defects of the fuel assembly positioning grillwork, separation and collection of the defect grillwork and collection of cuttings in the cutting process are effectively achieved, and on the premise that the exposure dose of personnel is reduced as much as possible and the original defect morphology is not affected, the sampling efficiency is improved. The grillage defect underwater sampling can be safely and effectively completed, and preconditions are provided for grillage hot chamber inspection and analysis.

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.