Abstract: There is provided a neutron shielding material which has heat resistance and has ensured neutron shielding performance even in a high-temperature environment during storage of a spent nuclear fuel for high burnup. A neutron shielding material having improved heat resistance and ensured neutron shielding performance due to the absence of an amine curing agent is provided by a neutron shielding material composition comprising a polymerization initiator, a polymerization component, a density increasing agent and a boron compound. As the polymerization component of the present invention, an epoxy component and an oxetane component are particularly preferably used.

Abstract: A neutron shield material that exhibits high heat resistance and ensures neutron shielding capacity. A composition for neutron shield material excelling in heat resistance and ensuring neutron shielding capacity is provided by comprising a hydrogenated bisphenol type epoxy of the formula: (1) (wherein each of R1 to R4 is independently selected from the group consisting of CH3, H, F, Cl and Br, and n=0 to 2), a hardening agent component having at least one cyclic structure and two or more amino groups, a density increasing agent and a boron compound.

Abstract: Moldable neutron sensitive compositions containing an inorganic scintillating component, and neutron capture component, and a moldable resin component, are described. They are prepared with optimized compositions for maximized thermal neutron sensitivity. Methods for preparing such compositions, and articles and radiation detectors made from them are described as well.

Abstract: A composite material includes lithium hydride particles dispersed within lithium to form a lithium-lithium hydride composite. The lithium-lithium hydride composite has increased strength over pure lithium and similar soft X-ray transmission characteristics as pure lithium. A soft X-ray blast window may be made from the lithium-lithium hydride composite with increased reliability and cost effectiveness. A method for making a composite material includes dispersing lithium hydride into lithium metal using a variety of dispersion techniques.

Abstract: The invention relates to a method for producing metal salt nanogel-containing aqueous dispersions, solid intermediate products and waterproof plastic products, thus allowing the simple production of novel products having homogeneously distributed agents, which exhibit, for example, an antimicrobial or barrier effect and/or have an absorbing capacity, such as with respect to oxygen, humidity, chemical, particularly gaseous compounds, or electromagnetic or radioactive radiation.

Abstract: An article and thermoplastic composition including polycarbonate, a polysiloxane-polycarbonate and an x-ray detectable or metal detectable agent having good magnetic permeability and/or electrical conductivity wherein the composition may be used in articles for food preparation. The thermoplastic compositions are useful in forming molds for manufacturing a food product, such as chocolate molds.

Abstract: A composition for radiation shielding or range of compositions which compositions may be used for a variety of radiation shielding applications. With proper adhesive selection and processing, the construction forms an integral bond with the craft as compatible adhesives form strong bonds. This eliminates the potential for delaminating associated with the use of metallic layered shielding. While prior art protects electronics with a direct coating to electronic packages, this approach allows larger equipment systems, such as optics, or spectrometers, to be shielded.

Abstract: Disclosed is a radiation shielding member having improved radiation absorption performance, including 80.0˜99.0 wt % of a polymer matrix or metal matrix and 1.0˜20.0 wt % of a radiation shielding material in the form of nano-particles having a size of 10˜900 nm as a result of pulverization, wherein the radiation shielding material is homogeneously dispersed in the matrix through powder mixing or melt mixing after treatment with a surfactant which is the same material as the matrix or which has high affinity for the matrix. A preparation method thereof is also provided. This radiation shielding member including the nano-particles as the shielding material further increases the collision probability of the shielding material with radiation, compared to conventional shielding members including micro-particles, thus reducing the mean free path of radiation in the shielding member, thereby exhibiting superior radiation shielding effects.

Abstract: Radiation structures formed from a composition including calcium silicate, magnesium or calcium oxides and an acid phosphate are provided. The composition may also include fly ash or kaolin with or without the calcium silicate.

Abstract: A bismuth compound composite having a polymer matrix and a bismuth compound therein. The bismuth compound may be bismuth oxide, or other bismuth compounds. The polymer may be any of a very wide range of materials or combinations thereof. Binder, secondary fillers or other third components may be added. By means of use of various bismuth compounds, polymers, and third components, the physical, radiological and electrical properties of the finished products may be tailored to achieve desired properties. In addition, the invention teaches that radiation shielding, insulators, and combined radiation shield/insulators may be fashioned from the composite. A wide range of production methods may be employed, including but not limited to liquid resin casting.

Abstract: Apparatus and methods according to various aspects of the present invention may operate in conjunction with composite matrix material and reinforcement material, such as nanostructures. The nanostructures may be evenly dispersed and/or aligned in the matrix material through application of an electromagnetic field, resulting in a nanocomposite material. In one embodiment, the nanocomposite material is suitable for large scale processing.

Abstract: A metal x-ray device component is provided that includes a high emissivity inorganically bonded ceramic coating that can be applied with minimal surface preparation and that provides good resistance to corrosion and oxidation of substrates in high temperature, vacuum environments. The coating has good dielectric properties, is stable in the high temperature, vacuum environment characteristic of x-ray devices, and provides effective and reliable performance over a wide range of operating temperatures.

Abstract: A high voltage insulator and radiation shield made of barium sulfate composite having a polymer matrix and barium sulfate therein. The device may be made by casting. By means of use of various combinations of barium sulfate, other radiologically resistant materials, polymers, and third components, the physical, radiological and electrical properties of the finished products may be tailored to achieve desired properties. In addition, the invention teaches that radiation shielding, insulators, and combined radiation shield/insulators may be fashioned from the composite. A wide range of production methods may be employed, including but not limited to liquid resin casting.

Abstract: Lightweight and rigid, leaded or lead-free integral radiation shielding structural compositions comprising two or more radiation attenuating elements or compounds thereof, selected for having compatible radiation attenuating characteristics, dispersed in a thermoplastic or thermoset resin. The radiation shielding structural compositions of the present invention can be used to functionally and structurally replace lead-lined structures in medical and industrial x-ray systems. The radiation shielding structural compositions of the present invention can also be formulated to minimize the density of the resulting structure.

Abstract: An electromagnetic-wave suppressing material is provided. The electromagnetic-wave suppressing material includes an ionic liquid and nanometer-order particles mixed with the ionic liquid, where 10 wt % or more of the nanometer-order particles is mixed with respect to 100 wt % of the ionic liquid.

Abstract: Techniques and compositions are provided for shielding radioactive energy. The composition includes a hydrocarbon component and a radiation shielding and absorbing material or additive. The composition may be applied to substrates or to radioactive materials. Moreover, the composition may be mixed with raw materials of products.

Abstract: Specially designed to form a high capacity barrier for radioprotection in the X-ray range, a mass for producing mortar, bricks, blocks or tiles, involving the incorporation of cement, aggregate, water and chemical additives varying in accordance with the features that may be required for this mass, such as strength, setting time and others, the invention focuses its characteristics on the fact that, as an aggregate barite plays a part in it in a suitable proportion according to the increase in the general density of the mass to be obtained, a highly continuous grain size being envisaged for said barite as well as a system of differential vibrating, except in the case of the mortar, with a view to obtaining optimal consistency in the mass.

Abstract: An electric wire and cable according to the present invention comprises a sheath made of a radiation-resistant non-halogen flame-retardant resin composition in which the radiation-resistant non-halogen flame-retardant resin composition includes one to 30 parts by weight of aromatic amine antioxidant with a melting point of 40° C. or higher and 50 to 300 parts by weight of metal hydroxide blended into 100 parts by weight of ethylene polymer.

Abstract: The invention concerns a neutron shielding material for maintaining sub-criticality based on unsaturated polymer: Said material comprises an unsaturated polyester resin, at least an inorganic boron compound, and at least a hydrogenated inorganic compound, in amounts such that the boron concentration is 4.1021 to 25.1021 atoms per cm3 and the hydrogen concentration is 3.1022 to 5.5.1022 atoms per cm3.

Abstract: A composition for shielding living tissue from cosmic radiation exposure during air and space flights, using polyhedral oligomeric silsesquioxanes incorporating metals with high neutron capture cross-sections. Methods for incorporation of such compositions into textiles, garments, and skin lotions are described.

Abstract: Techniques and compositions are provided for shielding radioactive energy. The composition includes a hydrocarbon component and a radiation shielding and absorbing material or additive. The composition may be applied to substrates or to radioactive materials. Moreover, the composition may be mixed with raw materials of products.

Abstract: Techniques and compositions are provided for shielding radioactive energy. The composition includes a hydrocarbon component and a radiation shielding and absorbing material or additive. The composition may be applied to substrates or to radioactive materials. Moreover, the composition may be mixed with raw materials of products.

Abstract: The invention relates to a material for neutron shielding and for maintaining sub-criticality, and a process for preparation of this material and applications of the said material. The material comprises a matrix based on a vinylester resin, at least one polyamide and an inorganic filler capable of slowing and absorbing neutrons. Applications: manufacturing of neutron shields in packagings for transport, interim storage and/or ultimate storage of radioactive materials, particularly packagings for new nuclear fuels.

Abstract: Disclosed herein is a composition comprising an organic polymer composition that comprises an organic polymer that has a refractive index of about 1.60 to about 1.66; and an xray absorbing filler composition that comprises barium sulfate that has been annealed to a temperature of about 500 to about 1,500° C. Disclosed herein too is a method for manufacturing a composition comprising annealing barium sulfate to a temperature of about 500 to about 1,500° C. to form annealed barium sulfate; and blending an organic polymer composition with the annealed barium sulfate; wherein the organic polymer composition comprises an organic polymer that has a refractive index of about 1.60 to about 1.66.

Abstract: The present invention provides a mixture containing a) at least 26 wt. % of gadolinium and b) one or more elements, alloys and/or compounds from the group consisting of barium, indium, tin, lanthanum, molybdenum, niobium, tantalum, zirconium and tungsten, a process for the preparation of this mixture, use of the mixture as radiation protection, use of the mixture to prepare polymeric radiation protection substances, a process for preparing radiation screening rubbers, thermoplastic materials and polyurethanes, a process for preparing products from the polymeric radiation protection substances and products made from these polymeric radiation protection substances.

Abstract: A composite for providing shielding against cosmic radiation, consisting essentially of carbon nanotubes, a biopolymer of lignin and a halogen as dopant.

Abstract: A radiation protection material for the screening of X- and/or gamma-rays is made from a film-like multi-layer composite material, in which radiation absorbing particles are dispersed. The composite material comprises at least one support layer and a radiation absorbing layer, whereby the radiation absorbing layer comprises a hardening polymeric preparation, which can flow in the working state and with an effective lead content of ?15%.

Abstract: The present invention provides a mixture containing a) at least 26 wt. % of gadolinium and b) one or more elements, alloys and/or compounds from the group consisting of barium, indium, tin, lanthanum, molybdenum, niobium, tantalum, zirconium and tungsten, a process for the preparation of this mixture, use of the mixture as radiation protection, use of the mixture to prepare polymeric radiation protection substances, a process for preparing radiation screening rubbers, thermoplastic materials and polyurethanes, a process for preparing products from the polymeric radiation protection substances and products made from these polymeric radiation protection substances.

Abstract: A composite material includes lithium hydride particles dispersed within lithium to form a lithium-lithium hydride composite. The lithium-lithium hydride composite has increased strength over pure lithium and similar soft X-ray transmission characteristics as pure lithium. A soft X-ray blast window may be made from the lithium-lithium hydride composite with increased reliability and cost effectiveness. A method for making a composite material includes dispersing lithium hydride into lithium metal using a variety of dispersion techniques.

Abstract: The present invention provides radioprotective materials and products produced using the materials, the materials and products being easily usable for blocking the effects of radiation, exposure to which occurs unconsciously in daily life or in the working environment. Specifically stated, the present invention provides radioprotective materials comprising at least one member selected from the group consisting of collagens, keratins, silk fibroins and their derivatives. The present invention also provides radioprotective products produced using the radioprotective materials.

Abstract: A urethane based polymer composition is provided that exhibits superior shielding properties during and after exposure to high level radiation. The composite is formed by mixing a liquid isocyanate monomer, preferably 4,4?-diisocyanate monomer with a liquid phenolic resin, preferably phenol formaldehyde resin, and a phosphate ester flame retardant. An optional pyridine catalyst may be added to shorten the cure time. The resulting composition cures at room temperature and can be utilized in several manners, including spraying or pouring the composition prior to curing over radioactive material to prevent leakage of radiation. The uncured composite can be sprayed on the walls of a room or container to prevent leakage of radiation and can also be used to contain radiation prior to demolition. The uncured composite can also be molded into bricks or panels for use in construction.

Abstract: A cask includes a trunk body that includes a basket having a square pipe or a plate member forming a cell that contains a spent fuel assembly, and a neutron shield that is formed by filling a composition for neutron shielding between the trunk body and an outer cover surrounding the trunk body. The composition includes a refractory material, a density increasing agent, and a neutron shielding material composed mainly of a polymer.

Abstract: A method of controlling or containing radioactive contamination by providing a neutron absorbing material to a radioactive contamination site. Preferably the neutron absorbing material is present as a powder, granule, slurry or suspension, allowing the neutron absorbing material to blanket cover the radioactive contamination site. Suitable neutron absorbing materials include lanthanide elements having a cross section of 100 Barns or greater, as well as hafnium, zirconium, tantalum, silver, indium, and hydrogen.

Abstract: This invention deals with multi-component composite materials and techniques for improved shielding of neutron and gamma radiation emitting from transuranic, high-level and low-level radioactive wastes. Selective naturally occurring mineral materials are utilized to formulate, in various proportions, multi-component composite materials. Such materials are enriched with atoms that provide a substantial cumulative absorptive capacity to absorb or shield neutron and gamma radiation of variable fluxes and energies. The use of naturally occurring minerals in synergistic combination with formulated modified cement grout matrix, polymer modified asphaltene and maltene grout matrix, and polymer modified polyurethane foam grout matrix provide the radiation shielding product. These grout matrices are used as carriers for the radiation shielding composite materials and offer desired engineering and thermal attributes for various radiation management applications.

Abstract: This invention relates to a composite material for neutron shielding and maintenance of sub-criticality comprising a matrix based on vinylester resin and an inorganic filler capable of slowing and absorbing neutrons. The vinylester resin may be an epoxymethacrylate resin and the inorganic filler may contain a zinc borate and an alumina hydrate or magnesium hydroxide.

Abstract: An improved radiation shielding material and storage systems for radioactive materials incorporating the same. The PYRolytic Uranium Compound (“PYRUC”) shielding material is preferably formed by heat and/or pressure treatment of a precursor material comprising microspheres of a uranium compound, such as uranium dioxide or uranium carbide, and a suitable binder. The PYRUC shielding material provides improved radiation shielding, thermal characteristic, cost and ease of use in comparison with other shielding materials. The shielding material can be used to form containment systems, container vessels, shielding structures, and containment storage areas, all of which can be used to house radioactive waste. The preferred shielding system is in the form of a container for storage, transportation, and disposal of radioactive waste. In addition, improved methods for preparing uranium dioxide and uranium carbide microspheres for use in the radiation shielding materials are also provided.

Abstract: A urethane based polymer composition is provided that exhibits superior shielding properties during and after exposure to high level radiation. The composite is formed by mixing a liquid isocyanate monomer, preferably 4,4′-diisocyanate monomer with a liquid phenolic resin, preferably phenol formaldehyde resin, and a phosphate ester flame retardant. An optional pyridine catalyst may be added to shorten the cure time. The resulting composition cures at room temperature and can be utilized in several manners, including spraying or pouring the composition prior to curing over radioactive material to prevent leakage of radiation. The uncured composite can be sprayed on the walls of a room or container to prevent leakage of radiation and can also be used to contain radiation prior to demolition. The uncured composite can also be molded into bricks or panels for use in construction.

Abstract: A urethane based polymer composition is provided that exhibits superior shielding properties during and after exposure to high level radiation. The composite is formed by mixing a liquid isocyanate monomer, preferably 4,4′-diisocyanate monomer with a liquid phenolic resin, preferably phenol formaldehyde resin, and a phosphate ester flame retardant. An optional pyridine catalyst may be added to shorten the cure time. The resulting composition cures at room temperature and can be utilized in several manners, including spraying or pouring the composition prior to curing over radioactive material to prevent leakage of radiation. The uncured composite can be sprayed on the walls of a room or container to prevent leakage of radiation and can also be used to contain radiation prior to demolition. The uncured composite can also be molded into bricks or panels for use in construction.

Abstract: A high-polymer neutron shielding material which scarcely reduces the hydrogen number density when exposed to a high temperature of 150 to 200° C. for a long time period A heat-setting type epoxy resin is employed. The base resin is selected from various epoxy resins such as bisphenol A type epoxy resin. The hardener is selected from alicyclic polyamine, polyamide amine, aromatic polyamine, acid anhydride, and so on. These materials are mixed and hardened at a temperature higher than the room temperature. To give a flame resistance to the hardened resin, a fire retardant such as magnesium hydroxide is added to the mixture. To improve the neutron shielding performance of the hardened resin, a neutron absorbing material is added to the mixture. Further, to increase the moderating performance, hydrogenated bisphenol A epoxy resin is used as the base resin or metal hydride or hydrogen absorbing alloy is added.

Abstract: There is disclosed a composition which is layered in a reflective board to constitute a radio wave absorber. In this composition, an electroconductive titanium oxide is compounded with a substrate. With regard to the substrate, there may be used thermoplastic resin, thermosetting resin, rubber or elastomer.

Abstract: The present disclosure relates to an organic anti-reflective coating composition and a method for forming photoresist patterns using the same. The anti-reflective coating compositions are useful for preventing reflection of a lower film layer or a substrate of a photoresist film, reducing standing waves caused by light and variations in the thickness of the photoresist itself, and increasing the uniformity of the photoresist patterns. More particularly, the present invention relates to an organic anti-reflective coating composition comprising particular organo-silicon based polymers and a method for forming photoresist patterns using the same. The organic anti-reflective coating composition can prevent excessive absorbency of an anti-reflective film formed therefrom and, thus, minimize the reflectivity of the film so that it can efficiently remove standing waves and increase the uniformity of the photoresist pattern.

Abstract: Metal Nanoshells having partial coverage of a substrate or core particle and methods of making them are provided. A method of making a partial metal nanoshell preferably includes asymmetrically confining a substrate particle and selectively layering a metallic material over the substrate particle according to the asymmetry. Confining the substrate particle may include attaching it to a support defining an exposed portion and a contact portion. The method may include either chemically modifying the substrate particle. The solid angle of coverage of the partial metal nanoshell may be influenced by the nature of the chemical modification, such as alternatives of activating and passivating the exposed portion.

Abstract: A first antiradiation concrete includes a metallic aggregate having a grain size of up to 7 mm, and at least 5.0% by weight, in particular at least 7.8%, of a boron-containing aggregate having a grain size of up to 1 mm and being finer-grained than the metallic aggregate. A second antiradiation concrete includes a boron-containing aggregate having a grain size of up to 1 mm, and between 80 and 90% by weight, in particular 85 to 89%, of a metallic aggregate having a grain size of up to 7 mm. For the second concrete, the boron-containing aggregate is between 1.0 and 1.5% by weight. To achieve a shielding action that absorbs as much heat and radiation as possible, an antiradiation shell (2) has a wall region (2a to 2z) formed from the first or second antiradiation concrete where each has a boron-containing aggregate with a grain size up to 1 mm and a metallic aggregate grain size up to 7 mm.

Abstract: The radiation shielding composition and method of the present invention relate to a conformal coating material composed of a matrix of densely packed radiation shielding particles, which are disbursed within a binder. The shielding composition is applied to objects to be protected such as integrated circuits, or to packages therefor, as well as for protecting animals including humans from unwanted exposure to radiation in outer space or other environments.

Abstract: A high-polymer neutron shielding material which scarcely reduces the hydrogen number density when exposed to a high temperature of 150 to 200° C.

Abstract: Disclosed is a composition of matter comprising a tributyl phosphate complex of a group 3, lanthanide, actinide, or group 13 salt in an organic carrier and a method of making the complex. These materials are suitable for use in solid or liquid organic scintillators, as in x-ray absorption standards, x-ray fluorescence standards, and neutron detector calibration standards.

Abstract: An epoxy resin composition which is cured transparent product having high neutron shielding capability, comprised by an epoxy resin without any not transparent inorganic substances and a hardener and characterized by said composition's viscosity at ambient temperatures is below 7000 mPa·s and said composition is curable at said temperatures.

Abstract: The radiation shielding composition and method of the present invention relate to a conformal coating material composed of a matrix of densely packed radiation shielding particles, which are disbursed within a binder. The shielding composition is applied to objects to be protected such as integrated circuits, or to packages therefor, as well as for protecting animals including humans from unwanted exposure to radiation in outer space or other environments.

Abstract: An improved nuclear shielding material that is flexible so as to effectively fill voids in radiation containment structures. Under very high temperatures the material is designed to undergo pyrolysis and transform into a strong ceramic material. The material contains a number of components, the first of which is a polymeric elastomer matrix such as a two part self-polymerizing system like RTF silicone rubber. Additional components include: a compound to shield gamma radiation like tungsten carbide powder, a neutron absorbing/gamma blocking compound such as boron carbide powder, a heat conducting material such as diamond powder, a high temperature resistant compound such as silicon dioxide powder, a second neutron absorbing compound which also imparts electrical conductivity, namely barium sulfate powder, and a hydrogen gas surpassing component which readily absorbs hydrogen such as sponge palladium.

Abstract: A new gamma-ray stabilizer comprising a combination of 100 parts by weight of a benzyl compound (A) having a specific chemical structure and 0.01 to 10 parts by weight of a pentaerythritol phosphorous ester (B) having a spirocyclic structure. Said stabilizer is preferably blended in such a manner that said (A) is contained in an amount of 0.01 to 10 parts by weight based on 100 parts by weight of a thermoplastic polymer (polycarbonate or the like), and said (B) is contained in an amount of 0.01 to 1 part by weight based on 100 parts by weight of said (A).