649 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 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.

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.

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.

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 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.

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 provides a radiation detection device and method for measuring ultra-wide-range gamma rays, and relates to the technical field of radiation detection.The radiation detection device comprises a detection assembly, a radiation shielding assembly and a signal processing assembly, and the signal processing assembly is located in the radiation shielding assembly; the detection assembly comprises three GM counting tubes with different measuring ranges and an acquisition circuit, and the acquisition circuit is used for converting signals output by the GM counting tubes into voltage counting signals; the signal processing assembly comprises a high-voltage control circuit, a power supply processing circuit, a pre-amplification circuit and a processor, the power supply processing circuit is used for converting a direct-current power supply signal and then transmitting the converted direct-current power supply signal to the high-voltage control circuit and the acquisition circuit, and the high-voltage control circuit is used for outputting a high-voltage power supply signal to each GM counting tube; the pre-amplification circuit is used for filtering and amplifying the voltage counting signals, and the processor is used for determining a target radiation dose rate according to the processed voltage signals. The radiation detection device provided by the invention has a relatively wide measuring range and relatively high measurement precision.

The invention relates to the technical field of materials for anti-nuclear radiation clothes, in particular to ethylene propylene rubber for anti-nuclear radiation clothes and a preparation method of the ethylene propylene rubber. A composite multi-walled carbon nanotube subjected to pretreatment; an accelerant; a fiber; a plasticizer; an anti-aging agent; stearic acid; through an innovative raw material formula and a corresponding preparation process, the novel ethylene propylene rubber material for the nuclear radiation prevention clothing is mainly researched and developed. In the aspect of raw materials, the radiation shielding performance of the ethylene propylene rubber is remarkably improved by introducing the specially pretreated composite multi-walled carbon nanotubes and reasonably matching the nano zinc oxide. Meanwhile, the specific dosage ratio of the ethylene propylene rubber, the accelerant, the fiber, the plasticizer and other raw materials ensures that the product has excellent shielding performance and also has good weather resistance, flexibility and comfort.

A radiation safety apparatus for a semiconductor processing system has a safety fence with a support frame and radiation shields defining containment regions associated with load ports of the semiconductor processing system. The containment regions are associated with radioactive sources that emit radioactive radiation, where radiation shields attenuate the radiation to a region external to the containment regions. The radiation shields have access doors movably coupled to the support frame to provide access to the containment regions. Interlocks are provided with the access doors to selectively lock the access doors in a closed position to control the access to the containment regions from the external region through the access doors. A controller controls the interlocks based on a radiation decay associated with each of the radioactive sources and a predetermined safe radiation exposure level.

The invention provides a radiation shielding assembly, a drug vial assembly system, a method of dispensing a drug vial assembly system, and a radiopharmaceutical infusion device. The radiation shielding assembly is used for shielding a medicine bottle assembly containing radiopharmaceuticals, and the medicine bottle assembly is provided with a puncture communication piece capable of transversely moving. The shielding body is provided with a top opening, a small bottle containing cavity and a combination port, and the medicine bottle assembly is contained in the containing cavity through the top opening. The containing cavity is provided with a circumferential matching wall, the distance between the matching wall and the vertical center line is gradually decreased from the starting end to the tail end, and a moving path is provided for assembly. The medicine bottle is guided to move along the wall, and the bottom puncture communicating piece is guided to transversely move inwards and is in butt joint with the combination port when reaching the assembly completion position. After assembly is completed, the puncture communicating piece is in butt joint with the combination port. According to the invention, only one needle puncturing the top of the medicine bottle is used as an inflow channel. Needle adjustment is not needed when medicine is nearly empty, operation is simplified, and the error rate is reduced.

The invention provides a doped yttrium hydride neutron moderation material and a preparation method and application thereof, and belongs to the technical field of radiation shielding materials. At least one of samarium, europium and gadolinium is doped in yttrium hydride in the form of hydride, and the mass ratio of metal yttrium to metal gadolinium to metal europium to metal samarium is controlled, so that the neutron moderation effect of the neutron moderation material can be improved. According to the invention, at least one of gadolinium hydride, europium hydride and samarium hydride is mixed with yttrium hydride under the protective atmosphere, so that the mass content of each element in the doped yttrium hydride neutron moderation material can be accurately controlled. According to the invention, the mixture is sintered and molded, and the sintering parameters of sintering and molding are controlled, so that the components of the mixture are sintered in a compact state, cracks generated by thermal expansion and cold contraction can be reduced, and the doped yttrium hydride keeps high density and has fewer cracks and defects.

The invention relates to a fast-charging energy transmission structure. According to the fast-charging energy transmission structure, a low-frequency MOS tube is adopted to build a full-bridge switching circuit, the two ends of a transmitting coil are electrically connected with common-mode inductors, the two ends of the transmitting coil are electrically connected with capacitance filters, and a radiation shielding mechanism is arranged on the transmitting surface side of the transmitting coil. The fast charging electric energy transmission structure adopting the low-frequency MOS tube not only can inhibit conducted interference, but also can prevent radiation interference, so that on the basis that the fast charging electric energy transmission structure can meet the working frequency requirement of a charging standard Qi2 and meet the EMC requirement, the circuit setting cost is greatly reduced, and the fast charging experience requirement of a user is met.

The invention discloses a radiation shielding method and a radiation shielding body based on a multi-physics field synergistic effect, and the radiation shielding body is used for shielding a neutron-gamma mixed radiation field, and the radiation shielding method based on the multi-physics field synergistic effect comprises the steps: a first stage, absorbing neutrons and gamma rays at a radiation initial position through a first composite material; in the second stage, energy spectrum adaptive attenuation is carried out on the first residual radiation passing through the first stage through a second composite material, and the amount of the second composite material is gradually decreased in a gradient mode in the radiation propagation direction; and a third stage of performing path scattering on the second residual radiation passing through the second stage through a third composite material. According to the invention, the technical problem of insufficient shielding capability caused by difficulty in adapting to the dynamic shielding requirement of a neutron-gamma mixed radiation field when a traditional anti-radiation shielding body faces the neutron-gamma mixed radiation field generated in a BNCT treatment scene is solved.

The present invention relates to the technical field of polymer materials, and specifically to a tungsten-containing lead-free radiation-proof rubber glove and a preparation method thereof. The present invention overcomes the disadvantages of poor radiation-proof ability and poor anti-permeability performance. After the modified ethylene propylene diene monomer rubber is plastified, an activator and an antioxidant are added for the first stage of internal mixing, then carbon black, a composite reinforcing agent, a radiation shielding powder, and a dispersant are added for the second stage of internal mixing, and finally paraffin oil is added for the third stage of internal mixing to obtain a crude mixed rubber; the crude mixed rubber, the radiation shielding powder, the dispersant, a vulcanizing agent, and a vulcanization aid are mixed and open-milled to obtain a rubber sheet; after the rubber sheet is parked, filtered, injection molded, second-stage vulcanized, cleaned, and dried, a tungsten-containing lead-free radiation-proof rubber glove is obtained. The tungsten-containing lead-free radiation-proof rubber glove prepared by the present invention has strong radiation-proof performance and strong anti-permeability performance, and is suitable for the protection of complex radiation environments.

The invention relates to the technical field of high polymer materials, in particular to tungsten-containing lead-free anti-radiation rubber gloves and a preparation method thereof. The anti-radiation fabric overcomes the defects of poor anti-radiation capability and poor anti-permeation performance. The preparation method comprises the following steps: plastifying modified ethylene propylene diene monomer rubber, adding an active agent and an anti-aging agent, carrying out first-time internal mixing, adding carbon black, a composite reinforcing agent, radiation shielding powder and a dispersant, carrying out second-time internal mixing, and finally adding paraffin oil, and carrying out third-time internal mixing to obtain a crude rubber compound; mixing the crude rubber compound, radiation shielding powder, a dispersing agent, a vulcanizing agent and a vulcanizing aid, and performing open milling to obtain a rubber sheet; and the tungsten-containing lead-free anti-radiation rubber gloves are obtained after the rubber sheets are subjected to standing, filtering, injection molding, two-stage vulcanization, cleaning and drying. The tungsten-containing lead-free anti-radiation rubber glove prepared by the invention has strong anti-radiation performance and strong anti-permeation performance, and is suitable for protection in a complex radiation environment.