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7250119 |
Composite materials and techniques for neutron and gamma radiation shielding
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...
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7091393 |
Processes for immobilizing radioactive and hazardous wastes
The present invention utilizes one or more processes to immobilize a waste that contains one or more of radionuclides, hazardous elements, hazardous compounds, and/or other compounds present in the...
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7090827 |
Process for immobilizing metallic sodium in glass form
A process for immobilizing metallic sodium in glass form. The process comprises: (A) introducing in a dispersed state, into a reactor, an amount of a vitrified matrix precursor, metallic sodium and...
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7012168 |
Boron-based containment matrix for the storage or transmutation of long-life radioactive elements
The invention relates to a confinement matrix for the storage or incineration of at least one long-life radioactive element, comprising at least one crystalline boron compound of a rhombohedral...
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6518477 |
Simplified integrated immobilization process for the remediation of radioactive waste
A method for remediating non-homogeneous radioactive waste to significantly reduce the waste mass/volume and to convert such waste to products that meet federal regulatory compliance standards is...
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6448461 |
Method for treating boron-containing waste
The present invention provides a method and an apparatus for treating boron-containing waste, which prevent clogging of a waste liquid line, achieve an increase in feeding of a waste liquid to a...
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6436271 |
Preparation of mineral matrices by cold crucible induction melting
The aim of the present invention is a process for preparing a mineral matrix by melting, which is implemented according to the method of direct cold crucible induction melting. The method employs a...
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6372950 |
Method of treating a radiation protector
A radiation protector treating method including the steps of pulverizing a used radiation protector to obtain a pulverized radiation protector material and mixing the pulverized radiation protector...
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6329563 |
Vitrification of ion exchange resins
The present invention relates to vitrification of ion exchange resins that have become loaded with hazardous or radioactive wastes, in a way that produces a homogenous and durable waste form and...
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6258994 |
Methods of vitrifying waste with low melting high lithia glass compositions
The invention relates to methods of vitrifying waste and for lowering the melting point of glass forming systems by including lithia formers in the glass forming composition in significant amounts,...
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6204214 |
Pumpable/injectable phosphate-bonded ceramics
A pumpable ceramic composition is provided comprising an inorganic oxide, potassium phosphate, and an oxide coating material. Also provided is a method for preparing pumpable ceramic-based waste...
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5998690 |
Method and agents for solidification of boric acid and/or borates solutions
A unique method for solidification of solutions containing boric acid and/or borates is disclosed in this invention. The boron species in the solutions are polymerized to form polyborates, and the...
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5961679 |
Recovery of fissile materials from nuclear wastes
A process for recovering fissile materials such as uranium, and plutonium, and rare earth elements, from complex waste feed material, and converting the remaining wastes into a waste glass suitable...
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5947887 |
Extruder glass-melter process for vitrification of nuclear and other toxic wastes
A toxic waste and glass frit are fed into an extruder having a helical screw. The glass frit, as well as any glassy material and glass-forming component in the waste, are melted in the extruder as...
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5846278 |
Method of determining glass durability
A process for determining one or more leachate concentrations of one or more components of a glass composition in an aqueous solution of the glass composition by identifying the components of the...
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5637127 |
Plasma vitrification of waste materials
This invention provides a process wherein hazardous or radioactive wastes in the form of liquids, slurries, or finely divided solids are mixed with finely divided glassformers (silica, alumina,...
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5613240 |
Method of preparing sodalite from chloride salt occluded zeolite
A method for immobilizing waste chloride salts containing radionuclides and hazardous nuclear material for permanent disposal starting with a substantially dry zeolite and sufficient glass to form...
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5530174 |
Method of vitrifying high-level radioactive liquid waste
A method of vitrifying a high-level radioactive liquid waste comprising removing a precipitate composed mainly of Mo and Zr from the high-level liquid waste, mixing the resulting high-level liquid...
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5494863 |
Process for nuclear waste disposal
The present invention relates to a process for nuclear waste disposal. In it, a glass forming mixture including an aqueous solution of one or more metal alkoxides, alcohol, and solubilized, low...
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H001013 |
Process for the immobilization and volume reduction of low level radioactive wastes from thorium and uranium processing
A process for the immobilization and volume reduction of low level radioactive wastes produced from the processing of rare earth recovery processes comprising mixing the waste residue with 0.1 to...
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4851156 |
Retention of radio-ruthenium in acid processing of nuclear waste
Radioactive combustible waste can be processed with hot concentrated sulfuric acid and the resulting residue material immobilized in glass with retention of volatile radio-ruthenium, if present. In...
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4797232 |
Process for the preparation of a borosilicate glass containing nuclear waste
The invention relates to a process for the preparation of a borosilicate glass containing nuclear waste. In this process, an inactive borosilicate matrix is prepared in an aqueous medium by mixing...
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4772431 |
Process for the immobilization of nuclear waste in a borosilicate glass
The invention relates to a process for the immobilization of nuclear waste in a borosilicate glass. In the process, the following are mixed simultaneously: a silica-based gel precursor, a...
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4759879 |
Glass former composition and method for immobilizing nuclear waste using the same
An alkoxide glass former composition has silica-containing constituents present as solid particulates of a particle size of 0.1 to 0.7 micrometers in diameter in a liquid carrier phase...
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4725383 |
Process for volume reduction and solidification of a radioactive sodium borate waste solution
A process is disclosed for volume reduction and solidification of a radioactive waste solution mainly composed of sodium borate and discharged from a pressurized water reactor. The process...
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4595528 |
Process for immobilizing radioactive boric acid liquid wastes
A method of immobilizing boric acid liquid wastes containing radionuclides by neutralizing the solution and evaporating the resulting precipitate to near dryness. The dry residue is then fused into...
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4544499 |
Fixation by anion exchange of toxic materials in a glass matrix
This invention relates to the immobilization of toxic, e.g., radioactive materials, internally in a silicate glass or silica gel matrix for extremely long periods of time. Toxic materials, such as...
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4514329 |
Process for vitrifying liquid radioactive waste
A process for vitrifying liquid radioactive waste is provided. In this process, a solution of a water-soluble vitrifying-facilitating inorganic compound in liquid radioactive waste is mixed with a...
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4487711 |
Cinder aggregate from PUREX waste
Disclosed is a process for making a cinder aggregate from neutralized PUREX waste. The PUREX waste is concentrated to about 30 to about 40 percent solids and a colloid of such de-alcoholated...
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4430257 |
Alcohol-free alkoxide process for containing nuclear waste
Disclosed is a method of containing nuclear waste. A composition is first prepared of about 25 to about 80%, calculated as SiO 2 , of a partially hydrolyzed silicon compound, up to about 30%,...
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4422965 |
Nuclear waste encapsulation in borosilicate glass by chemical polymerization
Disclosed is a process for containing a solution of nuclear waste, where the nuclear waste is at least 10% sodium or nitrate. A composition is prepared in an alcohol of about 1 to about 99% of a...
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4376070 |
Containment of nuclear waste
Disclosed is a method of immobilizing nuclear waste in glass. A composition is prepared of about 30 to about 85% of a hydrolyzed glass-forming silicon compound, about 5 to about 30% of a...
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4202792 |
Method for noncontaminating solidification of radioactive waste materials
Method for the solidification, in a manner which protects the environment against contamination, of waste materials obtained during reprocessing of irradiated nuclear fuel and/or breeder materials...
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4152287 |
Method for calcining radioactive wastes
This invention relates to a method for the preparation of radioactive wastes in a low leachability form by calcining the radioactive waste on a fluidized bed of glass frit, removing the calcined...
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4097401 |
Thermodynamically stable product for permanent storage and disposal of highly radioactive liquid wastes
Highly radioactive liquid wastes are permanently stored in a solidification matrix containing the components of a known borosilicate glass together with nucleation agents selected from the group...
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4020004 |
Conversion of radioactive ferrocyanide compounds to immobile glasses
Complex radioactive ferrocyanide compounds result from the scavenging of cesium from waste products produced in the chemical reprocessing of nuclear fuel. These ferrocyanides, in accordance with...
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3321409 |
Production of radioactive fused glass bodies
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3272756 |
Radioactive waste disposal using colemanite
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3265627 |
Addition of lithium values in conversion of fission-product wastes to a glass-like solid for disposal
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