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JP2003220302A |
To obtain high concentration of ferric ions used in dissolving ore to increase dissolving efficiency by removing unnecessary metal ions as much as possible and oxidizing by iron oxidizing bacteria.In recovering an objective element from ...
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JP2003215292A |
To provide a method for efficiently and economically separating and recovering americium, curium, and rare-earth elements from a solution containing radioactive liquid waste and rare-earth elements which occur in nuclear-power-related fa...
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JP2003521583A |
Described is a process for the separation of americium metal from spent fuel or chlorinated high level waste of fuel reprocessing by using a liquid electrode electrode whereby americium will be obtained in high yields.
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JP3426613B2 |
PURPOSE: To easily separate a corrosive product such as iron from a trivalent lanthanoide existing in an acidic aq. solution by allowing an organic solvent containing propane diamide expressed by a formula to contact with the acidic aq. ...
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JP2003515667A |
A method for separating a metal from a composition including the metal involves forming an electrolytic cell in which the anode comprises a composition including the metal. The electrolyte is an ionic liquid. A sufficient potential diffe...
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JP2003515751A |
The invention comprises a method for the dissolution of spent nuclear fuel pins or contaminated cladding, the method comprising contacting together the pins and both nitric and fluoroboric acids which, preferably, are present in admixtur...
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JP3403475B2 |
PURPOSE: To provide a method capable of easily separating and extracting not only a nuclear fuel material, such as thorium, but a rare earth element as well from a raw material contg. the nuclear fuel material. CONSTITUTION: Plural bar-s...
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JP2003508631A5 |
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JP3366485B2 |
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JP2002538413A |
The invention concerns a method comprising a step which consists in passing the powder through a unit for reducing (24) the average size of the powder particles, bringing about a modification in the general appearance of the spectrum of ...
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JP2002534612A |
The invention provides a series of techniques for processing uranium containing feed materials such as uranium ores, reprocessed uranium, uranium containing residues and uranium containing spent fuel. The processes described involve fluo...
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JP3320177B2 |
A process for extracting uranium from uranium-containing waste residues. The process dissolves the residue in hot nitric acid, and precipitates the resulting solution with sodium carbonate/sodium bicarbonate.
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JP3315083B2 |
To provide a method which is capable of removing uranium from by-products at the time of uranium production, i.e., magnesium fluoride slag contaminated with metallic uranium and uranium compd., recovering other components in an effective...
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JP3316007B2 |
An apparatus for solvent extraction processes utilizing countercurrent flow of streams of an aqueous phase and an organic phase, such as the Purex process for uranium recovery, comprises contoured fluid passing orifices in the phase disp...
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JP2002516810A |
There is described a method for treating or reprocessing spent nuclear fuel in which an organic phase is contacted with an aqueous nitric acid phase containing zirconium, technetium and at least one extractable actinide metal such that t...
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JP3259033B2 |
To provide a energy saving apparatus for particularly concentrating the solution containing specified components recovered from sea water. This apparatus is provided with an upper layer tank having a drainage opening with a valve and a l...
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JP3257797B2 |
PCT No. PCT/FR93/01161 Sec. 371 Date May 17, 1995 Sec. 102(e) Date May 17, 1995 PCT Filed Nov. 25, 1993 PCT Pub. No. WO94/12502 PCT Pub. Date Jun. 9, 1994The invention relates to bis-crown calix[4]arenes, their preparation process and th...
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JP3241475B2 |
PURPOSE: To easily separate a specific element from an aqueous solution resulting from reprocessing of spent nuclear fuel at a high recovery by bringing the aqueous solution into contact with a solid resin composed basically of a vinylpy...
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JP3232807B2 |
PURPOSE: To regenerate an anion exchange resin whose perrhenate ion adsorbing ability has been reduced by adsorption of a thiocyanato complex so that the resin can adsorb perrhenate ions. CONSTITUTION: An anion exchange resin with an ads...
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JP2001523330A |
The process for converting feed materials of high mineral content containing primary metal values and fluorine values to the primary metal or useful compounds thereof and to fluorine values or useful compounds thereof, wherein the feed m...
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JP2001518139A |
(57) [Summary] A method for directly extracting a metal from a metal oxide by exposing the oxide to a supercritical fluid is disclosed. Preferably, the metal is actinide or lanthanide. More preferably, the metal is uranium, thorium or pl...
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JP2001516809A5 |
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JP2001516321A |
A method and apparatus producing halogenated products from metal halide feeds. In one embodiment, uranium hexafluoride is treated by separating fluorine from the metal of the uranium hexafluoride. Uranium hexafluoride is introduced into ...
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JP2001514377A |
The invention involves a process for separating actinides and lanthanides by liquid-liquid extraction by means of calixarenes.These calixarenes have the formula:with R1 and R2 being alkyl groups or o-nitrophenoxy alkyl groups and R3 and ...
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JP2001511480A |
A metallothermy method includes continuously withdrawing an ingot of a metal product such as uranium or a uranium alloy as it is formed from an oxide or salt of the metal. The method employs upper and lower communicating crucibles. The u...
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JP3172863B2 |
To perform all the isotope separations including uranium enrichment by one-step operation and to provide a technique of constituting an ultrahigh purity ion source or plasm source. Only an object isotope element to be separated is separa...
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JP2001133593A |
To provide a simple method of removing thorium. This method of continuously removing radioactive thorium from an aqueous solution is characterized in that the average residence time of thorium in ion exchange resin exceeds the average ti...
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JP2001056393A |
To obtain a method recovering uranium as reusable pure uranium dioxide by removing impurity when plutonium is recovered from spent oxide nuclear fuel generated from a nuclear power station. Spent nuclear oxide fuel and reducing agent sam...
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JP2001500422A |
PCT No. PCT/GB97/02181 Sec. 371 Date Feb. 26, 1999 Sec. 102(e) Date Feb. 26, 1999 PCT Filed Aug. 14, 1997 PCT Pub. No. WO98/08994 PCT Pub. Date Mar. 5, 1998Apparatus for the solidification by desublimation of a sublimed gaseous substance...
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JP2000515932A |
A method of extracting metal and metalloid species from a solid or liquid substrate using a supercritical fluid solvent containing one or more chelating agents followed by back-extracting the metal and metalloid species from the metal an...
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JP2000292593A |
To provide a reduction device of actinide oxide obtaining high reduction ratio of actinide oxide to actinide metal. A reduction device of actinide oxide comprises a holding vessel 5 containing molten salt 2, a recovery vessel 6 placed in...
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JP3093793B2 |
A method is disclosed for producing a non-radioactive product from a radioactive waste composition that includes a radioactive component and a non-radioactive component. The method includes directing the radioactive waste into a molten m...
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JP3082921B2 |
A metallurgical processing system for economically recovering metal values, such as columbium, tantalum, thorium, and uranium from dilute source solids, such as digestion sludges, by a series of steps including: 1) slurrying the source s...
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JP2000212655A |
To provide a collection device capable of efficiently collecting useful metals such as uranium, vanadium, cobalt and titanium dissolved in micro amount in sea water in which a collection material having amidoxime group to collect the met...
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JP3062448B2 |
To provide a method capable of selectively separating and recovering uranium included in a sulfuric acid leaching liquid of uranium ores from impurities and selectively separating and recovering valuable metals in these impurities. The s...
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JP2000178531A |
To provide a scavenger and a scavenging method capable of recovering useful metals dissolved in seawater at high efficiency by merely mooring in seawater such as the black current by introducing an adoxime group and/or a hydroxyl group i...
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JP2000507306A |
A process for recovering metal values from a metal containing material including the metal values comprising digesting the metal containing material in a sulfuric acid solution comprising sulfuric acid, a reducing agent, and a carbon sou...
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JP3050359B2 |
PURPOSE: To easily separate neptunium and plutonium without generating secondary waste liquor. CONSTITUTION: A nitric acid mixed soln. of neptunium/plutonium is subjected to photooxidation by irradiation with UV in the presence of a redu...
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JP2000080492A |
To provide a recovering method of uranium from a uranium-iron alloy with a simple dry process and a molten salt electrolytic cell used for this method. A molten salt electrolytic cell is constituted of a basket like cathode 14 housing a ...
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JP3014186B2 |
A process for cleaning solutions of an alkylphosphate in a hydrophobic organic solvent. The process involves the steps of washing the solution with aqueous sulphuric acid, and contacting the washed solution with an ion exchange material....
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JP2000038623A |
To separate uranium, plutonium or compounds thereof by the use of magnetic attraction. A method for separating radio active particles comprises flowing a fluid to be treated, containing the radio active particles, into a magnetized rotar...
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JP2977744B2 |
A method is provided for separating trivalent actinides and rare earth elements in the TRUEX method using a CMPO-TBP mixed solvent. The method of separating trivalent actinides and rare earth elements comprises a trivalent actinide/rare ...
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JP2972369B2 |
A method for selectively reducing tetravalent plutonium dissolved in an aqueous solution or organic solvent solution together with hexavalent uranium, which comprises adding isobutyraldehyde to said solution. Separation between uranium a...
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JPH11290603A |
To efficiently recover a particular element contained in a salt. A method comprises the steps of dissolving in a dissolving tank 4 a salt 1a containing a particular element (for example, uranium) to be recovered, mixing a mixed fluid 2, ...
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JP2939110B2 |
PURPOSE: To easily coextract neptunium and plutonium without generating secondary waste liquor. CONSTITUTION: A nitric acid mixed soln. of neptunium/plutonium is subjected to photooxidation by irradiation with UV. Since the valence of th...
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JPH11211889A |
To selectively separate a transuranium element from radioactive waste liquid containing the transuranium element by using a chelate resin having n-octyl (phenyl)-N,N-diisobutylcarbamoyl-methylphosphine-oxide as functional group. A chelat...
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JP2912920B1 |
To improve dissolving rate and solubility, to reduce insoluble residue and to prevent the generation of NOx gas in nitric acid dissolution to the utmost at the time of dissolving a multiple oxide of uranium/plutonium containing impuritie...
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JP2909197B2 |
Sodium silicate (waterglass) is added to a waste process stream containing metal to form a waterglass sludge containing the metal contaminants. The waterglass sludge matrixed with the metal is removed from the stream. Thereafter, a caust...
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JP2908029B2 |
Soil including sand and clays contaminated with nuclear waste materials are decontaminated by treating with anhydrous liquid ammonia alone or in combination with solvated electrons. Methods comprise concentrating radionuclides, such as p...
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JP2908030B2 |
Soil including sand and clays contaminated with nuclear waste materials, elemental mercury or as mixed waste with hazardous organic compounds are decontaminated by treating with anhydrous liquid ammonia alone or with solvated electrons. ...
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