46 results about "Lead shielding" patented technology

The invention belongs to the technical field of flexible ray protective clothing, and discloses medical flexible ray shielding protective clothing and a preparation method thereof. A medical flexible ray shielding protective garment comprises a shielding material, flexible rubber and a garment material, the shielding material is equally distributed in small capsule cabins of the flexible rubber, and the small capsule cabins are distributed in the thickness direction of the flexible rubber for 3-10 times; the clothing material is attached to the flexible rubber loaded with the shielding material to manufacture the clothing. The novel integrated ray protection suit provided by the invention adopts a lead-free shielding material, has a relatively good shielding effect on gamma rays and X rays, is soft in material, light in weight and non-toxic and harmless to a human body, can be widely applied to military industry, medical science, other ray protection laboratories and the like, and has a wide application value.

The utility model relates to a lead shielding chamber sample changing structure which comprises a lead shielding chamber cover, a lead shielding chamber body and a movable lead shielding chamber wall, and the movable lead shielding chamber wall is located on the opening side of the lead shielding chamber body and is in sliding connection with the lead shielding chamber body through a sliding rail to form a lead shielding chamber. Two probes of the high-purity germanium detectors which are oppositely arranged are arranged in the lead shielding chamber, when a sample is replaced, the lead shielding chamber cover is opened, and the movable lead shielding chamber wall and the high-purity germanium detectors fixed with the movable lead shielding chamber wall slide through the hand wheel on the slide rail, so that the distance between the two high-purity germanium detectors is adjusted; according to the structure, low-background and high-efficiency measurement of samples with different sizes can be realized, so that the detection sensitivity of the system is improved.

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 invention relates to a modular shielding device for radioactive waste of a nuclear power plant, which comprises a base frame, a first shielding mechanism, a cabin body and a second shielding mechanism, and is characterized in that the base frame comprises a plurality of accommodating cavities; the first shielding mechanism is fixedly connected to the base frame and covers the base frame, so that the containing cavity forms a plurality of shielding spaces, each shielding space is used for containing one radioactive waste barrel, a plurality of openings corresponding to the containing cavities are formed in the first shielding mechanism, and each opening communicates with the outside and the corresponding containing cavity; the cabin body is sleeved outside the first shielding mechanism; and the second shielding mechanism is arranged between the first shielding mechanism and the cavity wall of the accommodating cavity. Compared with the existing temporary lead shielding / lead wall or fixed screen equipment, the environment pollution or personnel poisoning caused by lead when temporary lead sheaths or lead bricks and the like are adopted for shielding is avoided, and meanwhile effective closed shielding protection in all directions can be achieved.

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 invention relates to a high-sensitivity radioactive gas activity measuring device and method. The device 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 method, the original spectrum of the gamma detector, the anti-cosmic ray gamma spectrum, the beta-gamma coincidence spectrum without mutual influence among different radioactive gases and the anti-cosmic ray beta-gamma coincidence spectrum can be obtained. According to the invention, synchronous measurement of different radioactive gases can be realized, and the detection sensitivity of the radioactive gases can be greatly improved.

The present invention belongs to the technical field of uranium exploration, and particularly relates to an automated lead chamber suitable for detecting radon using activated carbon, which can automatically open and close a door and meets the use requirements of an efficient and intelligent radon detector. The device comprises: a lead chamber base (1), a lead shielding chamber (2), a lead chamber door (3), a door connecting rod (4), a transverse gear (5), a transverse gear shaft (6), a transverse gear shaft left bracket (7), a transverse gear shaft right bracket (8), a vertical gear (9), a vertical gear shaft (10), a vertical gear shaft bracket (11), a locking connecting sleeve (12), a vertical gear shaft movable head (13), a motor connecting shaft (14), a motor outer cover (15), a motor base (16), and a brushless DC motor (17).

The utility model relates to the technical field of liquid medicine production, in particular to an integrated molybdenum technetium generator. The integrated molybdenum technetium generator comprises a shell; the lead shielding seat is arranged in the shell and is provided with a mounting hole penetrating through the surface of one side of the lead shielding seat; the generating column is mounted in the mounting hole; the liquid inlet assembly and the liquid collecting assembly are both installed on the shell, the liquid inlet assembly is used for injecting leacheate into the generation column, and the liquid collecting assembly is used for extracting liquid from the generation column; and the lead shielding block is mounted on the shell and blocks the hole opening of the mounting hole. By means of the structure, radiation shielding can be better carried out in the using process by means of the lead shielding block, and therefore the integrated molybdenum technetium generator can be used without being placed in a shielding body outside a shell.

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 utility model discloses a lead shielding device, belongs to the technical field of X-ray material counting, and particularly relates to a lead shielding device of a high-speed online X-ray material counting system, which realizes material management intellectualization, and comprises a metal plate main body and an intelligent desktop rotating device, the metal plate main body comprises a small lead room arranged in the metal plate main body, the small lead room is an X-ray detection area, and the X-ray source and the flat panel detector are fixedly installed in the small lead room. The intelligent table top rotating device is provided with four discharging positions, a radiation baffle is arranged between every two discharging positions, when materials to be detected flow to a detection area through the intelligent table top rotating device, the radiation baffles and the small lead rooms of the metal plate body can form a radiation shielding cover, radiation shielding is achieved, products and materials outside the detection area are effectively protected, and the detection efficiency is improved. And the service life and the detection efficiency of equipment are improved. According to the utility model, the manufacturing cost is effectively reduced, the self weight is reduced, and the service life of equipment is prolonged.

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.

The present invention relates to a device for generating gamma pulse radiation based on free fall, belonging to the field of ionizing radiation measurement technology. The device comprises a source container with a shutter and a lead shield. The source container can generate a radiation beam through a radiation outlet of the source container. The lead shield is close to the shutter and has a steel cladding on its outer layer. A circular lead shield radiation outlet is opened on the central axis of the upper position of the lead shield and penetrates the lead shield and the steel cladding. The device also includes a main bracket, which is provided with a guide rail, a slider is installed on the guide rail, and the lead shield is fixed to the slider. The upper end of the main bracket is provided with a top bracket, which is provided with a motor. The output shaft end of the motor is connected to an electromagnet via a nylon rope. The electromagnet is connected to the upper end surface of the lead shield by magnetic force. The device provided by the present invention can generate pulsed gamma radiation of different pulse widths, providing a reliable pulse radiation field for the research and development, calibration and verification of critical safety alarms and other related instruments.

The present invention belongs to the field of power transformer manufacturing, and specifically is a lead shielding tube structure with good heat dissipation function. It includes: a long support bar assembly, a support tube, an insulating tube, an outer insulation layer, and an oil drain hole opened on the lead shielding tube; wherein, the hole wall of the oil drain hole is coated with an insulating layer; a support tube is sleeved on the shielding tube; the support tube includes: a cylindrical section and a conical tube section connected thereto as a whole; the cylindrical section of the support tube is sleeved on the lead shielding tube at the oil drain hole, and an insulating tube is provided between the conical tube section of the support tube and the lead shielding tube; the insulating tube is adapted to the conical tube section of the support tube; a long support bar assembly is sandwiched between the insulating tube and the support tube; the outer insulation layer is coated on the lead shielding tube, and the thickness of the outer insulation layer is equal to the outer diameter of the conical tube section of the support tube. The present invention solves the contradiction between insulation performance and heat dissipation performance in the previous lead shielding tube structure by arranging an oil drain hole with a long support bar assembly and cooperating with the insulating tube.

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 invention discloses a calculation model of a complex gamma dose field radioactive source, aiming at the problem that the contribution of a body source and a line source is difficult to distinguish in the existing monitoring, a natural background, a uniform dispersion body source and a leakage channel line source are simultaneously incorporated into a gamma dose rate measurement model in a cuboid space; establishing a body source volume fraction and line source line integral dose formula according to nuclide activity, a kerma constant and geometric parameters; 2 or more measuring points are arranged to construct a linear equation set, MCNP5 Monte Carlo simulation is used for optimizing the size, the position and the direction of the lead shielding body, equation morbidity is reduced, and contribution of each source item is obtained through solving. The experimental verification deviation is less than 33%, and reliable technical support can be provided for radiation source discrimination and protection after nuclear power station and nuclear facility accidents.

The utility model discloses a transformer which comprises a transformer shell, a transformer body, a pipe barrel, a high-voltage bushing and a lead shielding pipe, and the lead shielding pipe is connected between the transformer body and the tail of the high-voltage bushing and used for containing a high-voltage lead led out of the transformer body and guiding the high-voltage lead to the high-voltage bushing. The transformer further comprises a first voltage-sharing ball, the first voltage-sharing ball is arranged in the transformer shell, the lead shielding pipe comprises a first shielding pipe and a second shielding pipe, the first shielding pipe is arranged in the transformer shell, the second shielding pipe is arranged in the pipe barrel, the first end of the first shielding pipe is connected to the transformer body, and the second end of the second shielding pipe is connected to the transformer shell. The second end of the first shielding pipe is connected to the first voltage-sharing ball, the first end of the second shielding pipe is connected to the high-voltage bushing, and the second end of the second shielding pipe is detachably connected to the first voltage-sharing ball. By means of the arrangement mode, production and transportation can be facilitated.

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 utility model discloses a transformer coil leading-out head shielding structure, which relates to the technical field of transformer manufacture, and comprises a transformer coil, a voltage regulating coil leading-out group, a first insulating layer and a shielding rod, the transformer coil comprises a voltage regulating coil, the voltage regulating coil leading-out group comprises a plurality of voltage regulating leading-out heads, and the first insulating layer comprises a first insulating layer and a second insulating layer. The voltage regulating outlet head is led out from the voltage regulating coil; the first insulating layer wraps the outer side of the voltage regulating coil leading-out group, the shielding rods are arranged in the outermost voltage regulating outlet head in the plurality of voltage regulating outlet heads and close to one side of the first insulating layer, the shielding rods are arranged side by side, and when the voltage regulating outlet heads are connected with the transformer lead, the shielding rods are in short circuit with the voltage regulating outlet heads in a crimping mode. According to the technical scheme provided by the utility model, the electric shielding effect on the voltage regulating coil outlet head can be realized without adopting aluminum foil which is wrapped layer by layer and needs to be molded, the whole structure is simple, the processing is easy, and the processing quality and the working stability of the transformer can be ensured.