1983results about "Shielding" 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 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 relates to an acid-base permeation-resistant protective glove for a glove box and a preparation method thereof, the glove adopts ethylene propylene diene monomer, butyl rubber, halogenated butyl rubber, chloroprene rubber, chlorosulfonated polyethylene rubber and other base materials to significantly improve the acid-base resistance and mechanical properties of the glove, and the glove is especially suitable for strong corrosive environments such as concentrated nitric acid and the like. The preparation method comprises a multi-step mixing process, the shielding component, the reinforcing filler and the filler are reasonably configured, and the particle size of the shielding component is controlled, so that the shielding component is uniformly dispersed in the rubber, and the permeation resistance of the glove is effectively improved. In addition, the wear-resistant furnace black, the white carbon black, the PTFE, the high-density polyethylene, the ultra-high molecular weight polyethylene and other fillers are selected, so that the glove has a higher wear-resistant grade (grade 4), and the service life is prolonged. The preparation method of the glove is simple and easy to implement, and the finished product has excellent acid and alkali permeability resistance, mechanical property, wear resistance and radiation protection property.

The invention discloses a preparation method of a polydopamine modified boron carbide-zinc methacrylate coordination reinforced rubber-based radiation protection composite material, and relates to the technical field of radiation protection materials. The method comprises the following steps: dispersing boron carbide in a triaminomethane buffer solution containing dopamine, and carrying out surface polymerization reaction to obtain polydopamine modified boron carbide; and mixing the polydopamine modified boron carbide, zinc methacrylate and a rubber matrix, and vulcanizing to obtain the polydopamine modified boron carbide-zinc methacrylate coordination enhanced (zinc is coordinated with nitrogen / oxygen and the like on the surface of the modified boron carbide) rubber-based radiation protection composite material. Through multiple effects of coordination enhancement, chemical crosslinking and the like, the material has excellent neutron shielding performance and tensile property, the preparation method is simple, the cost is low, and the material has a wide application prospect in the field of nuclear radiation protection.

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.

Disclosed is a nanosecond neutron analysis and associated particle imaging system (NNA / API) and gamma ray detector arrangement (arrangement) that uses associative element detection of titanium, iron and oxygen to determine concentrations of ilmenite or other minerals in extra-terrestrial bodies associated with He-3. The arrangement is used with a mobile carrier for mapping out concentrations of likely He-3 regions on the extra-terrestrial body.

A neutron capture therapy system includes a neutron generating device and a beam shaping assembly. The neutron capture therapy system further includes a concrete wall accommodating the neutron generating device and the beam shaping assembly and shielding radiations generated by the neutron generating device and the beam shaping assembly, the concrete wall and a reinforcing portion at least partially disposed in the concrete wall are provided to support the beam shaping assembly, and more than 90% of weight of a material of the reinforcing portion is composed of at least one element of C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S, Ca, and Ti. In the neutron capture therapy system, the reinforcing portion disposed in the concrete wall has good anti-activation performance. Therefore, compared with a conventional reinforced concrete structure, the radiation is further attenuated.

A cemented carbide body for neutron shielding and a method for producing the same, characterized in that the cemented carbide body contains WC, Fe, and Cr, the Cr being present in an amount of about 1% by mass to about 150% by mass relative to the Fe content, and the cemented carbide body contains WC grains, cementite grains, and dissolved Cr, W, and C in an Fe-based binder matrix material.

Certain embodiments are described that are directed to lead free compositions including radiation absorption metals in combination with a polymeric material. In some aspects, a composition includes at least one heavy metal, other than lead, known to have shielding capability against ionizing radiation and at least one polymer, polymer blend or co-polymer. Sheets and articles including the compositions are also described.

Embodiments of the present disclosure include an integral nuclear reactor having a core fluidly coupled to an inlet chamber and to an outlet chamber. In some instances, the nuclear reactor may include a hub to house the core, the chambers, and the protective plug. The hub may include a window allowing a heat transfer fluid to flow from the outlet chamber, through the hub, and enter an annular space between the hub and a separation shell. The heat transfer fluid may flow into an inlet of a heat exchanger. The heat transfer fluid may flow through the heat exchanger before exiting at a heat exchanger outlet. The heat transfer fluid may enter an annular delay tank before flowing down an annular downcomer duct formed by the separation shell being housed in a reactor vessel. The heat transfer fluid may flow from the annular downcomer duct and into the inlet chamber.

A mixed-spectrum molten-salt reactor has a primary containment vessel. A reactor core is housed in the primary containment vessel, the reactor core has an atypical geometry that holds a fuel salt. A blanket region is formed within the primary containment vessel and surrounding the reactor core, the blanket region comprises a blanket salt.

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.

A gas supply system suitable for a radioactive site protective gas garment comprises an external gas source and a concentric pipe switching device. An external air source is connected with the quick connector A, the quick connector A is connected with the air inlet pipe, the air inlet pipe is connected with the concentric pipe switching device through the quick connector B, and the quick connector C is connected with the concentric pipe switching device and the double-layer concentric pipe. The double-layer concentric pipe is connected with the concentric pipe switching device and is connected with the protective gas clothes through a quick connector D; the problems that in the exhaust process of an existing protective gas garment, gas is directly exhausted to a radioactive site through matched use of a one-way valve and a filtering device, when related parts break down in the exhaust process, personnel cannot judge in time, and aerosol intake causes personal injury are solved.

The preparation method of the aluminum oxide hydrogen-resistant coating on the zirconium hydride surface disclosed by the embodiment of the invention comprises the following steps: S1, plating aluminum on the surface of a zirconium hydride matrix in a magnetron sputtering manner, and forming an aluminum film on the surface of the zirconium hydride matrix; and S2, the aluminum film formed on the surface of the zirconium hydride matrix is subjected to micro-arc oxidation to obtain aluminum oxide, and the aluminum oxide hydrogen-resistant coating is obtained. Wherein an aluminum oxide film layer formed on the surface of zirconium hydride is tightly combined with a zirconium hydride matrix, and the thickness of the film layer is 5-80 microns; the aluminum oxide film layer is composed of an inner compact layer with a non-porous structure and an outer loose layer with a closed pore structure, the thickness of the compact layer is 2-15 microns, and the compact layer has a good hydrogen permeation resistance effect; the aluminum oxide film layer on the surface of zirconium hydride can serve as an aluminum oxide hydrogen-resistant coating, the hydrogen-resistant capacity of the zirconium hydride moderator is improved, and the service life of the zirconium hydride moderator is prolonged.

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 provides a reactor core structure capable of controlling an assembly clearance and a manufacturing method thereof. The reactor core structure comprises a reactor core heat management element and a filling material; wherein the base body is provided with a plurality of assembly holes; the reactor core heat management element comprises a fuel rod or a heat pipe; the reactor core heat management element is assembled in the assembly hole of the base body; the filling material is filled in an assembly gap between the reactor core heat management element and the assembly hole; and the filling material is a shape memory alloy. The reactor core structure can improve the safety margin of the heat pipe 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. Sterile coverings are provided to ensure asepsis during a surgical procedure.

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.

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.

An anti-nuclear radiation magnetic fluid sealing device includes a magnetically conductive rotating shaft, a magnetically conductive housing, a left snap ring, a left bearing, a left magnetically isolating ring, a left pole shoe, a magnetically isolating sleeve, an outer permanent magnet, an inner permanent magnet, a right pole shoe, a right magnetically isolating ring, a right bearing, a right snap ring, an end cover, an anti-radiation coating, an anti-magnetic coating, a magnetic fluid I, and a magnetic fluid II. An outer magnetic circuit and an inner magnetic circuit are formed using the magnetically isolating sleeve. The magnetically conductive housing, the left pole shoe, the outer permanent magnet, the right pole shoe, and the magnetic fluid I forms a magnetic fluid static seal. The magnetically conductive rotating shaft, the left pole shoe, the inner permanent magnet, the right pole shoe, and the magnetic fluid II form a magnetic fluid dynamic seal.

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 method for providing a neutron radiation shield includes a step (a) of providing a wall having an opening; and a step (b) of at least partially filling a space in the opening with a neutron moderator. Step (b) includes blast-injecting plastic granules into the opening with a blower device to form the neutron moderator.

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.

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 embodiment of the invention provides a self-adjusting shielding heat preservation device for a micro reactor and an operation method of the self-adjusting shielding heat preservation device, and relates to the field of nuclear reactors. The reactor comprises an outer shell, an inner shell, a control rod and a spiral flow channel, the inner shell is sleeved with the outer shell, an outer air inlet hole and an outer air outlet hole are formed in the outer shell, an inner air inlet hole and an inner air outlet hole are formed in the inner shell, a reaction cavity is formed in the inner side of the inner shell, and the spiral flow channels are arranged on the outer side of the inner shell and the inner side of the outer shell. The control rod is rotatably arranged on the side wall of the inner shell in a penetrating mode and located on the inner side of the outer shell, the control rod is provided with a control area and a non-control area, and the spiral runner is arranged between the inner shell and the outer shell; the outer gas inlet hole is used for inputting cooling gas, so that the cooling gas sequentially passes through the inner gas inlet hole, the reaction chamber, the inner gas outlet hole and the spiral flow channel and then is discharged from the outer gas outlet hole, and the cooling gas is used for flowing along the spiral flow channel and enabling the control rod to rotate so as to drive the control region to rotate into or out of the reaction chamber.