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Class 423/5 - Fusing


Subclass of Class 423 - Chemistry of inorganic compounds
Definition: Processes in which the treatment includes the step of melting
No. of patents: 39
Last issue date: 01/29/2008


NumberTitleIssue Date
7323032Pyrochemical reprocessing method for spent nuclear fuel
This invention is provided for improvement of corrosion-resistant property of a crucible and for promotion of safety in a pyrochemical reprocessing method for the spent nuclear fuel. The spent nuclear fuel is dissolved in a molten salt placed in the crucible. In a p...
01/29/2008
7052661Method for abatement of mercury emissions from combustion gases
A process for removing mercury from a feed of coal, heavy oil or other mercury contaminated material is disclosed. The feed is thermally decomposed, preferably within, or above, a molten metal bath under reducing conditions, to produce a vapor product and non-vapor ...
05/30/2006
6461576Pyroprocess for processing spent nuclear fuel
This is a pyroprocess for processing spent nuclear fuel. The spent nuclear fuel is chopped into pieces and placed in a basket which is lowered in to a liquid salt solution. The salt is rich in ZrF4 and containing alkali or alkaline earth fluori...
10/08/2002
6325986Method for reducing hydrogen chloride emissions from air-blown asphalt
In a method for reducing hydrogen chloride emissions from an asphalt air-blowing process, an asphalt is subjected to an air-blowing process where air is bubbled through hot asphalt to raise the softening point of the asphalt. The fumes from the air-blowin...
12/04/2001
6080224Method for processing waste containing metal contaminants using a reducing agent
The invention relates to a method for processing waste that contains contaminants. The contaminants may be metals modified by carbon, oxygen, phosphorus, or sulfur. The waste in the form of a powder is mixed with an ionic reducing agent in an inert liquid...
06/27/2000
5819158Reclamation of tungsten values from tungsten-thoria
A simple, cost effective method for reclaiming tungsten values from tungsten-thoria has been invented. The method involves reacting the tungsten-thoria with molten sodium hydroxide to form a soluble sodium tungstate and an insoluble residue of thoria, coo...
10/06/1998
5735932Process for the conversion of uranium oxide to uranium metal and uranium alloys
A process for preparing uranium metal or alloy thereof suitable for use in a metal-based uranium enrichment plant or other use requiring a superdense metal comprising providing a molten metal bath containing the alloy metal and feeding uranium oxide and a...
04/07/1998
5732366Method of reprocessing metal parts radioactively contaminated with uranium
A method for reprocessing metal parts that are radioactively contaminated with uranium includes smelting the metal parts so that a melt and a slag are formed. U235 -depleted uranium is admixed with the metal parts and/or the melt and/or the sla...
03/24/1998
5724669Metal decontamination process and systems for accomplishing same
The present invention provides for methods for on-line monitoring of a molten process phase to determine the extent of extraction of radioactive species from a waste metal contaminated with the radioactive species. The waste metal is mixed with an inorgan...
03/03/1998
5457264Method of melting treatment of radioactive miscellaneous solid wastes
A method of melting treatment of radioactive miscellaneous solid wastes containing therein an electrically conductive substance and other waste components. This method comprises charging the radioactive miscellaneous solid wastes into a cold crucible indu...
10/10/1995
5380406Electrochemical method of producing eutectic uranium alloy and apparatus
An apparatus and method for continuous production of liquid uranium alloys through the electrolytic reduction of uranium chlorides. The apparatus includes an electrochemical cell formed from an anode shaped to form an electrolyte reservoir, a cathode comp...
01/10/1995
5358549Method of indirect chemical reduction of metals in waste
An environmentally sound process is described for the remediation of waste materials that allows the separation, recovery and decontamination of metals. The method includes chemically reducing essentially all of a reducible toxic and potentially hazardous...
10/25/1994
5322547Method for indirect chemical reduction of metals in waste
An environmentally sound process is described for the remediation of waste materials that allows the separation, recovery and decontamination of metals. The method includes chemically reducing essentially all of a reducible toxic and potentially hazardous...
06/21/1994
5322545Method of producing uranium metal
Uranium chloride is reacted with either magnesium, sodium or calcium in the presence of a molten salt comprising light metal chlorides including lithium chloride. The temperature is maintained below the melting point of uranium. The magnesium may be in th...
06/21/1994
5290337Pyrochemical processes for producing Pu, Th and U metals with recyclable byproduct salts
In the pyrochemical reduction of uranium dioxide or other actinide metal oxides by reaction with magnesium, magnesium oxide byproduct is produced. The use of a salt flux comprising magnesium chloride and a rare earth element trichloride such as neodymium ...
03/01/1994
5202100Method for reducing volume of a radioactive composition
A method is disclosed for reducing the volume of a radioactive composition by separating a radioactive first component from a second component of the radioactive composition. The method includes directing the radioactive composition into a reaction zone. ...
04/13/1993
5160367Salt transport extraction of transuranium elements from lwr fuel
A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl2 and a Cu--...
11/03/1992
5147616Magnesium transport extraction of transuranium elements from LWR fuel
A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl2 and a U-Fe...
09/15/1992
5141723Uranium chloride extraction of transuranium elements from LWR fuel
A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels containing rare earth and noble metal fission products as well as other fission products is disclosed. The oxide fuel is reduced with Ca metal in...
08/25/1992
5096545Plutonium recovery from spent reactor fuel by uranium displacement
A process for separating uranium values and transuranic values from fission products containing rare earth values when the values are contained together in a molten chloride salt electrolyte. A molten chloride salt electrolyte with a first ratio of pluton...
03/17/1992
4814046Process to separate transuranic elements from nuclear waste
A process for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic ...
03/21/1989
4568487Depleted-uranium recovery from and cleaning of target sands
A method is provided for cleaning depleted uranium and its associated radioactivity from target sands, for reusing many of the reactants used in the cleaning, and for recovering the depleted uranium content as uranyl nitrate. The method involves roasting ...
02/04/1986
4564507Reductive decontamination of magnesium fluoride
A method is described for decontaminating magnesium fluoride resulting from the reduction of uranium fluoride to the metal by reaction with magnesium. This decontamination employs reactions with magnesium and carbon to remove radioactive components from t...
01/14/1986
4477373Molten salt hazardous waste disposal process utilizing gas/liquid contact for salt recovery
The products of a molten salt combustion of hazardous wastes are converted into a cooled gas, which can be filtered to remove hazardous particulate material, and a dry flowable mixture of salts, which can be recycled for use in the molten salt combustion,...
10/16/1984
4464344Process for recovering non-ferrous metal values from ores, concentrates, oxidic roasting products or slags
A process for recovering non-ferrous metal values from their ores, minerals, concentrates, oxidic roasting products, or slags by sulphating said starting material using a mixture comprising iron (III) sulphate and alkali metal- or ammonium sulphate as a r...
08/07/1984
4412860Process for recovering niobium from uranium-niobium alloys
Niobium is recovered from scrap uranium-niobium alloy by melting the scrap with tin, solidifying the billet thus formed, heating the billet to combine niobium with tin therein, placing the billet in hydrochloric acid to dissolve the uranium and leave an i...
11/01/1983
4399108Method for reprocessing and separating spent nuclear fuels
Spent nuclear fuels, including actinide fuels, volatile and non-volatile fission products, are reprocessed and separated in a molten metal solvent housed in a separation vessel made of a carbon-containing material. A first catalyst, which promotes the sol...
08/16/1983
4395367Process for treating fission waste
A method is described for the treatment of fission waste. A glass forming agent, a metal oxide, and a reducing agent are mixed with the fission waste and the mixture is heated. After melting, the mixture separates into a glass phase and a metal phase. The...
07/26/1983
4392995Molten tin reprocessing of spent nuclear fuel elements
A method and apparatus for reprocessing spent nuclear fuel is described. Within a containment vessel, a solid plug of tin and nitride precipitates supports a circulating bath of liquid tin therein. Spent nuclear fuel is immersed in the liquid tin under an...
07/12/1983
4297174Pyroelectrochemical process for reprocessing irradiated nuclear fuels
In a method for reprocessing irradiated nuclear fuels, the fuel to be reprocessed is dissolved in a fused-salt bath while absolute sulfuric acid is added dropwise to said bath, plutonium sulfate is thermally converted into the corresponding oxide, the ura...
10/27/1981
4234383Actinide nitride-fueled reactor and continuous method of operating the same
An actinide nitride-fueled nuclear reactor and a method of operation therefor, including continuous in situ removal of fission products and optional addition of fuel-forming actinide material as the reaction proceeds. The reactor employed has a fuel syste...
11/18/1980
4145396Treatment of organic waste
An organic waste containing at least one element selected from the group consisting of strontium, cesium, iodine and ruthenium is treated to achieve a substantial reduction in the volume of the waste and provide for fixation of the selected element in an ...
03/20/1979
4092397Pyrochemical separation of plutonium from irradiated nuclear fuels, by thermal decomposition in molten nitrates
In the recovery of plutonium from irradiated nuclear fuel elements especially those coming from fast nuclear reactors, the improvement consisting in that the spent nuclear fuel elements are subjected to the action of a molten nitrate bath (mixed nitrates ...
05/30/1978
4021530Preparation of metal fluorides
This invention concerns a process for preparing metal and metal fluoride products. A molten mixture containing a metal oxide, a molten metal fluorinating agent and carbon is reacted to produce a gaseous oxide of carbon, a metal fluorinated product derived...
05/03/1977
4012493Preparation of metal fluorides
This invention concerns a process for preparing metal and metal fluoride products. A molten mixture containing a metal oxide, a molten metal fluorinating agent and carbon is reacted to produce a gaseous oxide of carbon, a metal fluorinated product derived...
03/15/1977
4005178Method for converting UF5 to UF4 in a molten fluoride salt
The reduction of UF5 to UF4 in a molten fluoride salt by sparging with hydrogen is catalyzed by metallic platinum. The reaction is also catalyzed by platinum alloyed with gold reaction equipment....
01/25/1977
3984345Method for removal of adhering sodium from and storage of irradiated nuclear fuel elements
There is described a method for sodium-deactivating and/or stocking irradiated nuclear fuel elements, said elements being contacted with a fluid, in which use is made as fluid, of a molten salt mixture which is uncorrosive for the element stainless steels...
10/05/1976
3982928Separation of uranium from (Th,U)O2 solid solutions
Uranium is separated from mixed oxides of thorium and uranium by a pyrometallurgical process in which the oxides are mixed with a molten chloride salt containing thorium tetrachloride and thorium metal which reduces the uranium oxide to uranium metal whic...
09/28/1976
3981960Reprocessing method of caramic nuclear fuels in low-melting nitrate molten salts
Ceramic nuclear fuel is reprocessed through a method wherein the fuel is dispersed in a molten eutectic mixture of at least two alkali metal nitrates and heated to a temperature in the range between 200°C and 300°C. That heated mixture is then subjected...
09/21/1976
 
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