30 results about "Lead shielding" patented technology

The invention relates to the technical field of radiation measurement, in particular to a high-radioactivity volatile liquid on-line measuring device and method.The measuring device comprises an overflow pool, a lead shielding body and a detector, a detection channel is formed in the axis area of the lead shielding body in the vertical direction in a penetrating mode, and an orifice in the bottom of the detection channel is sealed through a window plate; a detector is coaxially arranged in the detection channel, and a light-sensitive surface of the detector directly faces the window plate; the lower end of the lead shielding body is embedded and fixed at the top opening of the overflow pool, so that the top of the overflow pool and the bottom of the lead shielding body define an annular airflow channel. The detector is arranged in the detection channel in the lead shielding body, and the dynamic air curtain isolation layer is constructed between the bottom of the lead shielding body and the liquid level of the overflow pool, so that the upward diffusion of volatile radioactive substances is physically blocked while gamma ray penetration measurement is realized, the detector and a light-sensitive surface are fundamentally prevented from being polluted, the maintenance frequency is remarkably reduced, and the measurement accuracy is improved. And the long-term measurement precision and the online continuous operation capability of the system are ensured.

The invention relates to a radioisotope tracer strain clamp cavity grease injection amount detection system and method, and provides a method for preparing electric grease containing a low-energy gamma-ray isotope tracer agent, injecting the electric grease into a strain clamp cavity, sealing, scanning in a lead shielding detection cabin by using a high-resolution sodium iodine detector, and detecting the grease injection amount of the strain clamp cavity. And the grease thickness of each area is calculated according to the Lambert-Beer law, and the total grease injection amount is obtained through accumulation. According to the method, non-contact measurement is adopted, the detection sensitivity reaches 0.01 ml, the method is suitable for detecting small-size cavities and is particularly suitable for complex shapes such as deep holes and narrow slits, and the problem of low resolution in the prior art is solved; in addition, the radiation dose in the detection process is lower than 0.1 mu Sv, safety is ensured, the quality control risk is reduced, and the maintenance reliability of the power system is improved.

The utility model provides a chip bonding wire three-dimensional measurement system based on an inner cavity reflection camera system. The chip bonding wire three-dimensional measurement system comprises a microscope lens, a reflector cavity, a relay lens, an industrial camera and an illumination module. Two parallel plane mirrors are arranged in the reflector cavity and used for separating a first real image imaged by the microscope lens into three independent light paths to form a three-view virtual image, and the three-view virtual image is transmitted to a photosensitive chip of the industrial camera through the relay lens at the amplification factor of 1: 1, so that three-view images are acquired through single exposure. The system is matched with a computer to carry out optical flow calculation, point cloud fusion and three-dimensional reconstruction, a three-dimensional grid model with texture colors is generated, and high-precision and non-contact measurement of the multi-layer lead shielding structure is achieved. The system is compact in structure, easy and convenient to install and adjust and suitable for on-line detection of bonding and packaging of vehicle-gauge-level chips.

This invention provides an online monitoring system and method for krypton-85 based on a scintillation fiber bundle, specifically relating to the field of nuclear radiation monitoring. The online monitoring system includes: a gas pretreatment unit, a detection unit, an electronics and data acquisition unit, and a control unit. The detection unit is connected to the gas output terminal of the gas pretreatment unit. The detection unit includes a detection chamber, a scintillation fiber bundle, a first photomultiplier tube, a second photomultiplier tube, and a lead shield. The scintillation fiber bundle is disposed within the detection chamber, and the first and second photomultiplier tubes are respectively located at both ends of the detection chamber, with their photosensitive surfaces optically coupled to both ends of the scintillation fiber bundle. The lead shield covers the outside of the detection chamber. The electronics and data acquisition unit receives the output signal from the detection unit, and the control unit controls the automatic operation of the entire system, parameter setting, and data acquisition and processing. This invention solves the problems of poor timeliness and insufficient representativeness in traditional offline monitoring methods.

The invention relates to a radiation environment monitoring camera, in particular to a gradient shielding camera based on a radiation direction gradient and a manufacturing method of the gradient shielding camera, and solves the problems that most of wall thicknesses are wasted, the light path adaptability is poor, and cameras of multiple specifications cannot be compatible in an existing shielding structure adopting a uniform wall thickness design. The device comprises a shell, a reflecting mirror, a lead shielding body and a camera movement, the position of a movement mounting cavity is positioned by calculating the thickness of a lead shielding layer, and the camera movement does not need to directly face a radiation field through reflection of the reflecting mirror, so that the influence of radiation on the camera movement is further weakened; due to the fact that the non-uniform wall thickness design is adopted in the lead shielding body, invalid loads are reduced, unnecessary material use is greatly reduced, the weight of the whole device is reduced, and meanwhile the manufacturing cost is reduced. The non-uniform wall thickness design is adopted, so that the position and the size of the window can be flexibly adjusted while necessary protection is ensured, and the device is suitable for camera movements of different sizes and types.

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 present application belongs to the technical field of radioactive source transport equipment, and discloses a radioactive source transport container, which comprises a shielding container body, a fireproof cover assembly, a carrying base and a drawer assembly. A lead shielding layer is cast in the shielding container body, and two drawer channels are arranged for the drawer assembly to slide through. The shielding container body is connected with an end cover assembly for sealing the drawer channel ports and axially locking the drawer assembly. The fireproof cover assembly is arranged outside the shielding container body and comprises a fireproof cover outer cylinder and a fireproof cover inner cylinder. Heat insulation material is arranged between the inner and outer cylinders, and a damping structure is arranged at the top. The present application doubles the loading capacity of radioactive sources through the double-drawer channels, improves the transport efficiency, and enhances the ability of the container to resist drop and fire-burning composite accidents through double-layer heat insulation and integrated damping structure. The horizontal pull-out type loading and unloading method is safe and convenient to operate. The container of the present application is suitable for B(U) type package transport of special form radioactive sources such as cobalt-60 and cesium-137.

The utility model provides a high-level waste shielding container which comprises a barrel body and a barrel cover, an inner cavity of the barrel body is hollow, and the barrel cover is installed on the top of the barrel body. Three steps are sequentially arranged on the inner wall of the can body from top to bottom, and reverse steps matched with the steps on the can body are arranged on the can cover. Each of the barrel body and the barrel cover comprises a lead shielding layer for shielding radiation emitted by radioactive substances and a coating layer coated outside the lead shielding layer, and annular areas which are not filled with the lead shielding layer are respectively arranged on the upper part and the lower part of the barrel body close to the outer edge. According to the high-level radioactive waste shielding container, radioactive waste is placed in the inner cavity of the barrel body, the barrel cover is matched with the step of the barrel body through the groove in the barrel cover, the sealing effect is guaranteed, and meanwhile necessary radiation protection is provided through the lead shielding layer. And the annular area which is not filled with the lead shielding layer between the inner wall and the outer wall of the barrel body can reduce the weight of the container while keeping the structural strength.

The embodiment of the invention discloses an online measuring device, method and system for uranium concentration of uranium mine leaching liquid. In the device, a first assembly or a second assembly can be adopted when the uranium mine leaching liquid is conveyed from a first pipeline to a measuring pool containing a lead shielding part. When uranium mine leaching liquid is conveyed to the measuring pool containing the lead shielding part through the first assembly, first energy spectrum data measured by the gamma-ray energy spectrum detection part does not contain U-235 gamma ray characteristic peaks. Second energy spectrum data measured by the gamma-ray energy spectrum detection part contains U-235 gamma ray characteristic peaks when uranium mine leaching liquid is conveyed to the measurement pool containing the lead shielding part through the first assembly, so that the uranium concentration can be determined according to the first energy spectrum data and the second energy spectrum data. In this way, no extra reagent needs to be added in the uranium concentration measuring process, and the uranium concentration measuring process is not affected by the content of radioactive daughters.

The utility model relates to a lead shielding automatic lifting door device, belongs to the technical field of industrial CT detection, and solves the problems that in the prior art, the transverse space of an entrance of an industrial CT is limited, and a shielding door is inconvenient to open and close. The shielding door comprises a shielding door body, a driving device, a grating and a controller, the shielding door body and the driving device are both installed at an entrance of the industrial CT detection equipment, and the shielding door body can slide up and down; the driving device is connected with the shielding door and used for driving the shielding door to ascend and descend to achieve door opening and closing. The grating is arranged at the top of the shielding door and connected with the controller, and the grating is used for detecting whether a workpiece to be detected passes through the shielding door or not and feeding back a signal to the controller; and the controller is connected with the driving device and used for controlling the driving device to act so as to automatically control the lifting of the shielding door. According to the utility model, the transverse occupied space is reduced, and the shielding door is convenient to open and close.

The invention discloses a shielding storage device and method for a radioactive sample inert protection environment, the shielding storage device comprises a shielding device box body, the shielding device box body comprises a box body and a box door arranged at one side of the box body, and the box door is used for realizing opening and closing of the shielding device box body; a square sample storage bin is arranged in the shielding device box body and comprises a bin body and a bin door; radioactive samples are stored in the sample storage square bins; lead shielding bodies are arranged on a box body and a box door of the shielding device box body and are used for shielding radioactive rays of the radioactive sample. The device has a good shielding effect, can improve the oxidation resistance and radiation protection effect of a radioactive sample, and realizes whole-process sealed transfer, radioactive shielding, air tightness maintenance and aerosol leakage prevention of the radioactive sample, so that the environment of experimenters is protected, cross contamination of the experimental environment is prevented, and the experimental efficiency is improved. And technical support and safety guarantee are provided for development of design, research and development tests of nuclear fuel elements and structural materials.

The utility model belongs to radiation monitoring technical field discloses an online radiation monitoring device for carrying out online monitoring to gamma radionuclide activity concentration in the pipeline to be measured, including support frame, detection component and lead shielding component, support frame includes support frame body and mounting panel, support frame body includes two support plates that are arranged in parallel along the length direction of the pipeline to be measured and is spaced, and two connecting plates that are arranged in parallel and are spaced between the two support plates, the support groove is set up on two support plates, the pipeline to be measured can be supported in the support groove, the both ends of mounting panel are connected with two connecting plates respectively, and detection component is detachably connected on mounting panel, lead shielding component is detachably connected with support frame, lead shielding component is formed around the circumference of the pipeline to be measured and is provided with shielding cavity, and the pipeline to be measured can penetrate the shielding cavity. The online radiation monitoring device has strong anti-interference ability, low background counting rate and high detection efficiency for radiation.

The embodiment of the utility model discloses an ultra-low background liquid scintillation counter, which comprises three main photomultipliers which are radially arranged in the same horizontal plane at equal intervals, and a counting chamber for measurement is formed among the end parts of the three main photomultipliers; the number of the auxiliary photomultipliers is three, each auxiliary photomultiplier is arranged between two adjacent main photomultipliers at equal intervals, and the auxiliary photomultipliers and the main photomultipliers are arranged in a one-to-one correspondence mode and located in the same horizontal plane. Three through hole structures which are arranged at equal intervals are arranged on the side wall of the plastic scintillator at intervals and are used for adaptively arranging the three main photomultipliers, and three concave structures which are arranged at equal intervals are arranged on the side wall of the plastic scintillator at intervals and are used for adaptively arranging the end parts of the auxiliary photomultipliers; a lead shield; the photomultiplier has a shape and a structure matched with the main photomultiplier, the auxiliary photomultiplier and the plastic scintillator; a copper lining layer is adaptively arranged between the lead shielding body and the plastic scintillator; and the outer shell is adaptively arranged outside the lead shielding body.

The invention discloses a radiopharmaceutical transportation protection method and device, and relates to the field of transportation protection, and the protection device comprises a container layer, a main shielding layer, a secondary shielding layer and a sealing cover assembly which are sequentially arranged from inside to outside; the container layer comprises a primary container and an inner container support for supporting the primary container, and the primary container is arranged on the inner container support; the main shielding layer comprises a first shielding case and a second shielding case; the secondary shielding layer comprises a damping layer and an external shell; the sealing cover assembly comprises a main sealing cover matched with the outer shell and a dynamic sealing structure used for enhancing the sealing performance when vibration occurs. The lead-tungsten alloy and the boron-containing polyethylene are compounded to form the main shielding body, and compared with the limitation that traditional single lead shielding can only attenuate part of rays in a targeted mode, the protection device can effectively reduce the dose equivalent rate of the surrounding environment, and the radiation safety in the transportation process is ensured.

This invention discloses a pulsed X-ray time-resolved energy dispersive spectroscopy (EDS) measurement system and its operating method, comprising a metal casing; an adjustable DC voltage source and a high-speed oscilloscope connected to the metal casing; a filter slot provided inside the metal casing, with multiple metal filters installed inside the filter slot; a corresponding Si-PIN detector located behind each metal filter, the central axis of the metal filter being collinear and coincident with the central axis of the corresponding Si-PIN detector; multiple SMA interfaces provided on the rear surface of the metal casing, the analog signal output terminal of each Si-PIN detector being connected to the internal signal input terminal of the corresponding SMA interface; the power output terminal of the adjustable DC voltage source being connected to the power input terminals of all Si-PIN detectors; the external signal output terminal of each SMA interface being connected to the independent signal input terminal of the high-speed oscilloscope; and a lead shielding layer covering the outer or inner side of the metal casing.

The application discloses a radioactive inert gas detection device, which comprises a gas chamber, a plastic scintillator detection assembly for detecting the total beta activity concentration of radioactive inert gas, and a lanthanum bromide crystal detection assembly for detecting the activity concentration of each radionuclide category in the radioactive inert gas. The plastic scintillator detection assembly comprises first, second and third plastic scintillator detectors and a first signal processing circuit board, and the bottom of the third plastic scintillator detector is provided with a lead shielding plate. The lanthanum bromide crystal detection assembly comprises first and second lanthanum bromide crystal detectors and a second signal processing circuit board, and the first lanthanum bromide crystal detector is provided with a lead shielding plate on the top thereof. The device can overcome environmental background interference, improve detection efficiency, and accurately measure the total beta activity concentration of radioactive inert gas in the exhaust pipeline and the activity concentration of each radionuclide category under the condition that the activity concentration of the radioactive inert gas is low.

The invention discloses a low-level liquid activity monitoring device and method with an adjustable measurement range, and belongs to the field of nuclear radiation detection.The low-level liquid activity monitoring device comprises a sampling water inlet pipe, a monitoring assembly and a sampling water outlet pipe, the monitoring assembly comprises a lead shielding part, the lead shielding part is provided with a shielding cavity, and a scintillator detector and a sampler are arranged in the shielding cavity; the sampler is a U-shaped piece, the U-shaped piece comprises a U-shaped sampling cavity and a U-shaped groove, the sampling water inlet pipe and the sampling water outlet pipe are both communicated with the U-shaped sampling cavity, and the detection end of the scintillator detector extends into the U-shaped groove; and a shielding material layer is arranged between the detection end of the scintillator detector and the inner wall of the U-shaped groove, so that the detection performance of the monitoring equipment can be improved.

1. Name of the designed product: Lead shield door. 2. Use of the designed product: Protection against ionizing radiation. 3. Design points of the designed product: In shape. 4. Picture or photograph best indicating the design points: Fig. 1.

The invention relates to the field of high-voltage safety operation tools, and discloses a live-line isolation switch and drainage wire shielding cover installation tool which comprises a first installation cylinder, a supporting rod and a second installation cylinder, the first installation cylinder is used for containing an insulator shielding part of a shielding cover, one end of the top of the first installation cylinder is of an opening structure, and the other end of the top of the first installation cylinder is of an opening structure. The top opening part is provided with a pair of elastic buckles which are opened towards the outer side direction, and the elastic buckles are driven by external force to deflect inwards and can be buckled at the opening part of the insulator shielding cover; an elastic supporting part is arranged at the bottom of the first installation cylinder, and the trend that the insulator shielding cover moves towards one end of the opening structure can be provided through the elastic supporting part so that the opening portion of the insulator shielding cover can be kept buckled with the elastic buckle. According to the installation tool, the shielding cover can be installed under the electrified condition, and operation is easy and convenient.

This invention pertains to shielding devices, specifically a shielding system for nuclear environmental sampling. The shielding system comprises a lower section of lead tile assembly, a middle section of lead tile assembly, and an upper section of lead tile assembly connected sequentially. The lower section of lead tile assembly is located at the bottom, the upper section of lead tile assembly is located at the top, and the middle section of lead tile assembly is located in between. These three sections form a barrel-like structure. Compared to existing technologies, this invention offers the following advantages: it minimizes the gaps between tile layers, ensuring the overall dimensions of the assembled shielding cylinder; it guarantees the quality of each lead tile; it ensures the overall shielding performance of the lead shielding cylinder after installation; and it minimizes the number of lead tiles while considering the convenience of single-person operation in space-constrained conditions.

The invention discloses a multi-channel low-background alpha and beta measuring instrument, which comprises a plurality of detector modules and a control unit module for processing output signals of the detector modules, and is characterized in that each detector module comprises a lead shielding body, a main detection unit and an anti-coincidence detection unit, and the main detection unit and the anti-coincidence detection unit are arranged in the lead shielding body in a layered manner; the main detection unit comprises two main detectors and two first PCBs (Printed Circuit Board) which are matched with the two main detectors respectively and are integrated with first coupling circuits; the anti-coincidence detection unit comprises an anti-coincidence detector and a second PCB which is matched with the anti-coincidence detector and is integrated with a second coupling circuit, a plurality of wave-shifting optical fibers are pre-buried in the anti-coincidence detector, and second SiPM sheets are arranged at the two ends of each wave-shifting optical fiber. The optical fiber is directly embedded into the crystal, light loss is reduced, detection efficiency is improved, optical signals are transmitted through the optical fiber, electromagnetic interference is reduced, the device is suitable for complex environments, and higher conversion efficiency can be achieved by using less SiPM.

The invention discloses an energy spectrum measurement system and method for a non-point X-ray source, and solves the problems that when a transmission bent crystal spectrometer is applied to pulse hard X-ray energy spectrum diagnosis of an annular ray source, the energy spectrum measurement is interfered by the non-point source, and the energy spectrum diagnosis range is difficult to meet requirements. The front end face of the lead shielding body is provided with an incidence window, the trapezoid collimation body is arranged at the front end of the lead shielding body, and the small hole check block, the cylindrical surface bent crystal, the slit, the IP screen, the shielding baffle and the collimation laser are sequentially arranged in the lead shielding body from front to back. Compared with the prior art, the non-point source pulse X-ray energy spectrum can be diagnosed, the energy spectrum diagnosis requirement of a ray source with the peak voltage ranging from 300 kV to 400 kV is met, and 20 keV to 150 keV energy spectrum diagnosis can be achieved by adopting the structural design provided by the invention.

The utility model relates to a shielding device, in particular to a radiopharmaceutical transmission lead shielding device. A radiopharmaceutical transmission lead shielding device comprises a door-shaped frame and is characterized in that the front side and the rear side of the door-shaped frame are connected with side plates through screws, a storage groove is formed between the door-shaped frame and the two side plates, and lead powder is filled in the storage groove. And a top cover is inserted into the upper side of the storage groove. Square holes corresponding to the rectangular cylinder are formed in the side plates, and the rectangular cylinder penetrates through the two square holes. And stop pins are inserted into the two ends of the rectangular cylinder. And glass is adhered to the middle part of the inner side of the rectangular cylinder. A right-angle plate is fixed to the lower end of each side plate. A connecting piece is fixed to the lower side of one end of the rectangular cylinder. And a groove rod is fixed on the connecting piece. And a strip-shaped groove is formed in the groove rod. And the lead plate can be inserted into the strip-shaped groove. And lead powder can be conveniently filled to shield radiopharmaceuticals.

The utility model discloses a low-background alpha-gamma energy spectrum composite measuring device, and belongs to the technical field of nuclear radiation measuring devices. The low-background alpha-gamma energy spectrum composite measurement device comprises a lead shielding layer, a lead shielding cover, a compression bar type hinge, a base, a lifting motor, a detector fixing frame, an alpha detector, a gamma detector and a pull-out sample table, the detector fixing frame can ascend and descend in the lead shielding layer, and an alpha detector, a drawing type sample table and a gamma detector are installed on the detector fixing frame; the liftable detector fixing frame can be used for realizing convenient sample replacement, and meanwhile, the relative positions of the alpha detector, the gamma detector and the sample can be kept fixed, so that the detection efficiency is kept unchanged. The low-background alpha-gamma energy spectrum composite measurement device is reasonable in design and convenient to use, alpha-ray and gamma-ray energy spectrum composite measurement of the sample can be realized, the radionuclide measurement range is expanded, alpha and gamma radionuclides in the sample can be qualitatively identified, and the radioactive activity of the sample can be quantitatively calculated.

According to the Am-Li neutron source preparation method based on molecular assembly, metal-organic framework (MOFs) molecular assembly serves as a core, Am < 3 + > and Li < + > are accurately connected through coordinate bonds to achieve field assembly of a neutron source, controllable release is achieved, the raw material utilization rate and the neutron yield are high, and the method is suitable for large-scale production. The used raw materials Am (NO), LiCOs, ligands and the like are all in a non-radioactive source state, can be transported independently, do not need lead shielding, are low in transportation cost, do not need to be reported in advance, and are adaptive to portable scenes such as the field and the site.

The invention belongs to the technical field of radiation imaging detection, and particularly discloses a cold cathode X-ray vehicle detection emission box and an optical arrangement method thereof. The emission box comprises an emission box shell, an emission unit and an X-ray source. According to the X-ray source, the cold cathode X-ray tube and the high-voltage part of the high-voltage power supply module are integrally immersed in the high-voltage insulating oil, natural heat dissipation is achieved through the emission box shell, and the structure is compact and reliable. And a replaceable optical filter assembly and a lead shielding lining are arranged in the transmitting unit, so that the safety and the flexibility are ensured. By designing the sizes and positions of the light guide strip and the light outlet aperture, the light guide strip and the light outlet aperture are accurately matched with the geometric parameters and the preset coverage range of the target lane. The invention further provides an optical arrangement method, according to parameters such as lane width and detector height, the installation position and size of each component are accurately determined through geometric calculation, accurate projection of X-ray beams is achieved, scattering is effectively reduced, and the imaging quality is remarkably improved while radiation safety is guaranteed.

The utility model discloses a multilayer shielding transfer case for radioactive waste, it includes base, shielding case, gyro wheel subassembly and stop gear, wherein, shielding case adopts three -layer structure, namely stainless steel outer layer, composite shielding layer and stainless steel inner layer, can effectively shield neutron, gamma / X ray and heat conduction, and the box cover contains lead shielding block, and the sealing property is strengthened through the embedded recess, and the base is equipped with brake gyro wheel and push handle and is convenient for moving, and is equipped with stop gear, and the whole design of above -mentioned structure forms continuous shielding barrier, and gives consideration to radiation protection and transfer safety.

The invention provides a pipeline thermal stratification displacement sensor installation structure, and relates to the technical field of sensor installation, the pipeline thermal stratification displacement sensor installation structure comprises a support, the support is arranged along the radial direction of a surge pipe, displacement sensors are respectively arranged between the two radial directions of the surge pipe and the support, and the included angle formed by the two displacement sensors and the center of the surge pipe is 90 degrees; each displacement sensor is arranged on the support and connected with a pull rope, and each pull rope is connected with the fluctuation pipe and the corresponding displacement sensor in the radial direction of the fluctuation pipe. According to the invention, the displacement sensors are arranged in the two vertical radial directions of the surge pipe and are matched with the symmetrical L-shaped brackets, so that the displacement change of the surge pipe can be monitored in an omnibearing and high-precision manner; radiation interference is effectively prevented through the arrangement of the lead shielding cover, and normal work of the displacement sensor is guaranteed; the heat preservation layer is matched with the installation structure, the installation gap requirement is met, and meanwhile an installation channel is provided for the pull rope.

The invention provides a radio frequency drainage shielding structure and thin film deposition equipment. The radio-frequency drainage shielding structure comprises a plurality of fixed supporting columns, first ends of the fixed supporting columns are fixedly connected with a body of a process chamber, second ends of the fixed supporting columns are electrically connected with a radio-frequency matcher, and radio-frequency signals output by the radio-frequency matcher pass through a deposition assembly in the process chamber, the body of the process chamber and the plurality of fixed supporting columns and are transmitted to the deposition assembly. The signals are transmitted back to the radio frequency matcher; and the plurality of shielding covers are detachably arranged between the adjacent fixed supporting columns.

The invention belongs to the technical field of personal dosimeter calibration, and aims to solve the problems that an existing irradiation device is not beneficial to large-batch comparison operation in a field, and personnel are irradiated by mistake due to the absence of an interlocking mechanism. According to the irradiation device for the batch comparison test of the personal dosimeter, when an outer ring lead cover is installed at the upper end of a lead shielding chamber, an interlocking mechanism is triggered to unlock a source frame movable rod, at the moment, the source frame movable rod is lifted upwards so that the source frame movable rod can move upwards to a second position, and meanwhile, the auxiliary interlocking mechanism locks the outer ring lead cover; the radioactive source is located in the second slot at the same height as the irradiation channel; when the source frame movable rod moves downwards to a first position, the interlocking mechanism is triggered to unlock the outer ring lead cover, at the moment, the outer ring lead cover is lifted upwards, and the auxiliary interlocking mechanism locks the source frame movable rod; in addition, the dosimeter mounting groove is provided with a plurality of dosimeter slots at intervals along the circumferential direction. By means of the device, the situation that personnel are mistakenly shot when the personal dosimeter is compared in the field can be avoided, and large-scale comparison operation in the field can be achieved.