87results about How to "Improved Radiation Shielding Performance" patented technology

The invention provides a microscopy CT imaging device with three-free degree motion control and a correcting method thereof. The microscopy CT imaging device comprises an X-ray source (1) and an X-ray source detector (2), wherein a material-carrying table (3) is arranged between the X-ray source (1) and the X-ray source detector (2). The device is characterized in that the material-carrying table is externally provided with a driving device for driving the material-carrying table to move along the horizontal direction, the vertical direction and the rotation direction. The device solves the problems of serious shake, large error and low precision when the common microscopy CT mechanical device moves; leads the three-free degree direction motion to be more stable, the speed to be more even, and the precision degree to be higher; has better radiation shield effect; solves the problem of the heat dissipation of the X-ray source and the X-ray source detector; solves the problem that the X-ray source, the X-ray source detector and a material-rotating center are positioned at one line; and lays good foundations for the subsequent image acquisition and image reconstruction.

The invention discloses a tungsten-polymer composite material and a preparation method thereof. The tungsten-polymer composite material comprises the following components in percentage by weight: 20-100% of polymers, 950-1000% of tungsten powder, 0-50% of tungsten fibers, 0.5-5% of coupling agent and 0.5-10% of other auxiliaries, wherein the tungsten powder is prepared through airflow pulverization and surface modification. The tungsten powder disclosed by the invention is good in compaction and flowability and high in loading capacity. The composite material disclosed by the invention is good in physical and mechanical properties, and excellent in weathering resistance, chemical resistance and organic solvent resistance, not only can be applied to the field of ray shielding, but also can be applied to the fields of vibration isolation, weight counterbalance, heat conduction, weapons and ammunitions and the like.

The invention discloses a neutron-resistant radiation shield plate and a preparation method thereof. The neutron-resistant radiation shield plate comprises the following components in parts by weight: 55-94 parts of polyolefins resin, 4-43 parts of boron carbide powder, 0.5-1.5 parts of a coupling agent, 0.5-1 part of an anti-oxidant and 0.5-2 parts of lubricant. The preparation method of the neutron-resistant radiation shield plate comprises the following steps: 1) batching a composite material, wherein components are added into a high-speed batching stirrer, firstly mixture at a low speed is performed for 30 s, and then mixture at a high speed is performed for 120-180 s; 2) fundamentally pelletizing the composite material, wherein a premixed material is added into a double-screw extruder, and is subjected to smelting, extrusion, cooling, grain cutting and packing to obtain a composite material for the neutron-resistant radiation shield plate; 3) forming the plate, wherein the pelletized composite material is dried, is smelted and extruded by a single-screw extruding machine, is shaped by three-roll pressing, is stretched, drawn and cooled, and then is cut to obtain the neutron-resistant radiation shield plate.

The invention provides a super-hybrid composite laminate for neutron shield. The super-hybrid composite laminate comprises a metal plate and a fiber enhanced resin-based composite layer which are alternately laminated, wherein the fiber enhanced resin-based composite layer is prepared from basalt fiber, epoxy resin, modified boron carbide, a curing agent, a moderator and a neutron absorber. The provided fiber enhanced resin-based composite layer has excellent shielding performance and mechanical performance, has the density of 2.36-2.42 g/cm<3>, the tensile strength of 1,120-1,160 MPa, the tensile modulus of 82-85 GPa and the interlaminar shear strength of 78-85 MPa, has the <252>CF neutron source shielding factor Kf (15 mm) of 2.65-3.02 and the neutron shield rate Ath10 (10mm) of 99.88%-99.89%. The invention further provides a preparation method of the composite laminate. The preparation method is simple and convenient to operate and easy to implement.

The invention discloses a neutron shield composite material taking foam metal as a matrix and a preparation method thereof. The material comprises a foam metal matrix and a neutron shield functional filler, wherein the neutron shield functional filler comprises a neutron absorption functional filler and a neutron moderation functional filler; the neutron moderation functional filler is one or a mixture of several materials in resins such as polyethylene, polypropylene, polystyrene and the like or paraffin and water; the neutron absorption functional filler is one or a mixture of several materials in borax, boric acid, boron carbide, lithium hydride and the like; the foam metal is foam of metals such as perforated lead, aluminum, iron, copper, nickel and the like. According to the invention, the preparation method comprises the following steps of: sequentially performing high polymer heating and melting on raw materials, mixing organic fillers with inorganic fillers, pretreating the foam metal, filling the perforated foam metal with fillers, cooling, curing, and finally obtaining the product.

The invention discloses an ionizing-radiation-preventive composite material and a preparation method thereof. In the ionizing-radiation-preventive composite material, basalt fiber is high in content of heavy-nucleus elements like iron and manganese, and the heavy-nucleus elements improve absorbing and scattering effect on high-energy ionizing radiation of the basalt fiber, so that compared with other reinforced fiber, the basalt fiber has better ray shielding performance; due to special atomic energy level, rare earth oxide has strong photoelectric absorbing effect on rays of 10-80 keV, and weak absorbing area that the heavy-nucleus elements have within the range can be filled up, so that shielding performance of the basalt fiber composite material on wide-energy-range rays is improved remarkably. The rare earth oxide, a resin matrix and the basalt fiber mutually cooperate and mutually act, so that the ionizing-radiation-preventive composite material has good radiation-preventive performance and mechanical performance.

The invention discloses a radiation shielding electronic packaging material, which comprises a sintered body of a composition, wherein the composition comprises heavy metal or heavy metal compound powder serving as a radiation shielding functional component, alumina ceramic powder serving as a substrate component, a sintering aid and an adhesive. The radiation shielding electronic packaging material is prepared by the following steps: uniformly mixing the heavy metal or heavy metal compound powder, the alumina ceramic powder and the sintering aid by taking an organic solvent as a dispersion medium; mixing the adhesive into the mixture after the mixture is dried, and performing granulation to obtain composite granules; performing dry-pressing molding and high-temperature sintering. The obtained material has high ray shielding performance, particularly high X and gamma ray radiation shielding performance.

The invention relates to a high-performance nuclear radiation-shielding concrete material which is mixed by concrete, aggregate, water and the like. The radiation-shielding concrete takes the crystal water-enriched olivinite as the aggregate, so that the material is higher in crystal water content (the moisture content is 6-14%), thereby being better in neutron shielding capability. The shielding concrete for shielding the neutron ray, the shielding concrete for shielding the gamma ray, and the shielding concrete for shielding the neutron ray and the gamma ray can be prepared by changing the density of the radiation-shielding concrete. The high-performance radiation-shielding concrete contains a mass of light nucleus substances, so that the material has good characteristic in the aspect of the neutron shielding characteristic. Aiming at the problem that the current common concrete package material is heavy in weight, small in volume, and inconvenient for long-distance transportation, the concrete package material is prepared due to the characteristic that the material is enriched in the crystal water, so that the aims of weight reducing and volume enlarging can be achieved.

In a master batch containing a heat radiation shielding component, which is used to produce heat radiation shielding transparent resin forms, the master batch has as chief components a thermoplastic resin and a hexaboride represented by XB₆, wherein X is at least one selected from La, Ce, Pr, Nd, Gd, Tb, Dy, Ho, Y, Sm, Eu, Er, Tm, Yb, Lu, Sr and Ca. The hexaboride, which is a heat radiation shielding component, is contained in an amount of from 0.01 part by weight or more to less than 20 parts by weight based on 100 parts by weight of said thermoplastic resin. The use of this master batch enables simple production of heat radiation shielding transparent resin forms having a high visible-light transmission power and a high heat radiation shielding performance, without relying on any high-cost physical film formation methods.

The invention discloses a production process of anti-radiation blended yarn. The production process includes blending, by mass percentage, 60-65% of hemp fibers and 35-40% of stainless steel fibers sequentially through opening picking, cotton carding, drawing, roving and spinning. The hemp fiber and stainless steel fiber blended yarn produced by the process has the advantages that advantages of the two fibers are combined, the yarn is smooth in touch, the stainless steel fibers are evenly blended in the yarn, and the yarn has environmental protection property and functionality, such as bacteria resistance, dampness absorption and fast dry and biodegradability, of hemp fibers, and good radiation shielding effect.

The invention discloses a polyacrylic acid metal salt/boron oxide material as well as a preparation method and application thereof. The material is obtained by mixing lead acrylate, gadolinium acrylate, acrylic acid, deionized water, boron oxide and benzoin dimethyl ether serving as a photoinitiator, preparing by virtue of an ultraviolet light-induced crosslinking method at room temperature and then molding by virtue of a mold-pressing method. The composite material disclosed by the invention can be used for radiation shielding and thus gamma ray irradiation can be effectively shielded and thermal neutrons can be absorbed. Since the ultraviolet light-induced crosslinking is directly carried out by virtue of in-situ polymerization and multi-network cross-compounding of ionic and covalent bonds is performed, the prepared material is dense and lightweight, is simple in process and low in cost and has good radiation shielding effect.

The invention belongs to the field of concrete and particularly discloses low thermal micro-expansive cement based radiation shielding concrete and a preparation method thereof. The low thermal micro-expansive cement based radiation shielding concrete is prepared from the following materials in parts by weight: 280-320 parts of cement, 900-1200 parts of fine aggregates, 1200-1500 parts of coarse aggregates, 10-20 parts of a neutron absorber, 0.4-0.6 part of a water reducer and 140-160 parts of water. The concrete accords with the strength requirements for C30 concrete without the segregation phenomenon, is good in slump and divergence, has the bulk density ranging from 2800 kg.m<3> to 2900 kg.m<3>, has the 28d restrained expansion rate ranging from 0.004 percent to 0.007 percent under thewater cultivation condition, has the characteristics of excellent working performance, good radiation shielding performance, low cost and the like at the same time, solves the problems of easiness insegregation, poor homogeneity, poor construction performance and the like of the traditional radiation shielding concrete, is further beneficial to meeting the requirements for the special performanceincluding non shrinkage, micro expansion, low hydration heat and the like of the radiation shielding concrete and is very suitable for large-size radiation shielding concrete engineering.

The invention belongs to the field of concrete and in particular discloses C40 ordinary Portland cement base radiation shield concrete and a preparation method thereof. The concrete consists of the following raw materials in parts by weight: 330-370 parts of cement, 800-1000 parts of fine aggregate, 1200-1500 parts of crude aggregate, 10-20 parts of a neutron absorber, 0.5-0.7 part of a water reduction agent and 150-170 parts of water. The C40 ordinary Portland cement base radiation shield concrete disclosed by the invention meets C40 concrete strength requirements, is free of separation phenomenon, is high in collapsbillity and expansion degree, has a volume weight within 2800-2850 kg.m<3>, meets requirements of radiation shield concrete on volume weights, and meanwhile has the characteristics of being excellent in working performance, high in radiation shield property, low in cost, and the like, and problems that conventional radiation shield concrete is liable to separate, low in homogeneity, low in construction performance, and the like, can be solved.

The invention belongs to the technical field of radiation protection and relates to an ethylene propylene diene monomer flexible base neutron shielding material and a preparation method thereof. The raw materials for preparing the neutron shielding material comprise the following components in parts by weight: 50-100 parts of ethylene propylene diene monomer, 30-150 parts of a radiation-proof functional auxiliary agent, 5-14 parts of a crosslinking agent, 3-7 parts of a plasticizer, 0.4-1 part of an accelerator, 0.5-1 part of an antioxidant and 10-70 parts of a reinforcing agent. The ethylene propylene diene monomer flexible base neutron shielding material has good physical and mechanical properties, ozone and thermal oxygen aging resistance and shielding effect, and has high cost performance.

The invention provides anti-crack and anti-impact ultra-high-performance radiation-proof concrete and a preparation method thereof. The radiation-proof concrete comprises cement, a mineral admixture, nano TiO2, calcium carbonate whiskers, an expanding agent, heavy metal sludge regenerated aggregate, a water reducing agent and super absorbent resin. According to the ultra-high-performance radiation-proof concrete disclosed by the invention, the nano TiO2, the calcium carbonate whiskers and the hybrid fibers are doped to toughen a concrete material from different scales and are disorderly distributed in the concrete, and the nano TiO2, the calcium carbonate whiskers and the hybrid fibers have ultra-high tensile strength, are complementary in size range and can bridge cracks with different scales in the concrete; impact energy is absorbed when the concrete is subjected to an impact load, so that the impact toughness of the anti-radiation ultra-high performance concrete is effectively improved. The filling effect of the micro-nano scale material TiO2 and calcium carbonate whiskers can improve the compactness of the ultra-high performance concrete, and the TiO2 material itself has a strong ray shielding effect, so that the radiation protection performance of the ultra-high performance concrete can be enhanced.

The invention discloses an opaque multi-layer container with light shielding, of the type produced by blowing a preform or by injection-blowing, preferably intended to contain photosensitive substances, which includes at least two layers of thermoplastic material with opacifying materials dispersed in the layers of the thermoplastic material, said thermoplastic material being polyethylene terephthalate (PET) in all of the layers and including, in at least one of the layers, aluminium metal (Al) and a light absorbent as opacifying material dispersed in the thermoplastic matrix. The invention that is presented provides the main advantage of being able to achieve practically total protection at any wavelength of the light spectrum, with much lower filler levels than those conventionally used to date.

The invention belongs to the field of concrete and in particular discloses quick-setting and quick-hardening calcium fluoraluminate cement-based radiation-prevention concrete and a preparation methodthereof. The concrete is prepared from the following raw materials in parts by weight: 280 to 320 parts of cement, 900 to 1200 parts of fine aggregate, 1200 to 1500 parts of coarse aggregate, 10 to 20parts of a neutron absorbent, 0.4 to 0.6 part of a water reducing agent, 0.1 to 0.3 part of a set retarder and 145 to 165 parts of water. The invention provides the quick-setting and quick-hardeningcalcium fluoraluminate cement-based radiation-prevention concrete; the concrete meets the strength requirements of C30 concrete; the compressive strength within 2h reaches about 18MPa and the operabletime is greater than 30min; no segregation phenomenon occurs and the slump is relatively good; the volume weight is in a range of 2850 to 2900kg.m<3> and meets the requirements of radiation-prevention concrete on the volume weight.

Provided is a radiation-shielding glass, including a glass composition in % by mass of 10 to 35% SiO₂, 55 to 80% PbO, 0 to 10% B₂O₃, 0 to 10% Al₂O₃, 0 to 10% SrO, 0 to 10% BaO, 0 to 10% Na₂O, and 0 to 10% K₂O, in which the radiation-shielding glass has a total light transmission at a wavelength of 400 nm at a thickness of 10 mm of 50% or higher. Also provided is a radiation-shielding glass which has the similar glass composition and can be used for a gamma-ray shielding glass for a PET examination.