1443results about "Shielding" patented technology

The invention provides anti-ionizing radiation powder with a core-shell heterogeneous gradient structure and a preparation method and application of the anti-ionizing radiation powder, and belongs to the field of radiation protection.The preparation method of the anti-ionizing radiation powder with the core-shell heterogeneous gradient structure comprises the following steps that high-atomic-number metal salt is added into deionized water, aging, washing, drying and primary calcination are conducted in sequence, and the anti-ionizing radiation powder with the core-shell heterogeneous gradient structure is obtained; a core layer is obtained; the core layer and low-atomic-number metal salt are added into deionized water, aging, washing, drying and primary calcination are sequentially conducted, and preliminary wrapping powder with the high-atomic-number metal core layer wrapped by low-atomic-number metal is obtained; and adding the preliminarily wrapped powder and rare earth salt into deionized water, and sequentially performing aging, washing, drying, primary calcining, secondary calcining, airflow crushing and air rotation purging to obtain the anti-ionizing radiation powder with the core-shell heterogeneous gradient structure. Through cooperation of the core-shell heterostructure, the high-atomic-number oxide, the low-atomic-number oxide and the multi-element rare earth element, the shielding performance of the material is remarkably improved.

A nuclear reactor is discussed herein. In some examples, the nuclear reactor may comprise an inner-core region, including liquid fuel, coolant / moderator, and a hydrogen vapor space, an out-of-core region surrounding the inner-core region, the out-of-core region including, an inner reflector adjacent to the inner-core region, the inner reflector including a first irradiation facility, and an outer reflector adjacent to the inner reflector, the outer reflector including a second irradiation facility.

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 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 discloses anti-radiation hydrogel capable of being used for interventional radiosurgery and a preparation method and application thereof.The anti-radiation hydrogel is in bridge connection with polymer chains of sodium alginate and sodium hyaluronate through the physical interaction between Fe < 3 + > and carboxyl, and the reversible interaction between Fe < 3 + > and carboxyl endows the hydrogel with the shear thinning characteristic; the injectability is ensured; the bismuth oxide nano-particles and the barium sulfate nano-particles are doped to achieve efficient attenuation of X-rays in the range of 20-100 keV, and meanwhile, the complementary K-edge absorption characteristics of the bismuth oxide nano-particles and the barium sulfate nano-particles are utilized, and the radiation absorption effect of a hydrogel network structure is combined, so that broad-spectrum radiation protection is achieved; according to the invention, acrylamide is taken as a raw material, an interpenetrating network elastic hydrogel of three polymers is formed under the action of polymerization under thermal initiation of acrylamide, the conversion from an injectable state to a solid state is realized, and at the moment, the cured hydrogel has tough mechanical properties, can also form a protective layer similar to gloves, and can be used for radiation protection in interventional operations.

The invention belongs to the field of light low-carbon concrete, and discloses hydraulic low-carbon concrete containing barium sulfate barite as well as a preparation method and application of the hydraulic low-carbon concrete. The concrete is prepared from 42.5-grade Portland cement, barium sulfate barite powder, modified polypropylene fiber, industrial waste residue lightweight aggregate, boron carbide powder, nano silicon dioxide, a polycarboxylate superplasticizer, a composite exciting agent and water according to specific parts by weight. Wherein the barium sulfate barite powder is subjected to graded proportioning and calcination activation, the modified polypropylene fiber is treated by plasma and a silane coupling agent, the industrial waste residue lightweight aggregate is formed by compounding fly ash ceramsite and steel slag microbeads, and the composite exciting agent is composed of specific components. The concrete is high in compressive strength, low in dry density, excellent in neutron shielding and gamma ray attenuation performance and low in chloride ion diffusion coefficient. The preparation method comprises the steps of premixing modification, gradient stirring, vibration compaction and steam curing. The concrete is suitable for construction of a nuclear reactor containment, a radioactive waste repository and a nuclear medicine protection wall.

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 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.

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 embodiment of the invention discloses a composite shielding plate and a preparation method thereof, and the composite shielding plate comprises a cladding which is provided with an accommodation space, and the accommodation space is in a vacuum state; the shielding material is arranged in the accommodating space; wherein the shielding material comprises a neutron moderation base material, and the cladding is made of a boron-containing metal material; or the shielding material comprises a neutron moderation base material and a neutron absorption base material, the cladding is made of a metal material, the neutron moderation base material comprises rare earth hydride, and the neutron absorption base material comprises boron-containing ceramic. The composite shielding plate provided by the embodiment of the invention not only comprises the neutron moderation base material which is high in hydrogen content and excellent in temperature resistance so as to effectively moderate fast neutrons, but also is combined with the neutron absorption base material containing boron atoms so as to efficiently absorb thermal neutrons, so that the complete neutron moderation-absorption integrated shielding performance of the composite shielding plate is realized; and stable shielding performance can be provided at the temperature of 300-1000 DEG C.

The invention relates to the technical field of radiation protection equipment, and provides a multi-scale self-adaptive fixing system for a lead plate, in the aspect of lead plate fixing, through a three-degree-of-freedom structure and a precise force control system of a shape memory alloy driving clamp, the clamping angle and force can be adjusted in a self-adaptive manner, the plastic deformation of the lead plate is effectively avoided, and the service life of the lead plate is prolonged. The problem that a traditional clamp is poor in fixing precision is solved. And due to the innovative structure of the modular quick connection assembly, the assembly and the disassembly are convenient, the seam leakage rate is greatly reduced, and the radiation protection performance is improved. In terms of environmental adaptation, the temperature and humidity cooperative control system can accurately adjust the temperature of the lead plate, and the self-repairing nano ceramic anti-corrosion coating can effectively isolate corrosion ions and automatically repair the coating. The intelligent monitoring and early warning system utilizes a multi-dimensional sensor, edge calculation and digital twinning technology to monitor the state of equipment in real time, quickly diagnose faults and perform graded early warning, so that the safe and stable operation of the system is guaranteed, and the reliability and the intelligent level of the equipment are greatly improved.

Self-adaptive fabrics for space applications are provided. In one aspect, a fabric for use in space includes a structural fabric and a plurality of synthetic fibers woven into a self-adaptive fabric. The self-adaptive fabric is attached to the structural fabric. Each of the synthetic fibers includes a plurality of hollow cells containing a trapped gas. The synthetic fibers are formed of a material having a sufficient elasticity such that the diameter of each of the synthetic fibers is configured to increase when the environmental pressure decreases.

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 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 disclosure provides a one-piece garment for protection of a wearer from radiation. The garment comprises an upper body section, a collar section and a front flap section to shield a region of thyroid, a region of torso and a region of gonad of the wearer.

The invention provides a design method and device for a biological shielding wall of a fusion device and electronic equipment. The design method of the biological shielding wall of the fusion device comprises the steps that a biological shielding occupying model is segmented in the height direction to obtain a plurality of biological shielding occupying modules, and the biological shielding occupying modules at least comprise top shielding modules used for arranging embedded parts; the bottom shielding module is used for arranging the bottom of the Tokamak Dewar base and an annular support; based on the performance indexes of the biological shielding wall, performing structural design on each biological shielding occupation module to obtain a biological shielding engineering module; and dividing each biological shielding engineering module in the circumferential direction to obtain a plurality of prefabricated sub-modules, and obtaining the biological shielding wall formed by splicing the plurality of prefabricated sub-modules. According to the method, on-site high-altitude, high-strength and long-time complex operation is reduced, the construction safety risk is reduced, and modular removal of the biological shielding wall and waste treatment are more efficient.

Insulated fuel assembly core with plurality of fuel monoliths, exhaust support plate, exhaust shield assembly, and insulation layer in which the plurality of fuel monoliths are located axially along a longitudinal axis and each of the plurality of fuel monoliths has a shape of an eccentric cylinder and a composition including a fissionable fuel component. Channels in the exhaust support plate are oriented so that propellant gas flow through the exhaust support plate does not impinge the exhaust shield assembly. The insulated fuel assembly core is manufactured by forming a tensioned fuel monolith stack mandrel assembly using mandrels spacers and internal tensioning components and forming an insulation layer on an outer surface of the tensioned fuel monolith stack mandrel assembly by mandrel winding. The insulated fuel assembly core can be incorporated into a fuel assembly of nuclear propulsion fission reactor structure of, for example, a nuclear thermal propulsion engine.

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 belongs to the technical field of heat pipe reactors, and discloses a hexagonal annular heat pipe cooling reactor, which comprises a pipe wall of a heat pipe, a silk screen wick, a steam cavity structure of the heat pipe, uranium-molybdenum alloy fuel, an outer pipe wall of the heat pipe, a wick attached to the inner wall surface of the heat pipe, and uranium-molybdenum alloy. The device is formed by coupling a hexagonal annular heat pipe with a hexagonal fuel element. Firstly, in the aspect of the structure, a framework structure composed of graphite is not needed to fix the heat pipe and the fuel element, an assembly composed of the heat pipe and the fuel element can be directly adopted for expansion to form the fuel element, and gap thermal resistance brought by the framework is eliminated. In addition, in terms of heat transfer performance, the heat transfer performance of the hexagonal annular heat pipe is superior to that of a traditional cylindrical heat pipe. The same heat transfer area is adopted, and under the condition of the same heat transfer power, the temperature of the outer surface of the pipe wall of the hexagonal annular heat pipe is lower than that of a cylindrical heat pipe. Therefore, the material stress requirement in the heat pipe pile and the thermoelectric conversion form of the condensation section can be richer.

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.

Provided is a rare earth magnesium alloy based on high-temperature and high-pressure hydrogenation and a preparation method thereof, which belongs to the technical field of alloy materials. In the present disclosure, a microstructure of a rare earth magnesium alloy is regulated based on high-temperature and high-pressure hydrogenation to significantly improve the plasticity of the rare earth magnesium alloy. A similar microstructure can also be achieved in other high-gadolinium (Gd) and high-yttrium (Y) systems. The present disclosure provides a unique approach to enhance the plasticity of a magnesium alloy, and makes it more likely to regulate the mechanical properties of such a rare earth alloy subsequently through other deformation processes. The rare earth magnesium alloy based on high-temperature and high-pressure hydrogenation can be used for neutron-shielding, and is a material with a structure-function integrated design that can be used in the nuclear energy field and space field.

The invention discloses a boron-reinforced cement-based radiation refrigeration composite material and a preparation method thereof, and belongs to the technical field of building materials.During preparation, Portland cement, ceramic micro powder and other powder are evenly mixed to obtain mixed powder; uniformly mixing the mixing water with the mixed powder, and fully stirring to obtain slurry; hardened cement paste with directional pores is obtained through an ice template method, and the boron-reinforced cement-based radiation refrigeration composite material is obtained after the hardened paste is subjected to high-temperature treatment. According to the preparation method, freezing forming and high-temperature treatment of an ice template method are combined, so that the radiation refrigeration capacity is obviously improved, the problem of insufficient material strength caused by freezing forming is avoided, and the prepared composite material has relatively high radiation refrigeration capacity and compressive strength.

The invention provides a homogeneous composite material, a composite material system, a stacking structure and a radiation protection material design method, and relates to the technical field of space radiation protection materials.The homogeneous composite material is prepared from, by mass, 10-30% of epoxy resin, 10-90% of bismuth trioxide and the balance polyethylene and boron nitride which are equal in mass fraction. According to the invention, the radiation protection material with radiation resistance and light weight can be designed.