808results about "Shielding" patented technology

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 an anti-ionizing radiation fiber with high filling amount, high strength and high elasticity and a preparation method and application thereof, and belongs to the field of functional fiber materials.The preparation method comprises the steps that rare earth nitrate and citric acid are dissolved in an acidic alcohol aqueous solution, heated and stirred, the pH value is adjusted, sol is obtained, the sol is subjected to secondary heating treatment to obtain gel, and the gel is dried to obtain the high-filling-amount high-strength high-elasticity anti-ionizing radiation fiber. Aging, drying, grinding and calcining the gel to obtain rare earth composite powder; wherein the rare earth nitrate is a mixture of gadolinium nitrate, dysprosium nitrate and cerium nitrate; adding polyurethane into a mixed solution of DMF and xylene, stirring, adding the rare earth composite powder, stirring, and defoaming to obtain a spinning solution; preparing nascent fibers from the spinning solution through wet spinning; and drawing, washing and drying to obtain the anti-ionizing radiation fiber. The anti-ionizing radiation fiber prepared by the invention has excellent shielding property, mechanical property and air permeability.

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 gadolinium-containing metal-based structure and function integrated neutron shielding material which comprises a stainless steel base material and gadolinium, chromium, tungsten and tantalum which are added into the stainless steel base material, and the stainless steel base material is martensitic stainless steel. The invention also discloses a preparation method of the shielding material. The preparation method comprises the following steps: (1) preparing and mixing the raw materials according to the design proportion; (2) smelting the mixed raw materials into a cast ingot under the protection of vacuum or inert gas; and (3) the cast ingot is made into the martensitic stainless steel material through hot pressing machining. Through the mode, the gadolinium-containing metal-based structure and function integrated neutron shielding material prepared by the preparation method disclosed by the invention has excellent mechanical properties, can be used as a structural component material, is suitable for radiation shielding protection of a microminiature reactor, and can be used as a structural component material to realize integration of a structure and a neutron shielding function.

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 application relates to a neutron absorption material and application thereof to a control rod for a nuclear reactor core. The neutron absorption material provided by the application is prepared by mixing ytterbium elements and holmium elements in a certain proportion, can effectively play the high neutron capture cross-section characteristics of the ytterbium elements and the holmium elements, effectively absorb thermal neutrons, and can ensure good chemical and thermal stability, so that the neutron absorption material can maintain its structure and performance stability for a long time in a high irradiation environment, effectively avoids the conversion of the neutron absorption material into a weak neutron absorption material after absorbing neutrons, and further controls the neutron absorption characteristics of the neutron absorption material. Further, the neutron absorption material provided by the application can still ensure the neutron absorption characteristics thereof and maintain the reactivity value under high burnup depth, so as to prolong the service life of the control rod for the nuclear reactor core.

An MLC is provided, the MLC includes: a plurality of leaves; first driving mechanisms connected to the leaves and configured to drive the leaves to move to form a radiation field; and at least one leaf head mechanism mounted on at least one corresponding leaf of the leaves and configured to adjust the radiation field.

The invention belongs to the technical field of nuclear physics and particle accelerators, and relates to a high-precision wide-energy-spectrum neutron source target body structure applied to a spallation neutron source device. The method comprises the following steps: a tungsten target is adopted, and a 6cm thin target design is adopted; the cooling layer contains boron water and the like and can be used for cooling and slowing down neutrons; the moderation layer moderates the neutron energy spectrum to a thermal neutron energy region by using boron-containing water; the shielding layer is made of low-carbon steel and concrete to ensure radiation safety; the tail end of the neutron channel is connected with an experimental terminal; according to the thin target design, the energy resolution is improved, the energy resolution of neutrons below 100 keV is higher than 0.1%, and the energy resolution of neutrons below 1 MeV reaches 0.3%; the boron element reduces the gamma ray background; and the five neutron pore channels meet various requirements. The overall design realizes the effect required by the high-precision neutron experiment and improves the precision of the device.

The invention discloses a composite shielding collimator suitable for a complex mixed radiation field, belongs to the technical field of radiation shielding and measurement, and mainly solves the problems of low signal-to-noise ratio, high space background and mixed energy spectrum caused by the mixed radiation field of high-energy neutrons, gamma rays and the like in a fusion device and the problem that traditional equipment is heavy and difficult to flexibly adjust. The composite shielding collimator adopts a cylindrical shielding structure formed by aluminum oxide, boron-containing polyethylene, boron carbide and lead from outside to inside, and background interference and secondary radiation are remarkably inhibited by moderating and absorbing neutrons step by step and effectively shielding gamma rays; the neutron and gamma ray detector is integrally integrated on a rotatable supporting mechanism, unification of excellent radiation shielding performance and detection flexibility is achieved, and the neutron and gamma ray detector is mainly used for high-precision neutron and gamma ray diagnosis in complex radiation environments such as a magnetic confinement fusion device.

The invention provides an assembly construction method of a biological shielding wall of a fusion device and the biological shielding wall. The assembly construction method of the biological shielding wall of the fusion device comprises the following steps: manufacturing a wall body framework of a prefabricated sub-module; the wall body frameworks of the prefabricated submodules are assembled in the circumferential direction to obtain an annular framework of the biological shielding wall module, and the biological shielding wall module at least comprises a top shielding module used for arranging embedded parts and a bottom shielding module used for arranging the bottom of a Tokamak Dewar base and an annular support; and the annular framework is hoisted to a pouring foundation, and the interior of the annular framework is poured after hoisting is completed every time. According to the method, on-site high-altitude, high-strength and long-time complex operation is reduced, and construction safety risks are reduced. In addition, if internal parts need to be replaced or overhauled in the future, corresponding structures on the specific prefabricated submodules can be directionally dismantled, and when the service life of the fusion device is over, modular dismantling of the biological shielding wall and waste treatment are more efficient.

Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material, the interior surface of which is lined in higher temperature regions with an insulation layer of porous refractory ceramic material. A continuous insulation layer extends the length of the fuel assembly or separate insulation layer sections have a thickness increasing step-wise along the length of the fuel assembly from upper (inlet) section towards bottom (outlet) section. Fuel element positioned inward of the insulation layer and between support meshes has a fuel composition including HALEU and the form of a plurality of individual elongated fuel bodies or one or more fuel monolith bodies containing coolant flow channels. Fuel assemblies are distributively arranged in a moderator block, with upper end of the outer structural member attached to an inlet for propellant and lower end of the outer structural member operatively interfaced with a nozzle forming a nuclear thermal propulsion reactor.

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.

A nuclear reactor core includes a plurality of fuel elements and moderator blocks to form a nuclear reactor core inner portion and a nuclear reactor core outer portion. The nuclear reactor core inner portion includes an inner moderator matrix formed of a plurality of inner holes that include a plurality of inner fuel openings with one or more fuel elements disposed therein. The plurality of inner holes further include a plurality of inner coolant passages to flow a coolant. The nuclear reactor core outer portion includes an outer moderator matrix formed of a plurality of outer holes that include a plurality of outer fuel openings with one or more fuel elements disposed therein. The plurality of outer holes further include a plurality of outer coolant passages to flow the coolant. The outer coolant passage diameter exceeds the inner coolant passage diameter.

The invention provides a reactor internal capable of realizing integral movement of a reactor core, and relates to the technical field of research, development and design of reactor body structures, the reactor internal comprises a hanging basket barrel, a reactor core shroud and a reactor core; the reactor core is arranged in the reactor core shroud; the reactor core shroud is arranged in the hanging basket barrel body, the reactor core shroud is movably connected with the hanging basket barrel body, the reactor core shroud slides up and down in the hanging basket barrel body, and the bottom of the hanging basket barrel body supports the reactor core shroud. According to the invention, the material changing and maintenance efficiency can be effectively improved, the downtime is shortened, the safety is enhanced, the personnel radiation exposure risk is reduced, the inspection and maintenance are convenient, and the service life of equipment is prolonged. The system adapts to advanced reactor design and conforms to the development trend of modularization and high efficiency, and the performance, safety and economical efficiency of the nuclear reactor are remarkably improved through the design of the system.

A radiation barrier system comprising: a chemically reactive base layer; a first layer at least partially disposed above the base layer; the first layer comprising a first soil; a second layer at least partially disposed above the first layer; and the second layer comprising a second soil. The chemically active base layer is a hydro-geochemical filter barrier. The chemically active base layer mitigates soluble uranium or uranyl ion transport. The chemically active base layer filters out uranyl ions. The uranyl ions are filtered out by a process of surface adsorption to a phase added to a lithified soil composition.

Provided is an inorganic fiber or inorganic flake having excellent neutron shielding properties. A formulation composed of a base component in which SiO2 and Al2O3 are the main components (in which the total mass ratio of SiO2 and Al2O3 in the base component is 0.60 or more) and a neutron shielding component composed of at least one of gadolinium, gadolinium oxide, samarium, samarium oxide, cadmium, or cadmium oxide is prepared in a ratio of 50 to 90 parts by mass of the base component and 10 to 50 parts by mass of the neutron shielding component, and then melted, thereby obtaining a good amorphous inorganic fiber and inorganic flake.

The invention provides a radiation shielding device and a neutron capture treatment system. The radiation shielding device comprises a shielding body, a base part and a driving device, the shielding body is movably arranged on the base part; the shielding body is provided with a first position and a second position, the first position is the position where the shielding body shields the beam outlet, and the second position is the position where at least part of the shielding body does not shield the beam outlet; the driving device is connected with the shielding body, and the shielding body can be switched between a first position and a second position through the driving device. According to the technical scheme, after a patient finishes irradiation and before a worker enters a treatment room to carry out a subsequent operation process, the position of the shielding body can be adjusted and controlled to shield the beam outlet, so that the patient and the worker are prevented from being radiated, activation of other equipment in the treatment room is avoided, and the treatment efficiency is improved. And the personal safety of patients and workers and the normal operation of equipment are ensured.

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 application belongs to the technical field of control rod drive mechanism, and particularly relates to a heat insulation sleeve assembly of a magnetic lifting type control rod drive mechanism. The heat insulation sleeve assembly comprises a pipe base, a guide sleeve and a guide cover. The upper part of the pipe base is a first end, and the lower part is a second end. The radial dimension of the first end is larger than that of the second end. The lower part of the second end is provided with a first connecting end, and the guide sleeve is fixedly connected with the first connecting end of the pipe base. The upper part of the guide cover is provided with a fourth connecting end, and the lower part is provided with a horn cover. The fourth connecting end of the guide cover is fixedly connected with the second fixed end of the guide sleeve. The heat insulation sleeve assembly of the application is in a fixed state, and the problem of active wear of the heat insulation sleeve assembly is solved from the root.

The application belongs to the field of new materials, and discloses a lead-free perovskite X-ray shielding composite material and a preparation method and application thereof, and comprises the following steps: mixing ANF / DMSO dispersion liquid with ethanol to obtain re-protonated ANF dispersion liquid; mixing the re-protonated ANF dispersion liquid, CsI powder and ethanol, and stirring to obtain two portions of the same CsI / ANF dispersion liquid; mixing re-protonated ANF, Cs3Bi2I9 powder and ethanol, and stirring to obtain Cs3Bi2I9 / ANF dispersion liquid; sequentially filtering the first portion of CsI / ANF dispersion liquid, the Cs3Bi2I9 / ANF dispersion liquid and the second portion of CsI / ANF dispersion liquid by using a gel-gel method, and vacuum hot-pressing to obtain a composite gradient film with a biomimetic symmetrical structure, which is used as a lead-free perovskite X-ray shielding composite material; and the application realizes continuous and efficient X-ray shielding effect, and can improve the mechanical flexibility and thermal stability of the material.

The utility model discloses a radioactive ray isolation device in the technical field of isolation devices, which comprises a placing frame, a plurality of lead plates are welded on the surface of the placing frame, and a through groove is arranged on the surface of the placing frame; the device comprises a through groove, two lead curtains are arranged on the inner wall of the through groove, the device further comprises an installation unit and a detection unit, the installation unit is used for installing the two lead curtains on the inner wall of the through groove, and the detection unit is used for monitoring the radiation amount of radioactive substances in the through groove. According to the lifting device, the lifting frame is arranged above the two main frame bodies, and when the lifting device is used, a user can control the two electric push rods to stretch out and draw back through the controller, so that the lifting frame fixedly installed at one ends of the two electric push rods is driven to ascend and descend, and the distance between the inner wall of the lifting frame and a conveying belt below the lifting frame is controlled; and therefore, belt conveyors with different heights can be adapted.

The ray protection lead screen comprises a main protection plate, a cavity penetrating through the left side and the right side is formed in the main protection plate, extending protection plates are arranged at the left end and the right end in the cavity in a sliding mode, and a bidirectional driving mechanism is fixedly arranged on the rear side face of the main protection plate. The outer ends of the extending protection plates are rotationally connected with overturning plates through rotating shafts, and the rotating shafts are fixedly arranged at the upper ends and the lower ends of the overturning plates and rotationally connected with the extending protection plates. The cavity is formed in the main protection plate, when the extension protection plate needs to be stored, the extension protection plate can slide into the cavity of the main protection plate to be stored, the outer end of the extension protection plate is rotationally connected with the turnover plate through the rotating shaft, and the turnover plate is arranged in the cavity of the main protection plate. The first chuck is arranged at the bottom of the turnover plate, the second chuck is in clearance fit with the outer side of the rotating shaft, and the guide rod and the fastening bolt are matched, so that flexible and stable angle adjustment and fixation of the turnover plate are achieved.

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 present disclosure provides a ray protection device and a radiation inspection system. The ray protection device comprises: a mobile bearing device, including a vehicle frame and a traveling device supporting the vehicle frame to drive the vehicle frame to travel in a first direction; and a protection wall, arranged on the vehicle frame and including a movable wall which is movable relative to the vehicle frame. The movable wall has a shielding position and a retracting position; at the shielding position of the movable wall, the protection wall has first projection area in a vertical plane parallel to the first direction; and at the retracting position of the movable wall, the protection wall has second projection area in the vertical plane, where the first projection area is larger than the second projection area.

The invention relates to the technical field of spaceflight protective clothing, and provides a spaceflight titanium alloy fiber composite protective clothing and a preparation method thereof.The preparation method comprises the steps that materials are pretreated, titanium alloy fibers are sequentially subjected to surface oil removal and acid pickling activation treatment, and then the titanium alloy fibers are immersed into a specific hydrothermal reaction solution to grow ceramic whisker reinforcements in situ; meanwhile, the TC4 titanium alloy powder, the SiC fibers, the Ni-Ti shape memory alloy microwires, the ZrO2-Y2O3 temperature-sensitive ceramic particles, the self-repairing microcapsules and the flexible graphene sensor array are subjected to pretreatment such as activation, annealing and dispersion. A three-dimensional interlocking microstructure is formed through in-situ growth of single crystal aluminum oxide whiskers on the surface of the titanium alloy fiber, the three-dimensional interlocking microstructure is cooperated with the shape memory fitting effect of SMA microwires and the thermal expansion matching effect of temperature-sensitive ceramic particles, the interlayer interface bonding strength is remarkably improved, the stable performance is maintained under an extreme temperature cycle, and the temperature-sensitive ceramic fiber composite material is prepared. And the layering defect of a traditional bonding process is thoroughly overcome.

The utility model provides an electron accelerator irradiation safety protection system comprising an irradiation protection body, the irradiation protection body comprises an accelerator chamber used for placing an accelerator, and a monitoring center isolated from the accelerator chamber through an inspection channel; the inspection channel forms a U-shaped channel around the accelerator chamber; the inspection channel is communicated with the monitoring center through the first electric door, the accelerator chamber is communicated with the inspection channel through the second electric door, the first electric door and the second electric door are located at the two ends of the inspection channel respectively, direct contact between a radiation area and the outside is effectively isolated by arranging the radiation protection body, and the safety of operators is ensured; meanwhile, it is guaranteed that the flow entering the accelerator chamber from the outside is clear and orderly, and the working safety and efficiency are improved.

The invention relates to the technical field of nuclear reactor design, in particular to a safety assembly, a lead-cooled fast neutron reactor and a passive negative reactivity feedback method. The safety assembly comprises a first positioning piece, a second positioning piece and a containing piece. The first positioning piece and the second positioning piece are respectively connected with the accommodating piece so as to position the two ends of the accommodating piece in the linear direction, the accommodating piece is provided with an accommodating cavity for accommodating a coolant, and one end of the accommodating cavity in the length direction is communicated with the outside of the accommodating piece. The safety assembly is applied to the lead-cooled fast neutron reactor to serve as a safety barrier on the periphery of the reactor core, passive negative reactivity can be rapidly introduced, the structure is simple, implementation is convenient and fast, the nuclear reactor design specification and related technical requirements can be better met, and safety and reliability are further improved.

The utility model relates to the field of composite anti-radiation plates, and discloses a composite anti-radiation plate convenient to stack and splice, which comprises a main body, a splicing mechanism is arranged on the main body, the splicing mechanism comprises a splicing assembly and a locking assembly, the splicing assembly comprises a convex disc, a clamping block II, a clamping block I and a clamping block III, and the convex disc is arranged on the main body. The convex disc is fixedly connected to the right side of the main body through a fixing block, a groove is formed in the bottom end of the left side of the main body, the convex disc is matched with the groove and movably clamped to the inner wall of the groove, and a first clamping groove is formed in the top end of the main body in a left-right penetrating mode. According to the utility model, the front and back two groups of main bodies can be quickly spliced by mutually inserting and clamping the clamping block III and the other group of clamping blocks II, the four groups of main bodies can be quickly spliced by clamping the convex discs in the grooves of the other two groups of main bodies, and the multiple groups of main bodies can be quickly spliced by pushing the clamping blocks I to be matched with the round balls and the round grooves, so that the operation is convenient; extra tools are not needed for operation, and the mounting and splicing efficiency is improved.