101 |
METHOD FOR MANUFACTURING HEAVYWEIGHT AGGREGATE AND HEAVYWEIGHT CONCRETE |
US13149465 |
2011-05-31 |
US20110226163A1 |
2011-09-22 |
Minoru Yoshimoto; Yasuhide Higo; Eichi Manabe |
The invention has an object to provide a heavyweight fine aggregate and a heavyweight aggregate for a stiff heavyweight concrete having a slump of 0 to 3 cm, in which segregation from the cement paste is unlikely to occur, and to provide a stiff heavyweight concrete having a slump of 0 to 3 cm, using the heavyweight fine aggregate and heavyweight aggregate. The heavyweight fine aggregate comprises no less than 20 wt % of aggregate having a particle size smaller than 0.15 mm, and no less than 20 wt % of aggregate having a particle size from 2.5 mm to less than 5 mm. The above feature allows effectively inhibiting segregation between the aggregate and cement paste when blending the aggregate into the heavyweight concrete, and allows effectively increasing the filling rate in boxes when blending the aggregate into the heavyweight concrete for box filling. |
102 |
Insulation product, such as a thermal insulation product, and production method thereof |
US10519683 |
2003-07-09 |
US07887908B2 |
2011-02-15 |
Philippe Espiard; Bruno Mahieuxe |
The invention relates to a thermal and/or acoustic insulation product based on mineral fibers for use above 150° C., especially between 200 and 500° C., or even up to 700° C. and higher in the case of rock fibers, which comprises at least 1%, or at least 2% and even more than 4% by weight of binder obtained from a sizing composition, the resin or resin mixture of which consists substantially of at least one epoxy-type resin whose EEW value is between 150 and 2000, preferably at least 160 and/or at most 700, or even at least 170 and/or at most 300. |
103 |
Protective concrete for weakening the intensity of proton radiation |
US12448649 |
2007-07-20 |
US07819970B2 |
2010-10-26 |
Yingzhi Lv; Yingren Lv; Yan Lv; Qiang Lv; Yongsheng Gao |
Provided is a protective concrete for weaken the intensity of proton radiation, and it is prepared by mixing 525# cement 500-700 Kg; barite sand 1000-1400 kg, barite stone 1500-1800 Kg, lead powder 180-200 Kg and water 170-180 Kg. The barite that can absorb the proton radiation is used, so the present concrete is much better than conventional concretes in weakening the proton radiation, and 1.5 m-thick wall without lead plates which is prepared with the present concrete can achieve the same effect on weakening the proton radiation with a conventional 2 m-thick wall covering with lead plates. |
104 |
Borated Concrete-Rubber |
US12665241 |
2008-06-20 |
US20100258751A1 |
2010-10-14 |
Zeev Shayer |
A concrete material is disclosed according to one embodiment. The concrete material may include a mixture of cement, granular rubber and boron in various forms and ratios. The boron may include boron carbide. The rubber may be recovered rubber from used automobile and/or truck tires. Various other components may be added to the cement, such as, for example, binders, water, sand, rock, or other aggregates. Embodiments described herein may be used in radiation shielding applications, such as, for example, nuclear waste facilities, nuclear storage and/or transportation casks, nuclear power plants, medical waste facilities, illicit drug detection facilities, linear accelerator facilities, etc. |
105 |
Heavy refractory mass for the execution of radioprotection and heat accumulation barriers |
US12285175 |
2008-09-30 |
US20090293771A1 |
2009-12-03 |
Juan Manuel Caruncho Rodado |
The mass is structured on the basis of calcium aluminate cement, aggregates, water and chemical additives that modify the characteristics of the concrete. This mass uses magnetite, hematite or steel shot as an aggregate, with a highly continuous granulometry so as to achieve perfect consistency in the mass (Fuller's curve), accompanied by a high density, decisive factors for an optimum barrier effect against radiations. It can withstand high temperatures without there being any structural loss and it therefore maintains the barrier effect. The mass is suitable for producing poured concrete, concrete for bricks, and mortar, for use in the building of radioactive enclosures in which energies above 450 KeV, etc. are handled.Furthermore, prefabricated blocks of mixed mass, one of high density with great heat accumulation capacity and the other with the opposite effect, i.e. of low capacity and low conductivity, enable the prefabricated blocks to emit the thermal energy from the same faces by which they absorb it |
106 |
Heavy mass for the execution of radioprotection barriers in an X-ray environment |
US12285062 |
2008-09-29 |
US20090159852A1 |
2009-06-25 |
Juan Manuel Caruncho Rodado |
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. |
107 |
Electrically Gradated Carbon Foam |
US11964036 |
2007-12-25 |
US20080299378A1 |
2008-12-04 |
Jesse M. Blacker; Janusz W. Plucinski |
Electrically gradated carbon foam materials that have changing or differing electrical properties through the thickness of the carbon foam material and methods for making these electrically gradated carbon foam materials are described herein. In some embodiments, the electrically gradated carbon foam materials exhibit increasing electrical resistivity through the thickness of the carbon foam material such that the electrical resistivity near a second surface of the carbon foam is at least 2 times greater than the electrical resistivity near a first surface of the carbon foam. These electrically gradated carbon foam materials may be used as radar absorbers, as well as in electromagnetic interference (EMI) shielding schemes. |
108 |
Construction Composition and Method for Making a Construction Product |
US10592367 |
2004-03-12 |
US20080229978A1 |
2008-09-25 |
Robin De La Roij |
A construction composition includes: an ash in an amount of 90.0-99.9 wt. %, based on the total weight of the construction composition, wherein the ash is fly ash or bottom ash; an additive composition in an amount of 0.1-10.0 wt. %, based on the total weight of the construction composition, wherein the additive composition includes a component from group (2a) and a component from group (2b), wherein group (2a) consists of metal chlorides and wherein group (2b) consists of silica, zeolite and apatite, and wherein group (2a) includes 70.0-99.0 wt. % of the total additive composition and group (2b) comprises 1.0-30.0 wt. % of the total additive composition; and cement, in an amount of 0.0-5.0 wt. %, based on the total weight of the construction composition. With this composition, fly ash can be used as construction material, having properties comparable or better than concrete. |
109 |
Powdered material and ceramic material manufactured therefrom |
US10490628 |
2002-08-21 |
US07351281B2 |
2008-04-01 |
Leif Hermansson; Lars Kraft; H{dot over (a)}kan Engqvist; Irmeli Hermansson; Nils-Otto Ahnfelt; Gunilla Gomez-Ortega |
Powdered material, the binder phase of which mainly consists of a cement-based system, which powdered material has the capacity following saturation with a liquid reacting with the binder phase to hydrate to a chemically bonded ceramic material, preferably for dental purposes. According to the invention the powdered material has a composition and/or structure suitable for giving the ceramic material translucence in the hydrated state. The invention also relates to the ceramic material produced by hydration of the powdered material. |
110 |
Cement composite, concrete, concrete cask and method of manufacturing concrete |
US10621652 |
2003-07-18 |
US20040067328A1 |
2004-04-08 |
Hiroaki
Taniuchi; Jun
Shimojo; Yutaka
Sugihara; Eiji
Owaki; Reiko
Okamoto |
The invention provides a composite from which concrete featuring a sufficiently high heat resistance can be produced, as well as a high-safety sealed concrete cask having no opening (shielding defect) to offer high shielding performance that can prevent corrosion of an internal canister and release of radioactive material to the exterior. A concrete cask of the invention includes a cask body having a bottom but no lid in itself, and a lid which can open and close off a top opening of the cask body. Both the cask body and the lid are made of concrete manufactured by using a composite including Portland cement or blended cement containing Portland cement, which is mixed with water in such a manner that the content of calcium hydroxide falls in a range of 15% to 60% by mass after hardening through hydration reaction. Metallic heat-transfer fins are embedded in the cask body. |
111 |
Inorganic dual-layer microporous supported membranes |
US10104551 |
2002-03-22 |
US20020142172A1 |
2002-10-03 |
C.
Jeffrey
Brinker; Chung-Yi
Tsai; Yunfeng
Lu |
The present invention provides for a dual-layer inorganic microporous membrane capable of molecular sieving, and methods for production of the membranes. The inorganic microporous supported membrane includes a porous substrate which supports a first inorganic porous membrane having an average pore size of less than about 25 null and a second inorganic porous membrane coating the first inorganic membrane having an average pore size of less than about 6 null. The dual-layered membrane is produced by contacting the porous substrate with a surfactant-template polymeric sol, resulting in a surfactant sol coated membrane support. The surfactant sol coated membrane support is dried, producing a surfactant-templated polymer-coated substrate which is calcined to produce an intermediate layer surfactant-templated membrane. The intermediate layer surfactant-templated membrane is then contacted with a second polymeric sol producing a polymeric sol coated substrate which is dried producing an inorganic polymeric coated substrate. The inorganic polymeric coated substrate is then calcined producing an inorganic dual-layered microporous supported membrane in accordance with the present invention. |
112 |
Antiradiation concrete and antiradiation shell |
US09790031 |
2001-02-21 |
US20020134951A1 |
2002-09-26 |
Dieter
Vanvor |
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. |
113 |
Substrate body with a protective coating |
US09402550 |
1999-12-06 |
US06428885B1 |
2002-08-06 |
Katharina Seitz; Stephan Süssbrich; Michael Hornung; Heinrich Kühn; Frank Hiltmann |
The invention relates to a support body with a coating of at least 95% by weight titanium boride, said coating having an oxygen content of less than or equal to 1% by weight, a metallic impurities content of less than or equal to 0.5% by weight, and a specific electrical resistance of less than or equal to 10 &mgr;&OHgr;·m at room temperature. |
114 |
Process for preparing ceramic-like materials and the ceramic-like
materials |
US564204 |
1995-12-18 |
US5683616A |
1997-11-04 |
Marceli Cyrkiewicz; Erwin Herling; Jacek Kleszczewski |
This invention relates to a process for preparing ceramic-like materials with specific properties by binding an inorganic filler in the form of a dry composition with a grain size of up to 25 .mu.m containing in the volume ratio 1:0.-1.52 a waste phosphogypsum and magnetite or glass-forming oxides, with an unsaturated polyester resin in an amount of 46-220 volume parts per 100 volume parts of the filler. The use of magnetite makes it poisible to prepare materials with magnetic properties, while glass-foming oxides enable preparing materials effective to absorb an X-radiation of 45-55 keV and a hard radiation of 0.6-125 MeV. When an expanding agent is added to the raw composition according to this invention, an expanded material is obtained, having completely closed pores, particularly useful in the building industry. The resultant ceramic-like materials are characterized by good adhesion to metals, plastics, glass, wood, concrete and can be easily joined with them both at the stage of polymerization and after its termination by using a prepolymerized resin as a binder. |
115 |
Method of immobilizing toxic or radioactive inorganic wastes and
associated products |
US306515 |
1994-09-14 |
US5678233A |
1997-10-14 |
Paul W. Brown |
The present invention discloses a method of creating a monolithic wasteform consisting of a binder which chemically immobilizes heavy metals and radioactive materials so as to render them environmentally safe. An apatite or apatite-like material may be employed in immobilizing the hazardous material. A preferred practice of the invention employs a hydroxyapatite or a calcium depleted hydroxyapatite into which the waste materials are substituted and immobilized. The stoichiometric apatite or calcium deficient hydroxyapatite may be formed in the aqueous solution containing heavy metals or radioactive materials, or both, wherein binding of the latter is effected. Alternatively, a preformed calcium deficient phosphate may be introduced into the solution having heavy metals or radioactive materials, or both, dissolved therein in effecting the desired binding in situ. A high strength monolithic wasteform which may be stored or buried for long-term, safe storage of the hazardous materials is produced. |
116 |
Method for stabilizing low-level mixed wastes at room temperature |
US380922 |
1995-01-31 |
US5645518A |
1997-07-08 |
Arun S. Wagh; Dileep Singh |
A method to stabilize solid and liquid waste at room temperature is provided comprising combining solid waste with a starter oxide to obtain a powder, contacting the powder with an acid solution to create a slurry, said acid solution containing the liquid waste, shaping the now-mixed slurry into a predetermined form, and allowing the now-formed slurry to set. The invention also provides for a method to encapsulate and stabilize waste containing cesium comprising combining the waste with Zr(OH).sub.4 to create a solid-phase mixture, mixing phosphoric acid with the solid-phase mixture to create a slurry, subjecting the slurry to pressure; and allowing the now pressurized slurry to set. Lastly, the invention provides for a method to stabilize liquid waste, comprising supplying a powder containing magnesium, sodium and phosphate in predetermined proportions, mixing said powder with the liquid waste, such as tritium, and allowing the resulting slurry to set. |
117 |
Backfill for engineered barrier |
US66436 |
1993-05-25 |
US5464473A |
1995-11-07 |
Shin J. Shiao |
A backfill for an engineered barrier used to contain radioactive waste has a predetermined amount of clayic material and a predetermined amount of a reinforcement material with hydrophobic surface characteristics. The reinforcement material may include hydrophobic compounds selected from group consisting of organic polymers or inorganic materials on which a layer of hydrophobic compounds is formed. The hydrophobic reinforcement material results in the backfill maintaining a very low water permeability while providing high mechanical strength and other properties suitable for use in a repository of radioactive waste. |
118 |
Means for the conditioning of radioactive or toxic waste in cement and
its production process |
US274764 |
1988-11-22 |
US4906408A |
1990-03-06 |
Pascal Bouniol |
A process for conditioning radioactive or toxic waste which can contain boron in a cement-based matrix comprises mixing the waste in a drum in the presence of water with non-aluminous cement, aluminous cement and optionally a siliceous compound and/or a boron-containing compound, in order to form a cement matrix containing stable phases of the straetlingite, calcium monoboroaluminate and borated ettringite type and, if desired, placing around the drum a mortar layer, which can be prepared from cement, deflocculated fumed silica, siliceous sand, smectic clay and water. |
119 |
Method of producing a solid product containing cement for storing
tritium water in an accessible terminal storage facility |
US132412 |
1987-12-14 |
US4842773A |
1989-06-27 |
Willfried Kunz; Winfried Gramatte; Rolf-Erhard Schmitt; Udo Pohl |
The invention is directed to a method for producing a cement product for terminal storage of tritium water wherein activated bentonite capable of swelling is dispersingly mixed with the tritium water and the suspension obtained thereby is subjected to a swelling operation. The swollen suspension is dispersingly mixed with cement. The cured product has a water content of over 75% by weight. |
120 |
Method for coating uranium impregnated graphite with zirconium carbide |
US80381059 |
1959-04-02 |
US3865614A |
1975-02-11 |
NEWBURY RAY S; TULLY JR GEOFFREY R |
1. In a process for producing a tenacious zirconium carbide coating on graphite impregnated with uranium comprising the steps of impregnating a piece of porous graphite with uranyl nitrate dihydrate dissolved in tertiary butyl alcohol, enveloping said graphite piece in clean tertiary butyl alcohol solvent to dissolve said uranyl nitrate dihydrate impregnant from the surface of said graphite into a liquid, enveloping said graphite piece in liquid nitrogen to freeze said impregnated solution, evaporating said frozen solvent therefrom, whereby said uranyl nitrate dihydrate is deposited within said graphite pores, converting said uranium to the carbide by the application of heat, outgassing said graphite, applying a coating of finely divided zirconium suspended in liquid containing a carbonaceous binder onto said graphite surface, evaporating said liquid and converting said zirconium to the carbide by the application of heat whereby a zirconium carbide coating is obtained.
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