498 results about "Radiation protection" patented technology

The invention discloses a reactor instant-slow source item radiation shielding design system and method, and relates to the field of computer aided design of reactor radiation protection. The reactor instantaneous-delayed source item radiation shielding design system comprises a model conversion module, a population construction module, an index calculation module, an individual evaluation module, a selective evolution module, a hierarchical sorting module and an iterative convergence module which are in data flow connection in sequence from front to back. The invention relates to a reactor instant-slow source item radiation shielding design method. The method comprises the following steps: model conversion; constructing a population; calculating indexes; performing individual evaluation; selecting evolution; layering and sorting; and carrying out iterative convergence. According to the invention, a radiation shielding design system covering the whole life cycle of reactor operation and shutdown is established, and collaborative breakthrough of light weight, high safety and efficient convergence is realized through a multi-objective optimization algorithm.

The invention relates to the technical field of pipeline decontamination, in particular to an online pipeline ultrasonic decontamination device and method suitable for various pipe diameters, and the online pipeline ultrasonic decontamination device comprises a numerical control generator, a transducer, an amplitude-change pole, an adaptive clamp, an online monitoring device and other key components. And through the designed adaptive clamp, the device can act on pipelines with various pipe diameters and can move along the pipelines, and the decontamination requirements in different scenes are met. The online ultrasonic decontamination device is suitable for maintenance and cleaning work of pipelines with different pipe diameters in nuclear power facilities, and has important significance in improving the safety of the nuclear facilities and guaranteeing radiation protection for operators. The problem that an ultrasonic device is poor in applicability is effectively solved, meanwhile, the flexibility of the device is guaranteed, effective online decontamination of pipelines with various pipe diameters can be achieved through a single set of device, the decontamination cost of radioactive contamination of nuclear facility pipelines is effectively reduced, online efficient decontamination of radioactive contamination deposited in the pipelines is achieved, and the service life of the pipelines is prolonged. The safe and stable operation of the reactor is ensured, and the radiation risk of operators is reduced.

The invention discloses a rapid large-scale calculation simulation method and system for gamma radiation dose in a dynamic environment and a storage medium, and belongs to the technical field of ionizing radiation protection. The method comprises the following steps: firstly, constructing a triangular mesh scene model containing a radioactive source and a shielding body, and discretizing the radioactive source into a local point kernel; global coordinates of the point kernel and the vertex of the triangle are calculated in parallel by using a GPU, and a maximum parallelization hierarchical surrounding structure MPBVH of the scene is constructed; ray tracing is executed in parallel on the GPU, and all intersection points of MPBVH calculation rays and the shielding body are traversed to determine the thickness and the material of each shielding layer; and finally, dose values of all counting grids are calculated in parallel by adopting a point kernel method. When a radioactive source or a shielding body in a scene is subjected to dynamic changes such as movement and rotation, geometric data can be quickly updated, and calculation can be executed again. According to the method, the speed of large-scale point kernel calculation is increased, the influence of the environmental complexity on large-scale calculation time consumption is small, and the method can be suitable for rapid large-scale calculation and dynamic updating of the radiation field in the complex dynamic environment.

The invention relates to the technical field of photovoltaic adhesive films, and discloses an anti-radiation photovoltaic packaging adhesive film, a preparation method thereof and a photovoltaic module. The adhesive film is of a multi-layer co-extrusion composite structure formed by co-extrusion molding and irradiation, and comprises an upper surface layer, a middle functional layer and a lower surface layer, the upper surface layer is a radiation-resistant polymer matrix (such as EVA-g-St, EVA-g-(alpha-MeSt), POE-g-St and an EVA / POE-aromatic resin blend); the middle functional layer comprises a packaging resin matrix, an anti-radiation agent (which is a nano-scale radiation protection material such as a rare earth oxide, a heavy metal oxide, a boron-containing compound and a polymer derivative of a benzotriazole type ultraviolet absorbent) and a stabilizer; and the lower surface layer is a bonding surface layer formed by light-transmitting bonding resin. The adhesive film is good in radiation resistance, the light transmittance, the cohesiveness, the elongation at break retention rate, the yellowing resistance, the power attenuation resistance of a component and the like after accelerated radiation are obviously improved, and the service life of the component under strong radiation can be prolonged.

The invention discloses a multi-angle X-ray imaging system based on a detachable scintillation screen, and belongs to the technical field of X-ray imaging. The system comprises a base, a first / second rotating seat, a scintillation screen assembly, an objective table, a prism assembly, a protection module and a control module, wherein the scintillation screen assembly supports rapid switching between a flexible scintillation screen and a non-flexible scintillation screen and has a multidirectional position adjusting function, and the objective table lifting mechanism and an adjusting structure of the prism assembly jointly guarantee that the centers of the X-ray source, the sample to be tested, the scintillation screen and the prism are coaxially aligned. The protection module constructs a full-dimension radiation protection and state early warning system through a lead housing, a lead glass observation window, a radiation detection module and a tricolor lamp, operation safety is effectively guaranteed, and the control module comprises a master control system and an external touch screen and can achieve parameter presetting, intelligent regulation and control and detection data storage. The system can flexibly switch a static three-dimensional imaging mode and a dynamic rotary imaging mode, and can adapt to regular and special-shaped sample detection; and by replacing the scintillation screen, the performance of different scintillation screens can be conveniently detected. The system is convenient to operate and high in safety, and meets the multi-angle X-ray imaging requirements in the fields of industrial quality inspection and scientific research.

The present application provides a method for synergistically extracting polysaccharides from Kuding tea and an application of the polysaccharides in radiation protection. The extraction process of the polysaccharides comprises the following steps: subjecting the dried Kuding tea to steam explosion treatment, crushing the Kuding tea into particles with a size of 90-100 mesh, immersing the Kuding tea particles in distilled water, adding the solution into a microwave countercurrent extraction device, and simultaneously applying ultrahigh pressure for synergistic extraction to obtain an extraction solution. After centrifugation, the supernatant is collected, Sevage solution is added to remove proteins, and the supernatant is collected. Then, anhydrous ethanol is added to the supernatant, followed by centrifugation and freeze-drying to obtain the polysaccharides. The present application provides a method for synergistically extracting polysaccharides from Kuding tea, and it is found that the polysaccharides have a radiation protection effect, which provides a basis for further deep processing and a preparation method with a higher extraction rate.

The invention relates to the technical field of radiation protection and environment monitoring, and particularly discloses a radioactive waste gas emission radiation dose real-time monitoring system which comprises a fixed monitoring base station network, an autonomous mobile monitoring cluster, a data fusion and cooperative control center and a radiation dose field three-dimensional reconstruction and evaluation terminal. Through air-ground cooperative monitoring, plume prediction and intelligent path planning based on an atmospheric diffusion model, and a physically constrained spatial interpolation algorithm, efficient tracking of a radioactive plume three-dimensional dynamic diffusion process and accurate reconstruction and visual evaluation of a three-dimensional dose field are realized. According to the system, an air-ground cooperative monitoring system composed of a fixed base station network and an autonomous mobile cluster is constructed, so that a passive and static monitoring normal form is fundamentally changed.

The invention discloses bismuthate glass. The bismuthate glass is prepared from the following main raw materials: 50 to 83 weight percent of Bi2O3, 10 to 20 weight percent of B2O3, 3 to 10 weight percent of ZnO, 3 to 10 weight percent of SiO2 and 3 to 10 weight percent of Al2O3; 0-4wt% of TiO2 is added on the basis of the total weight of the main raw materials. The invention further discloses a coating based on the bismuthate glass. The reflection performance of the glass coating is remarkably improved, the radiation refrigeration effect of the glass ceramic coating is remarkably improved, and the glass ceramic coating has the radiation protection, insulation and anti-static effects.

The invention discloses an electromagnetic environment-friendly radiation protection assessment method and system, and the method comprises the steps: obtaining electromagnetic field data containing power frequency and high-frequency components through a data collection device, generating a multi-dimensional index data set and a radiation characteristic distribution diagram through the combination of exposure time and a crowd sensitivity index through a computational simulation method, and accurate quantitative analysis of the complex electromagnetic environment is realized. On the basis, a weight analysis method is adopted to fuse effect parameters to calculate a risk quantitative score, when the score exceeds a safety threshold value, radiation limit value data is automatically extracted to generate a visual risk map, and a processing module is linked to output a grading protection instruction. By activating protection configuration in the sensor network, decision unit parameters are dynamically adjusted according to real-time electromagnetic field data, and an optimized protection scheme including a dynamic strategy is formed. According to the invention, the conversion from passive protection to active early warning is realized, and the intelligent level and protection effect of electromagnetic radiation protection are significantly improved.

The invention discloses an anti-radiation medical protective glove and a production process thereof, and belongs to the technical field of medical protective gloves, a polydopamine hollow microsphere is prepared by using ZIF-8 as a self-sacrifice template, bismuth and gadolinium elements are loaded through hydrothermal synthesis and ion adsorption, a composite shielding microsphere is prepared, and the composite shielding microsphere is used for preparing the anti-radiation medical protective glove. Then, the composite shielding microspheres and a nano starch enhanced cross-linked network are synergistically introduced into a natural latex matrix, after dipping forming, a hydrophilic / hydrophobic wetting gradient is constructed on a glove lining through mask auxiliary plasma etching, and the anti-radiation medical protective glove is prepared. Through the cooperation of the shielding function of the composite microspheres, the mechanical enhancement of a nano starch cross-linked network and the surface one-way moisture conduction function, the glove has excellent radiation protection performance and also has the characteristics of being light, flexible and comfortable to wear, the problems that a traditional lead rubber glove is heavy, rigid and poor in air permeability are effectively solved, and the service life of the glove is prolonged. The system is especially suitable for medical scenes requiring high flexibility and comfort, such as interventional radiosurgery.

The present application relates to a kind of core high probe extraction mechanism, which provides effective radiation protection during the removal of the probe by introducing a shielding cylinder, significantly reduces the radiation dose that can be received by the operator when working, improves the safety of the working environment.Secondly, the present application also configures a positioning connection device with a positioning camera, which can monitor and adjust the position of the lifting moving assembly in real time, ensure its accurate alignment with the probe to be removed, and avoid positional interference between the shielding cylinder and other structural members in the core during the gradual deepening of the shielding cylinder into the core pool, thereby solving the problem of difficult accurate docking in traditional methods, improving the probe removal efficiency and operation safety.

The invention provides an automatic detection system for anti-radiation performance of a lead garment, a lead garment hanger adopts a humanoid structure design and is used for simulating the condition that the lead garment is worn in a human body posture, a plurality of X-ray detectors are arranged on the outer surface of the lead garment hanger and are used for detecting the X-ray penetration position and measuring the X-rays, and the X-ray detector is used for detecting the radiation resistance of the lead garment. The rack guide rail is detachably assembled on a CT operation site and arranged at the bottom of the lead clothes hanger, the lead clothes hanger can reciprocate along the rack guide rail through a first driving motor and can rotate circumferentially through a second driving motor, and the main control module comprises a single chip microcomputer and is used for controlling the lead clothes hanger to move horizontally and rotate. And the X-ray penetration position and the X-ray measurement in the lead clothes are determined through fitting calculation. According to the lead clothes damage detection method, the lead clothes damage detection method during wearing by simulating the human body posture can be realized, the authenticity and reliability of lead clothes damage detection are effectively improved, and unnecessary damage of rays to the human body caused by internal damage of the lead clothes is prevented.

The invention discloses a rubber glove box protective glove with a latex coating and a manufacturing method. The glove comprises a mould pressing rubber layer and a local latex coating. The mold pressing rubber layer is prepared through mold pressing vulcanization forming and comprises rubber, a shielding component, a reinforcing filler, a filling agent, an active agent, an anti-aging agent, a plasticizer, a lubricating release agent, a vulcanizing agent and an accelerant. The local latex coating is prepared through latex impregnation, and latex components comprise latex, reinforcing filler, a stabilizer, a diffuser, an active agent, an anti-aging agent, a vulcanizing agent, an accelerant, a thickening agent, a defoaming agent and a coloring agent. Through formula design of the mold pressing rubber layer and the local latex coating and optimization of a latex dipping process, the glove box glove with high mechanical hazard protection performance in the local position is obtained on the premise that the ray protection function and wearing comfort are guaranteed, and the service life of the glove box glove is prolonged. And the service life of the glove box protective glove under the radiation and mechanical dual harm scenes is prolonged.

The present application relates to a kind of for the radiation protection detection in nuclear magnetic machine room, including: shielding sleeve box, by diamagnetic material is made, for shielding external static magnetic field, its internal cavity shape is adapted according to the shape of the used patrol instrument;Ray detection mesh, set up on shielding sleeve box corresponding to the position of patrol instrument probe, by diamagnetic material is made, allow X or gamma ray to penetrate;Instrument data reading mesh, set up on shielding sleeve box corresponding to the position of patrol instrument display screen, by diamagnetic material is made, allow detection personnel to read data directly visually;The import and export of instrument that can be closed, be set on shielding sleeve box, and be equipped with the sealing cover made of diamagnetic material, for the input and output of patrol instrument, the sealing cover is in closed state when detecting.The present application solves the phenomenon that the radiation diagnosis and treatment machine room adjacent place is the radiation protection detection difficult to implement for nuclear magnetic resonance machine room.

The invention relates to the use of a substrate for shielding X-ray radiation. The matrix for radiation protection against X-ray radiation comprises at least one silicone polymer and at least one filler.

The invention relates to the technical field of portable rays, in particular to a portable ray detection system suitable for multi-scene integration, which comprises the following modules: a scene adaptation module used for acquiring an adaptive portable X-ray equipment model by adopting a target scene analysis method and matching a radiation protection standard with a penetrating power requirement; the multi-energy imaging module is used for calculating the atomic number of a substance through gray value comparison by adopting a dual-energy penetration technology; the radiation protection module is used for controlling the daily accumulated dose of an operator to be below 1mSv by adopting an ALARA principle; and the data traceability module is used for calibrating equipment monthly by adopting a standard dose body, extracting a fault code positioning problem and obtaining a traceable detection report and a traceable maintenance record. The problems that a traditional ray detection system is difficult to adapt to multi-scene space and material difference, imaging cannot effectively distinguish substances, smear exists in moving target detection, radiation protection is difficult to reach the standard, detection data is difficult to trace, and maintenance is inconvenient are solved.

The utility model discloses a movable radiation protection equipment, including protection mechanism, splicing mechanism and angle locking mechanism, the protection mechanism includes the protection board material, the splicing mechanism includes the clamping handle and the card hole, the upper portion of one side surface of protection board material is equipped with the limit slot, the upper portion fixedly connected with the tab of limit slot, the surface of the card hole is passed through and is equipped in the tab, the upper portion fixedly connected with the limit block of the other side surface of protection board material, the inside of limit block is equipped with the expansion slot, the clamping handle swing installation is in the inside of expansion slot, the angle locking mechanism includes the locking plate and the locking lever, the locking plate rotation is installed in the upper surface one side of protection board material, the locking lever fixed mounting is in the upper surface the other side of protection board material. The utility model discloses the splicing mechanism of setting, has realized the quick splicing and disassembly of radiation protection equipment, and the operation is simple, has improved the convenience and efficiency of multiple equipment combination use significantly.

The radiation protection head and neck sleeve convenient to wear comprises a head protection part, a neck protection part is integrally formed at the lower end of the head protection part, a neck opening extending to the head protection part is formed in the front side of the neck protection part, a zipper is arranged in the neck opening, and the neck protection part is connected with the head protection part. A face opening is formed in the surface of the front side of the head protection part, a face protection part is arranged in the face opening, the head protection part and the neck protection part are both made of flexible materials, the head protection part and the neck protection part are integrally formed, and the neck opening is combined with the convenient wearing and taking-off design of a zipper, so that the pillow is matched with the physiological structure of the head and the neck of a human body; the wearing efficiency is improved, the key areas of the head and the neck can be fully covered through the integrated structure, the radiation leakage risk is reduced, and the comprehensiveness of radiation protection and the wearing convenience are balanced.

The invention relates to a vessel for the long-term storage of DNA in space at a constant temperature of -196 °C. The aim is to protect biological samples – especially DNA – for decades to centuries from the extreme environmental conditions of space, including vacuum, intense radiation, extreme temperature fluctuations and mechanical stresses. The vessel has a three-layered structure: 1. Inner chamber made of boron nitrogen nanotubes (BNNTs) that offer outstanding protection against cosmic radiation, high mechanical strength, chemical inertness and temperature resistance. 2. Middle insulating layer made of aerogel that minimizes heat exchange and keeps the cryogenic temperature constant. 3. Outer protective layer made of titanium, which protects against micrometeorites, It protects against physical impacts and corrosion. Technical advantages: • Long-term stability of DNA through consistently low temperatures. • Effective radiation protection against cosmic and solar radiation. • Excellent thermal insulation thanks to aerogel. • Mechanical robustness due to titanium. Areas of application: • Securing and archiving genetic material for research, space travel and long-term preservation. • Provision of DNA for future scientific or biological restoration projects. Special feature: The capsule is compact, space-compatible, and can be used as part of space missions, space stations, or interplanetary projects.

The invention relates to the technical field of cables, solves the problem that an existing aerospace cable is insufficient in vibration fatigue resistance and high-energy radiation resistance, and particularly discloses a multi-layer shielding optical fiber composite aerospace cable and a preparation method thereof.The multi-layer shielding optical fiber composite aerospace cable comprises an insulating layer, an inner shielding layer, a buffer bonding layer and an outer shielding layer which are sequentially arranged from inside to outside; a conductor core and an optical fiber bundle are arranged in the insulating layer, and the insulating layer comprises a bonding transition layer, a core insulating layer and an anti-radiation protection layer from inside to outside; the inner shielding layer comprises a nano-silver conductive film and a silicone rubber elastic layer, and the nano-silver conductive film is arranged on the inner side of the silicone rubber elastic layer; the outer shielding layer is provided with a nickel-copper alloy wire woven mesh; and the buffer bonding layer is provided with a modified polyimide adhesive layer. According to the optical fiber composite aerospace cable and the preparation process thereof, the shielding, buffering and interlayer bonding performance of the cable is guaranteed through control over the inner shielding layer, the buffering bonding layer and related preparation parameters, and the optical fiber composite aerospace cable adapts to aerospace application requirements.

The present invention pertains to the fields of cosmetology, nanotechnology, materials engineering, and related sciences. More specifically, the invention relates to a premix for infrared radiation protection comprising rock nanoparticles, to a process for preparing a composition, and to a composition for enhanced infrared radiation protection. Additionally, it discloses a method for blocking infrared radiation and the use of rock nanoparticles for blocking infrared radiation. The premix and the composition of the invention comprise rock nanoparticles, particularly basalt rock nanoparticles, plutonic rock nanoparticles, or combinations thereof, and provide advantageous and surprising effects.

A radiation protection shielding system is disclosed, which comprises at least one radiation protection drape sized to at least partially cover the patient from a proximity of a radiated area of the patient to the feet of the patient. The radiation protection drape comprises at least a first section a second section. The first section is partitioned from the second section from a first edge of the radiation protection drape towards a second edge of the radiation protection drape.

The invention discloses a radiation protection device capable of moving along with a bulb tube under perspective of a C-shaped arm, which belongs to the field of medical instruments and comprises a bed body, a C-shaped arm frame, a bulb tube part and an image acquisition part, and the bulb tube part and the image acquisition part are respectively fixed at two ends of the C-shaped arm frame; the anti-radiation bed further comprises an anti-radiation cover body, one end of the anti-radiation cover body is fixedly connected to the outer portion of the bulb tube part in a sleeving mode, and the other end of the anti-radiation cover body is fixedly connected to the lower end of the bed body. The anti-radiation bed is provided with the anti-radiation cover body, one end of the anti-radiation cover body is mounted at the bottom of the bed body, and the other end of the anti-radiation cover body is mounted outside the bulb tube, so that a flexible connection channel is formed; no matter how the bulb tube swings back and forth or left and right, the radiation-proof cover body can stretch and deform along with the bulb tube, the radiation-proof cover body is like a protective shield which always follows a hand, and most of primary scattered rays are limited in the radiation-proof cover body when being just generated, so that the environmental radiation background value in the operating room is remarkably reduced, and the radiation-proof effect of the operating room is improved. Particularly, the lower limbs of a doctor standing close to the operating bed are protected from being hit by lateral scattering.

According to the quick-drying medical ray protective cream and the preparation method and application thereof, through effective combination of a radiation-proof material and a specific film-forming system, a powerful protective film can be quickly formed on the skin surface after the protective cream is smeared, the ray shielding effect of the protective cream is superior to that of interventional protective gloves, and meanwhile, the protective cream does not contain heavy metal such as lead and the like, so that the service life of the protective cream is prolonged. The safety and non-toxicity can be ensured. The paste can be directly smeared on the skin, the problems that traditional lead gloves are heavy and inflexible and the like are solved, the paste is particularly suitable for scenes such as interventional operations, effective ray protection can be achieved, and meanwhile operation in the operation process cannot be affected.

This invention discloses a fissure grouting material, its preparation method, and its application, belonging to the technical field of radiation protection engineering materials. By mass, its raw materials include: 45-60 parts barite sand, 25-35 parts sulfoaluminate cement, 8-20 parts borax, 2-5 parts boron carbide powder, 1-5 parts nano-gadolinium oxide, 5-15 parts lithium slag powder, 3-8 parts barium sulfate whiskers, 3-8 parts polymer emulsion, 0.5-1.5 parts water-reducing agent, 0.1-0.5 parts stabilizer, and 18-25 parts water. This invention provides high-density gamma-ray shielding through barite sand, achieves all-round neutron protection through a quaternary composite neutron absorption system, enhances the material's toughness and shielding effect through barium sulfate whiskers, and ensures high fluidity and interfacial bonding strength of the grout through the polymer emulsion. This material is particularly suitable for sealing and shielding fissures in the surrounding rock of radioactive tunnels, possessing advantages such as excellent shielding effectiveness, good construction performance, high volume stability, and long-term durability.

The present application belongs to the technical field of radiation protection and pressurized water reactor source term calculation, and particularly relates to a pressurized water reactor pellet-cladding gap fissile product source term fast calculation method. The method comprises the following steps: step 1: establishing a first-order kinetic balance equation of the fissile product in the fuel rod; step 2: using Chebyshev rational approximation method to solve the accumulation of the nuclides in the decay chain corresponding to different mass numbers in the fuel rod; step 3: calculating the release production ratio of the fissile product nuclides; step 4: judging the release path of the target nuclides from the fuel pellet to the pellet-cladding gap; and step 5: judging the fissile product source term in the pellet-cladding gap according to the release path of the fissile product. The present application has the beneficial effect that the fissile product source term in the fuel rod is calculated in detail, and the fissile product source term in the pellet-cladding gap can be obtained, which is used for the release source term calculation when the fuel cladding is damaged subsequently.

The present application relates to the field of medicine, and particularly to the application of schisantherin B in the preparation of a medicine for preventing or treating radiation damage of the intestinal tract. The present application finds that schisantherin B has a protective effect on the intestinal tract after irradiation, and experiments prove that schisantherin B can reduce the pathological damage degree of the intestinal tract after irradiation, including increasing the length of intestinal villi and the number of crypts, maintaining the stability of the intestinal mucosal barrier, reducing the content of inflammatory factors in the intestinal tissue, restoring the activity of the intestinal epithelial cells after irradiation, and inhibiting the apoptosis. Meanwhile, schisantherin B can reduce the iron death caused by irradiation. Therefore, schisantherin B has a wide application prospect as a potential radiation protection agent in the treatment of radiation-induced intestinal injury and drug development.

The invention relates to the technical field of neutron measurement, and particularly discloses a multi-activation foil and method for measuring a neutron energy spectrum. The multi-activation foil comprises a shell and an activation sheet placed in the shell, and the activation sheet sequentially comprises Ni, Sc, Au, W, Cu, Pt, In, Zn and Fe from top to bottom. The activated foil can realize high-resolution measurement of a neutron spectrum in a very small space, has the characteristics of size miniaturization, wide energy response range, wide neutron fluence rate application range, controllable manufacturing tolerance, optimized material ratio and the like, and is suitable for neutron spectrum and neutron dose measurement of a small-scale region of a nuclear facility and neutron dose measurement of a small-scale region of a nuclear facility. The method can also be popularized and applied to fine dose field distribution measurement of a large-scale area of a nuclear facility, and provides accurate data support for safe operation, shielding verification and radiation protection of the nuclear facility.

The invention discloses a local radiation protection device for CT examination, and belongs to the technical field of protection devices. A local radiation protection device for CT examination comprises a protection lead plate, one side of the protection lead plate is fixedly connected to a connecting frame, a lifting frame is movably installed below the connecting frame, the lifting frame is connected to a fixed sliding frame in a sliding mode, and the fixed sliding frame drives the lifting frame to conduct height adjustment through an adjusting assembly. The height and the horizontal rotation angle of the protection lead plate are convenient to adjust, the walking assembly is arranged on the base, the base and other structures are driven to linearly move along the walking guide rod, the protection lead plate can synchronously move along with a patient on the CT detection bed, and the protection lead plate can be always suspended on the covering part of the patient; according to the CT detection bed, the protection lead plate can be conveniently rotated to the lateral position, the protection lead plate can be conveniently moved away from the CT detection bed, when a patient enters the CT detection bed or gets up from the CT detection bed, the protection lead plate cannot cause obstruction, and practicability is improved.

The present invention provides a TSV radiation-resistant packaging structure and a packaging method. The TSV radiation-resistant packaging structure comprises: a first redistribution layer, which is disposed on a front side of a wafer; the wafer, a cavity being etched inside the wafer; a chip, which is disposed in the cavity inside the wafer; a second redistribution layer, which is disposed on a back side of the wafer and is electrically connected to the chip; a radiation protection layer, which is disposed in the cavity inside the wafer and on the back side, and encapsulates the chip; and a TSV via, which penetrates through the wafer and connects the first redistribution layer to the second redistribution layer. A radiation-resistant material is used to protect the chip, such that the present invention can be used in fields such as high-energy X-ray detection and gamma-ray detection, thereby improving the protection performance of the chip.