936 results about "Radiation shield" patented technology

One variation of a system includes a pressure vessel: including a wall; defining a primary working fluid circuit extending vertically within the wall; defining a secondary working fluid circuit extending vertically within the wall and fluidly isolated from the primary working fluid circuit; and configured to store a nuclear fuel, a primary working fluid, and a secondary working fluid. The wall of the pressure vessel: defines a heat exchanger configured to transfer thermal energy from the primary working fluid flowing through the primary working fluid circuit into the secondary working fluid flowing through the secondary working fluid circuit; and defines a radiation shield configured to attenuate radiation emitted by the nuclear fuel.

The invention provides a bismuth oxide-based epoxy resin composite material with a radiation shielding function as well as a preparation method and application of the bismuth oxide-based epoxy resin composite material. According to the preparation method disclosed by the invention, the bismuth oxide is subjected to surface modification, and after surface grafting modification by the coupling agent, the surface of the bismuth oxide is changed from strong hydrophilicity to strong hydrophobicity, so that the dispersity and interfacial compatibility of the bismuth oxide in an organic medium are remarkably improved. Secondly, preparing the composite material from the modified bismuth oxide, epoxy resin and a curing agent through a mechanical blending-vacuum defoaming combined process. On one hand, bismuth oxide, epoxy resin and a curing agent are uniformly mixed through mechanical blending; on the other hand, bubbles generated in the blending process are removed through vacuum negative pressure. The bismuth oxide in the composite material is uniformly distributed, no bubble exists in the body, and the surface is smooth and complete, so that the composite material has excellent gamma-ray shielding performance and good mechanical property. The process is simple, the yield is high, the product property is stable, and good economic benefits and environmental benefits are achieved.

An antenna apparatus includes a radiation shield between an antenna element and at least one radio frequency integrated circuit (RFIC) coupled to the antenna element. An antenna substrate includes a first dielectric layer having opposite first and second surfaces, and a first metallization layer attached to the second surface to form a ground plane. A base substrate includes at least one second dielectric layer having opposite third and fourth surfaces, and a second metallization layer having a first side attached to the third surface and a second side attached to the first metallization layer to form the radiation shield. The RFIC is RF coupled to the antenna element through at least one via extending through the base substrate and a coupling element within aligned openings of the first and second metallization layers.

The invention provides a samarium / europium / gadolinium-containing zirconium hydride block as well as a preparation method and application thereof, and relates to the technical field of radiation shielding materials. The zirconium hydride block containing samarium / europium / gadolinium comprises the following elements in percentage by mass: 95% < = Zr < = 99.5%, 0% < = Gd < = 5%, 0% < = Sm < = 5%, 0% < = Eu < = 5% and 0% lt. Gd + Sm + Eu < = 5%. The preparation method comprises the following steps: respectively hydrogenating sponge zirconium, metal gadolinium, metal europium and metal samarium to respectively obtain corresponding hydride powder; weighing zirconium hydride powder, gadolinium hydride powder, europium hydride powder and samarium hydride powder according to a required proportion, and uniformly mixing under a protective atmosphere; and carrying out pressure sintering on the mixed powder, and carrying out secondary hydrogenation to obtain the zirconium hydride block containing samarium / europium / gadolinium. According to the invention, the absorption of the material to low-energy-segment neutrons can be obviously improved; and the preparation of the zirconium hydride block containing samarium / europium / gadolinium and the accurate regulation and control of doped elements are realized.

A radiation shield assembly is described, configured to block radiation emanating from a radiation source from reaching a user. Two shields are supported by a support arm, and are configured to rotate and translate relative to one another about the support arm's longitudinal axis. This allows the shield to be easily configured and reconfigured as necessary to visualize various parts of a patient's body via radiography.

The invention provides a thermal radiation shielding assembly and a thermal radiation shielding system of a star imitator, the thermal radiation shielding assembly comprises a plasma container and a Dewar tank surrounding the periphery of the plasma container, and a first thermal radiation shielding part is arranged in an annular cavity formed between the plasma container and the Dewar tank; the first heat radiation shielding part is fixedly arranged on the periphery of the plasma container in a surrounding mode and comprises a cold pipe assembly, a first heat insulation assembly, a first cold shield assembly and a first supporting assembly; the cooling pipe assembly comprises a cooling pipe which surrounds and is attached to the peripheral wall of the plasma container to extend; the first heat insulation assembly extends around the plasma container, and the inner side surface of the first heat insulation assembly is attached to the peripheral wall of the cooling pipe assembly. The first cold shield assembly and the first heat insulation assembly extend around the plasma container at an interval; the first cold shield assembly is fixed to the outer wall of the plasma container through the first supporting assembly to form multiple heat radiation shielding layers, and high-temperature heat radiation from the plasma container can be isolated.

A lightweight radiation shielding material. A carbon nanotube forest is embedded in a matrix comprising nanoparticulates, such as nanoparticles, carbon nanotubes, or graphene nanosheets. The nanoparticulates can be low atomic number (low-Z) or high atomic number (high-Z). The matrix can be a solidified polymer, epoxy, resin, or ceramic precursor, for example silicon carbide. The radiation shield can shield an object from radio frequency interference (RFI), lightning, electromagnetic interference (EMI), an electromagnetic pulse (EMP), gamma rays, X-rays, neutrons, and / or protons. The nanoforest is disposed on a conductive base with sufficient in-plane electrical conductivity to provide an effective conductive path for currents induced by radiation absorption. The base can be a second nanoforest comprising horizontally-oriented carbon nanotubes, which makes the shield particularly lightweight, as low as 10% of the mass of aluminum that provides equivalent shielding. The base can be adhered to an object to be shielded.

The present disclosure relates to an X-RAY detector including a base substrate and a plurality of detection units arranged on the base substrate. Each detection unit includes a light conversion element and a switching transistor, the light conversion element is configured to convert an optical signal into an electrical signal, and the switching transistor is configured to output the electrical signal to a reading signal line. Each detection unit further includes a radiation shielding structure located at a light-entering side of the detection unit, and an orthogonal projection of the radiation shielding structure onto the base substrate fully covers an orthogonal projection of the switching transistor onto the base substrate. The present disclosure further relates to a method for forming the X-RAY detector.

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.

A clamping system has a workpiece clamp having a platen to support a workpiece and heating elements for heating the platen to a platen temperature. A cooling plate has cooling features to cool to the cooling plate. A vacuum chamber defines a chamber volume between the platen and the cooling plate. One or more radiation shields within the chamber volume can limit a radiative heat transfer between the platen and the cooling plate. A vacuum source and a gas source are selectively fluidly coupled to the chamber volume. A controller controls the platen temperature in both a high and a low temperature regime by controlling a pressure within the vacuum chamber through the vacuum source and gas source to control a heat transfer between the platen and the cooling plate.

The invention provides a radiation shielding multi-objective optimization design method based on a Bayesian neural network, and the method is characterized in that the method comprises the following steps: S1, obtaining sample data; s2, network construction and evaluation; s3, robust design optimization is carried out; according to the method, cognitive uncertainty in the modeling process of an agent model is quantified by using a loss function based on variational inference and KL divergence derivation, a nuclear radiation shielding calculation agent model considering uncertainty factors is obtained, and radiation shielding calculation is performed on an objective function in multi-objective optimization design through the constructed agent model. And a Pareto optimal solution set with certain robustness is obtained in combination with robust optimization design. According to the method, prior distribution is added to the weights of a neural network model, then the change conditions of the weights when data are given are obtained to measure the cognitive uncertainty in radiation shielding simulation, and the robustness of an optimization result is improved.

A radiation shield assembly is described, configured to block radiation emanating from a radiation source from reaching a user. Two shields are supported by a support arm, and are configured to rotate and translate relative to one another about the support arm's longitudinal axis. This allows the shield to be easily configured and reconfigured as necessary to visualize various parts of a patient's body via radiography. Sterile coverings are provided to ensure asepsis during a surgical procedure.

The invention discloses a liquid metal-hydrogel composite radiation protection material and a preparation method and application thereof.The preparation method comprises the steps that indium, tin and bismuth are sequentially put into a flask from low melting point to high melting point to be mixed, and glycerin is added for immersion; placing the mixture in an argon atmosphere, and stirring by using a heating type magnetic stirrer; taking out the spherical liquid metal particles from the glycerol, and finally washing and drying to obtain liquid metal alloy particles; preparing a PVA (polyvinyl alcohol)-H2O solution with the mass fraction of 15% and a PVA-DMSO (dimethyl sulfoxide) solution with the mass fraction of 15%; and a PVA-H2O solution, a PVA-DMSO solution and the liquid metal alloy particles are stirred and mixed according to the mass ratio, the mixed solution is subjected to ultrasonic treatment and then poured into a mold to be frozen into gel, and the liquid metal-hydrogel composite material is obtained. By combining the advantages of the liquid metal and the hydrogel, excellent biocompatibility, adjustable mechanical property and efficient radiation shielding capability are realized, and the hydrogel can be used as a novel lead-free radiation protection material.

A shield assembly for an intensity modulated brachytherapy (IMBT) system, has: a tubular applicator engageable to a rotating mechanism of the IMBT system, the tubular applicator having a peripheral wall enclosing an internal cavity extending longitudinally along a central axis; a radiation shield extending axially along the central axis and received within the internal cavity, the radiation shield made of an MRI-compatible and radiation attenuating material; and a radionuclide-receiving passage within the internal cavity of the tubular applicator, the radionuclide-receiving passage extending axially and being radially offset from the central axis.

The present invention provides a low electromagnetic interference target chamber for laser plasma and its system, comprising: an outer vacuum target chamber, an inner metal target chamber and a radiation shielding channel; the inner metal target chamber is fixed inside the outer vacuum target chamber through an insulating support block, and the inner metal target chamber is at zero potential; the outer vacuum target chamber comprises: a first vacuum pipe arranged in the side wall, isolating the cable of the inner metal target chamber from the outer vacuum target chamber; the radiation shielding channel is arranged inside the inner metal target chamber, one end of the radiation shielding channel is sealed and connected to the inner metal target chamber; the other end extends toward the target material direction and communicates with the inner metal target chamber; the radiation shielding channel is a metal tubular structure with a cutoff frequency. The present invention sets an inner metal target chamber so that the electromagnetic interference generated by the laser plasma is blocked by the metal inner shielding layer, which greatly reduces the electromagnetic interference to the outer vacuum target chamber.

The invention discloses a nuclear power plant secondary side cleanliness evaluation and radiation shielding method. The method comprises the following steps that S1, whole secondary circuit system equipment of a steam generator is washed; s2, full-coverage cleanliness inspection is carried out in the range from a filter screen of the electric main water feeding pump system to the secondary side of the steam generator, and meanwhile, if foreign matter is found, a cleaning tool is used for picking up the foreign matter; s3, evaluating the cleanliness condition, and if the cleanliness is qualified, ending; if the cleanliness is not qualified, returning to the step S1; s4, if the foreign matter falls off after the steam generator runs, stopping the equipment, and filling the secondary side of the steam generator with water to a preset position for reducing the radiation dose; and S5, picking up foreign matters by using a cleaning tool. Full-coverage cleanliness inspection is carried out in the range from the filter screen of the electric main feed pump system to the secondary side of the steam generator, effective verification of the secondary loop foreign matter flushing effect and radiation shielding when necessary are achieved, and foreign matter remaining on the secondary side of the steam generator is avoided.

The invention relates to an intelligent design method of a radiation shielding material based on cross-scale error feedback lock step, which comprises the following steps: determining a material component set and acquiring an atomic-scale graph structure of the material component set, and extracting intrinsic performance parameters such as heat conductivity and attenuation coefficient through an atomic-scale prediction module; and then, constructing a design variable vector in combination with a multi-physical field condition, calculating equivalent performance parameters of the composite material, establishing a cross-scale lock step mechanism, and triggering a molecular dynamics and Monte Carlo recalculation module to carry out correction when the deviation between a predicted value and a mesoscopic recalculation result exceeds a limit. Based on the correction parameters, a candidate material scheme is generated by using a multi-objective optimization algorithm; and performing gamma-ray and neutron shielding performance simulation on the candidate schemes through a Monte Carlo radiation transfer model accelerated by a deep neural network, and comparing with an experimental result to realize self-adaptive material design driven by cross-scale errors. According to the method, the design precision and efficiency of the radiation shielding material are remarkably improved.

A radiation shield assembly is described, configured to block radiation emanating from a radiation source from reaching a user. Two shields are supported by a support arm, and are configured to rotate and translate relative to one another about the support arm's longitudinal axis. This allows the shield to be easily configured and reconfigured as necessary to visualize various parts of a patient's body via radiography. Sterile coverings are provided to ensure asepsis during a surgical procedure.

Radiation shielding technologies for radioisotope battery-powered vehicles to protect computer systems and humans and increase the energy efficiency, mass efficiency, and duration capability of the vehicle during operation. A radioisotope power system includes a radioisotope power unit that emits a plurality of radiation particles. The radioisotope power system further includes a radiation shield configured to block a first radiation particle of the plurality of radiation particles. The radioisotope power system further includes a decoupling device configured to decouple the radiation shield from a vehicle. The radioisotope power unit can include one or more radioisotopes for power, propulsion, or both power and propulsion of the vehicle. The one or more radioisotopes can include an alpha emitting isotope, a beta emitting isotope, a gamma emitting isotope, or a combination thereof. The one or more radioisotopes can be for heat generation. The vehicle can be a spacecraft or an aircraft.

A system configured to reduce scatter radiation around a surgical table during a medical procedure that may include at least one radiation shield configured to be connected to a surgical table with an attachment mechanism, wherein the at least one radiation shield includes one or more adjustable radiation shield segments coupled or releasably coupled to the at least one radiation shield. A device may include a pump in fluid communication with the one or more adjustable radiation shield segments comprising a pneumatic channel that is configured to at least partially inflate the pneumatic channel such that at least a first portion of the at least one radiation shield extends vertically above at least a portion of the surgical table, wherein a second portion of radiation shield is configured to extend below the surgical table. A device may include a controller configured to activate the pump.

The invention provides a damaged fuel element storage and transportation container which comprises a storage container body, the storage container body comprises a storage barrel, an inner sleeve part and a sealing part, the inner sleeve part is arranged in the storage barrel, a plurality of storage cavities are formed in the inner sleeve part, the storage cavities are used for storing damaged elements, and the sealing part is arranged in the storage barrel; the sealing plug is arranged at the top of the storage container and is used for sealing the storage barrel; the storage container is detachably arranged in the transportation container; the device has the beneficial effects that damaged elements are stored in a sealed mode through the storage container, the storage container is stored through the transportation container, double-layer protection of the damaged fuel elements is achieved, the radiation shielding performance of the damaged fuel elements can be improved, and harm to operators in the transportation process is reduced; the protection and sealing performance of the damaged fuel element is improved, the probability of leakage of the damaged fuel element in the transportation process is reduced, and the safety of operators is improved.

The invention discloses a high-strength tungsten-boron silicone rubber radiation shielding material, which is prepared from the following ingredients in parts by weight: 100 parts of methyl vinyl silicone rubber raw rubber, 30 to 50 parts of white carbon black, 90 to 240 parts of tungsten oxide coated boron carbide heterostructure particles, 4 to 10 parts of hydroxyl silicone oil and 1 to 2.5 parts of 2, 5-dimethyl-2, 5-bis-(tert-butylperoxy) hexane. The preparation method comprises the following steps: 1, surface modification of tungsten oxide particles; 2, boron carbide surface modification; 3, grafting the surfaces of the two; and 4, mixing and vulcanizing the raw materials. White carbon black and tungsten oxide coated boron carbide heterostructure particles are introduced into the material, so that the dispersity of tungsten oxide particles in a silicon rubber matrix is improved, the interface interaction between boron carbide and the silicon rubber matrix is enhanced, the high strength of the material is ensured, and the material has excellent mechanical strength and neutron / gamma ray comprehensive shielding performance; the method is easy for mass production and can be used in the field of radiation protection.

A cryopump includes: a cryopump container defining a cryopump intake port; a cryocooler including a first cooling stage and a second cooling stage; a radiation shield thermally coupled to the first cooling stage and extending from the cryopump intake port into the cryopump container; an intake port plate thermally coupled to the first cooling stage and extending along a plane perpendicular to an axial direction, a gas inlet being formed between the intake port plate and the radiation shield; a cryopanel unit thermally coupled to the second cooling stage and disposed inside the radiation shield, a frost accommodation space being formed between the cryopanel unit and the intake port plate; and a skirt thermally coupled to the first cooling stage and extending from an outer periphery of the intake port plate into the radiation shield, a gas flow path being formed between the skirt and the radiation shield.

The invention provides a floating nuclear power platform and a radiation shielding system thereof. The radiation shielding system comprises a primary shielding structure, a combined shielding structure and a containment shielding structure, the primary shielding structure covers the outer side of a reactor pressure vessel to perform primary shielding on the reactor pressure vessel, the combined shielding structure sleeves a loop pipeline and accessory equipment thereof, and the containment shielding structure is arranged in the containment structure; the primary shielding structure comprises a first heat preservation layer wrapping the outer side of the pressure vessel shell, a shielding water tank covering the first heat preservation layer and a shielding material layer covering the outer side of the shielding water tank, and the shielding water tank is hollow to contain water. The combined shielding structure comprises a high-density alloy layer and a second thermal insulation layer; the high-density alloy layer is sleeved outside the loop pipeline and accessory equipment thereof; the second thermal insulation layer is sleeved outside the high-density alloy layer; the containment shielding structure comprises a lead plate, a polyethylene plate layer, a boron-containing polyethylene plate layer and an outer steel plate layer which are arranged in the containment structure. According to the radiation shielding system provided by the invention, the total radiation shielding weight can be reduced by 20-40% while the radiation shielding effect is guaranteed.

An antenna apparatus includes a radiation shield between an antenna element and at least one radio frequency integrated circuit (RFIC) coupled to the antenna element. An antenna substrate includes a first dielectric layer having opposite first and second surfaces, and a first metallization layer attached to the second surface to form a ground plane. A base substrate includes at least one second dielectric layer having opposite third and fourth surfaces, and a second metallization layer having a first side attached to the third surface and a second side attached to the first metallization layer to form the radiation shield. The RFIC is RF coupled to the antenna element through at least one via extending through the base substrate and a coupling element within aligned openings of the first and second metallization layers.

This invention provides an adjustable radiation shielding device for radiology departments, relating to the field of radiology. It includes a bed frame with a radiation shielding mechanism. The radiation shielding mechanism comprises a fixed part, a displacement winding part, an auxiliary rotating rail, a locking mechanism, and a radiation shielding cloth. The fixed part is rotatably connected to the bed frame. The displacement winding part extends to both sides of the bed frame. One end of the locking mechanism is on the fixed part, and the other end is on the displacement winding part. The auxiliary rotating rail is fixed to the lower end of the bed frame and presses against the displacement winding part. A sliding block slides on the bed frame and is connected to the displacement winding part. One end of the radiation shielding cloth is fixed to the fixed part, and the other end is wound around the displacement winding part. The displacement winding part rotates with the assistance of the auxiliary rotating rail to wind up the radiation shielding cloth and move it to the end of the bed frame. Through the locking mechanism, the fixed part and the displacement winding part are connected together, and under external drive, the cloth rotates to the lower end of the bed frame for storage.

Provided herein shielded radioactive storage devices including a hollow body defining an interior cavity, a first well positioned within the interior cavity, including a first well casing, and defining a first well cavity having a first well opening, the first well cavity and first well opening sized to receive a radioactive payload, a second well positioned within the interior cavity, including a second well casing, and defining a second well cavity having a second well opening, the second well cavity and second well opening sized to receive a second radioactive payload, a shield casing extending around and spaced apart from the first and second well casings to form a shielding cavity between the shield casing and the first and second well casings, and radiation shielding material filling the shielding cavity to surround the first and second well casings.

To provide a weed control base material capable of exerting stable weed control and radiation shielding functions over a long period of time, and a weed control method.SOLUTION: A weed control base material 1 is formed by kneading a base material 10 made of an inorganic porous material 11 and a plurality of plant materials 12 with a solidifying material 20, where the plant materials 11 include fibrous bodies made of a secondary crushed material of coniferous bark 11a. A weed control method includes the steps of: adding water W to the weed control base material 1 and kneading it to produce a mixed base material 1a; and laying the mixed base material 1a on a target base G and compacting it, or spraying the mixed base material 1a on the target base G.SELECTED DRAWING: None

A radiation shield assembly is described, configured to block radiation emanating from a radiation source from reaching a user. Two shields are supported by a support arm, and are configured to rotate and translate relative to one another about the support arm's longitudinal axis. This allows the shield to be easily configured and reconfigured as necessary to visualize various parts of a patient's body via radiography.

The invention discloses a multi-field coupled reactor radiation shielding design optimization method and system, and relates to the technical field of nuclear radiation shielding, and the method comprises the steps: collecting nuclear reactor information, determining constraint conditions, and building a nuclear reactor cavity and a shielding model; radiation field distribution parameters are calculated, calculation results are screened, and thermal and structural performance is combined for simulation; and parameters are trained and adjusted through a neural network model, and a shielding design scheme is optimized. According to the multi-field coupling reactor radiation shielding design optimization method, the safety and the reliability of the design scheme are improved according to the dose constraint condition screening result, the screened data are optimized and predicted through the neural network model, the precision and the robustness of the model are improved, the prediction precision and the optimization effect of the design scheme are improved, and the optimization effect of the design scheme is improved. The method has better effects in the aspects of precision, robustness and optimization effect.