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7622090 |
Method for separating uranium (VI) from actinides(IV) and/or actinides (VI) and its uses
The invention relates to a method for separating uranium(VI) from one or more actinides selected from actinides(IV) and actinides(VI) other than uranium(VI), characterized in that it comprises the...
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7597862 |
Process for radioisotope recovery and system for implementing same
A method of recovering daughter isotopes from a radioisotope mixture. The method comprises providing a radioisotope mixture solution comprising at least one parent isotope. The at least one parent...
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7578982 |
Radioisotope TI-201 production process
A radioisotope TI-201 is produced. The process includes electroplating, irradiating, dissolving, precipitating, ion exchanging, decaying and filtering. The TI-201 obtained is a liquid having a high...
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7569192 |
System for recovery of daughter isotopes from a source material
A method of separating isotopes from a mixture containing at least two isotopes in a solution is disclosed. A first isotope is precipitated and is collected from the solution. A daughter isotope is...
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7554098 |
Medical isotope generator systems
Medical isotope generator systems are disclosed according to some aspects. In one aspect, a 90 Y generator system comprises a generator column, a concentration column, and a flow control system,...
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7531150 |
Method of separating and purifying cesium-131 from barium carbonate
The present invention provides a method of separating and purifying Cesium-131 (Cs-131) from Barium (Ba). Uses of the Cs-131 purified by the method include cancer research and treatment, such as...
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7524469 |
Extractant composition including crown ether and calixarene extractants
An extractant composition comprising a mixed extractant solvent consisting of calix[4] arene-bis-(tert-octylbenzo)-crown-6 (“BOBCalixC6”), 4′,4′,(5′)-di-(t-butyldicyclo-hexano)-18-crown-6...
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7517508 |
Method of separating and purifying Yttrium-90 from Strontium-90
The present invention provides a method of separating and purifying Yttrium-90 (Y-90) from Strontium-90 (Sr-90). In addition, a zirconium (Zr) clean-up step for the Y-90 is provided. Uses of the...
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7510691 |
Method for improving the recovery of cesium-131 from barium carbonate
The present invention provides a method for improving the recovery of cesium-131 (Cs-131) from barium (Ba) carbonate. Uses of the Cs-131 purified by the method include cancer research and...
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7494630 |
Method of stripping metals from organic solvents
A new method to strip metals from organic solvents in a manner that allows for the recycle of the stripping agent. The method utilizes carbonate solutions of organic amines with complexants, in low...
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7476377 |
Rubidium-82 generator based on sodium nonatitanate support, and improved separation methods for the recovery of strontium-82 from irradiated targets
Sodium nonatitanate compositions, a method using the composition for recovery of 82 Sr from irradiated targets, and a method using the composition for generating 82 Rb. The sodium nonatitanate...
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7476370 |
Method for producing a sealed 210Pb—210Po alpha particle emitter
The present invention provides a method for producing a sealed 210 Pb— 210 Po α source (α particle emitter) and an apparatus thereof, which can be used as an α particle source for a random...
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7435399 |
Chromatographic extraction with di(2-ethylhexyl)orthophosphoric acid for production and purification of promethium-147
A method of producing and purifying promethium-147 including the steps of: irradiating a target material including neodymium-146 with neutrons to produce promethium-147 within the irradiated target...
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7394074 |
Protective housing for radionuclide generator and combination thereof
A protective cover and radionuclide generator assembly. The cover protecting inlet and outlet connections disposed on the radionuclide generator. The radionuclide generator having a distal end...
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7318899 |
Method of separating isotopes
A process in which isotopes of the same element belonging to the alkaline earth metals, transition elements and heavy metals having an atomic mass of less than 209, in particular lanthanide metals,...
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7294291 |
Ceramicrete stabilization of U-and Pu-bearing materials
A method of stabilizing nuclear material is disclosed. Oxides or halides of actinides and/or transuranics (TRUs) and/or hydrocarbons and/or acids contaminated with actinides and/or TRUs are treated...
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7291316 |
Cesium and strontium extraction using a mixed extractant solvent including crown ether and calixarene extractants
A mixed extractant solvent including calix[4]arene-bis-(tert-octylbenzo)-crown-6 (“BOBCalixC6”), 4′,4′,(5′)-di-(t-butyldicyclo-hexano)-18-crown-6 (“DtBu18C6”), and at least one...
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7244403 |
Purification of Lutetium 177
Undesirable metal cation contaminants, including hafnium, can be reduced from a solution containing Lutetium-177 on a bed of an anion exchange resin. The thus purified solution can be stored and...
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7211231 |
Ion exchange materials for use in a 213Bi generator
A bismuth-213 generator comprising an insoluble composition having the general formula Zr(Phosponate) x (HPO 4 ) 2−x .nH 2 O, wherein x is between 0 and 2; and n is the number of waters of...
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7195745 |
Method of preparing a product based on phosphate of thorium and/or actinide(s)
The invention relates to a process for the preparation of a product based on a phosphate of at least one element M(IV), for example of thorium and/or of actinide(IV)(s). This process comprises the...
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7192563 |
Process for recovery of high purity uranium from fertilizer grade weak phosphoric acid
A two-cycle countercurrent extraction process for recovery of highly pure uranium from fertilizer grade weak phosphoric acid. The proposed process uses selective extraction using di-(2-ethyl hexyl)...
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7157061 |
Process for radioisotope recovery and system for implementing same
A method of recovering daughter isotopes from a radioisotope mixture. The method comprises providing a radioisotope mixture solution comprising at least one parent isotope. The at least one parent...
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7157022 |
Multivalent metal ion extraction using diglycolamide-coated particles
A separation medium, a method for using that separation medium and an apparatus for selectively extracting multivalent cations such as pseudo-lanthanide, prelanthanide, lanthanide, preactinide or...
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7138643 |
Method and apparatus for separating ions of metallic elements in aqueous solution
Methods and apparatus for separating ions of metallic elements are provided. Preferred methods utilize a hydrophobic chelating extractant, such as an organophosphorus compound, adsorbed onto carbon...
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7118718 |
Gypsum decontamination process
A process for reducing a level of radionuclei in a phosphogypsum material having a radioactive contaminant is provided, wherein the process includes the steps of: (a) mixing the phosphogypsum...
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7101484 |
Sr-90/Y-90 radionuclide generator for production of high-quality Y-90 solution
A process for purifying a stock Sr-90 solution containing stable and radioactive impurities, holding the purified Sr-90 solution for Y-90 ingrowth, and subsequently extracting the Y-90 from the...
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7087206 |
Multicolumn selectivity inversion generator for production of high purity actinium for use in therapeutic nuclear medicine
A multicolumn selectivity inversion generator separation method has been developed in which actinium ions, a desired daughter radionuclide, are selectively extracted from a solution of the thorium...
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6974563 |
Ion exchange materials for the separation of 90Y from 90SR
Inorganic ion exchange materials for the separation of 90 Y from 90 Sr include clinoptilolite, potassium titanosilicate pharmacosiderite, sodium titanosilicate and sodium nonatitanate. These...
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6972414 |
Method and apparatus for production of 213Bi from a high activity 225Ac source
A method and apparatus for isolating and purifying a 213 Bi radioactive isotope from an 225 Ac source using a primary column and a primary sorbent which preferentially retains 225 Ac over 213...
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6951634 |
Process for recovery of daughter isotopes from a source material
The invention includes a method of separating isotopes from a mixture containing at least two isotopes in a solution. A first isotope is precipitated and is collected from the solution. A daughter...
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6908598 |
Rubidlum-82 generator based on sodium nonatitanate support, and improved separation methods for the recovery of strontium-82 from irradiated targets
Sodium nonatitanate compositions, a method using the composition for recovery of 82Sr from irradiated targets, and a method using the composition for generating 82Rb. The sodium nonatitanate...
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6852296 |
Production of ultrapure bismuth-213 for use in therapeutic nuclear medicine
A multicolumn selectivity inversion generator has been developed in which bismuth-213 is selectively extracted from an HCl solution of the actinium-225 parent (and its radiogenic descendents) by a...
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6787042 |
Automated radionuclide separation system and method
A gas-free system for separating a solution of substantially impurity-free daughter products from an associated parent load solution includes a pump, a plurality of multi-port valves, separation...
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6773686 |
Process for the purification and concentration of radiodide isotopes
Process for the purification and concentration of isotopes which isotopes are dissolved in a dilute acidic solution and adsorbed on an (optionally) activated surface of a d 10 -metal whereby the...
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6770195 |
Compact automated radionuclide separator
A method and apparatus are provided for automatically separating radionuclides using a chromatographic separation process. The method includes the steps of displaying a first flow diagram on a...
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6652661 |
Radioactive decontamination and translocation method
A method for removing a wide variety of radioactive contaminants from a contaminated surface sufficient for the surface to be classified as a low-level waste or as free release. Contaminated...
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6603127 |
Bismuth-213 generator and uses thereof
The present invention provides a generator capable of producing therapeutic Bismuth-213 doses. Also disclosed are methods of preparing Bismuth-213-labeled compounds using such generator and...
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6511603 |
Alkaline earth cation extraction from acid solution
An extractant medium for extracting alkaline earth cations from an aqueous acidic sample solution is described as are a method and apparatus for using the same. The separation medium is free of...
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6485695 |
Method and apparatus for preparing Bi-213 for human therapeutic use
This invention relates to a method and an apparatus for preparing Bi-213 to be integrated in a radioimmunocojugate for human therapeutic use. According to the invention the method comprises the...
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6423199 |
Electrochemical ion exchange using carbollide systems
An electrochemical ion exchange cell comprises a metal carbollide as ion exchange material. The carbollide is preferably a polynuclear cobalt dicarbollide and is typically substituted by chlorine....
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6337055 |
Inorganic sorbent for molybdenum-99 extraction from irradiated uranium solutions and its method of use
A high radiation resistant inorganic sorbent is used for the extraction of Mo-99 from the fission byproducts of a uranyl sulfate nuclear-fueled homogeneous-solution nuclear reactor. The sorbent is...
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6309614 |
Method for isolating and purifying 90Y From 90strontium in multi-curie quantities
The invention relates to a process for separating and purifying multi-curie quantities 90 Y of sufficient chemical and radiochemical purity suitable for use in medical applications without a...
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6258333 |
Method for the simultaneous recovery of radionuclides from liquid radioactive wastes using a solvent
The present invention relates to solvents, and methods, for selectively extracting and recovering radionuclides, especially cesium and strontium, rare earths and actinides from liquid radioactive...
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6245305 |
Method of separating and purifying gadolinium-153
The present invention is an improvement to the method of separating and purifying gadolinium from a mixture of gadolinium and europium having the steps of (a) dissolving the mixture in an acid; (b)...
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6214301 |
Hafnium radioisotope recovery from irradiated tantalum
Hafnium is recovered from irradiated tantalum by: (a) contacting the irradiated tantalum with at least one acid to obtain a solution of dissolved tantalum; (b) combining an aqueous solution of a...
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6157036 |
System and method for automatically eluting and concentrating a radioisotope
A system and method for eluting one or more radioisotope processing elements, such as generators and/or concentration and purification components, with a gas over eluent delivery mechanism is...
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6153154 |
Method for sequential injection of liquid samples for radioisotope separations
The present invention is a method of separating a short-lived daughter isotope from a longer lived parent isotope, with recovery of the parent isotope for further use. Using a system with a...
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6146601 |
Enrichment of silicon or germanium isotopes
Isotopes of either germanium or silicon are separated by a chemical exchange reaction. Preferably the compound is a hydro halide or halide composition and the donor can be a wide variety of...
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6126909 |
Process and apparatus for the production of BI-212 and a use thereof
A process for producing substantially radio-impurity-free Bi-212 is disclosed. An acidic feed solution containing Pb-212 is contacted with an extraction medium to bind the Pb-212 thereto. The...
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6113796 |
Method for separating metals by micellar ultrafiltration that can be used to process radioactive waste
The present invention relates to a method for separating metals by micellar ultrafiltration, that can be used to process radioactive waste. This process consists of adding to the aqueous solution a...
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