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JP2005502699A |
In the thermosensitive compound in which it is 可溶 at a temperature lower than the critical temperature Tc underwater, and it has underwater the character which is non-溶 at a temperature higher than Tc, and this character is heat re...
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JP3612554B2 |
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JP2004286719A |
To provide a uranium oxide to metal transformation and filtration recovery device which reacts uranium oxide powder with lithium metal in chloride lithium molten salt medium, transforms those to uranium metal powder, separates the transf...
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JP3576550B2 |
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JP2004183093A |
To provide a cyclic method for separating at least one chemical element E1 from at least one chemical element E2 from an aqueous solution containing above elements using a mixture of two extractants operating in non-overlapping chemical ...
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JP2004113941A |
To provide a method and an apparatus for separating isotopes of gadolinium, by which an enriched product/a scrap metal of gadolinium can be recovered effectively while using an atomic laser method, and which has excellent profitability.I...
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JP2004076147A |
To provide a resin which can capture and concentrate uranium and thorium with high selectivity in a wide pH range, especially in near neutral region and keep its capturing capacity even when stored in a heating and drying state for a lon...
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JP2004036000A |
To efficiently dissolve or extract metals, such as uranium, platinum and palladium, metalloids or their oxides while reducing environmental load.The metals, metalloids or their oxides are dissolved or extracted by using a supercritical f...
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JPWO2002022895A1 |
タンタル、ニオブ等を含有する原料を用いて
、フッ酸系溶液を用いたフッ素処理プロセス
を経て採取精製する製造方法において、発生
する抽出残渣中の放射性物質の濃縮を防...
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JP2003306725A |
To provide a method for producing titanium by which metallic titanium having high purity can be obtained directly from a titanium compound containing titanium oxide and processes can easily be made into a continuous process.The titanium ...
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JP3452360B2 |
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JP3463931B2 |
To improve corrosion resistivity and safety of a pot in dry reprocessing method. In the dry reprocessing method precipitating nuclear fuel by melting spent nuclear fuel in molten salt in a pot, the pot (2) is induction-heated, cooling me...
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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 |
(57) It is a method for electrolytic refining to separate americium metal to the fission product of summary rare earth, and the americium metal formed in the liquid metal electrode is returned by exchange of a liquid metal electrode, and...
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JP2003149370A |
To improve the recovery rate of U3O8 with the grain diameter of size not larger than the mesh so as not to cause defectiveness in the metal phase of pellet in manufacturing nuclear fuel pellet by adding scraps UO2 powder after oxidation ...
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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 |
(57) It is at the method of separating metal from the composite containing summary metal, and is characterized by forming the electrolysis vessel which consists of a composite in which an anode contains metal. An electrolyte is ion liqui...
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JP2003515751A |
(57) A summary and solution means In the present invention, this method consists of contacting both nitric acid which is in a mixed state as preferably as these pins, and a fluoroboric acid about spent-nuclear-fuel pins or the polluted d...
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JP2003508631A5 |
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JP2003508631A |
(57) the method of collecting contamination nature or precious ingredients from a summary solid supply substance (10), After supplying this substance (10) to a grinder as a pretreatment (12) as an option, it supplies with the substance (...
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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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JP3366485B2 |
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JP2002350584A |
To improve corrosion resistivity and safety of a pot in dry reprocessing method. In the dry reprocessing method precipitating nuclear fuel by melting spent nuclear fuel in molten salt in a pot, the pot (2) is induction-heated, cooling me...
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JP2002538413A |
(57) Summary book invention passes a granular material through the unit (24) for making small the mean diameter of the particles of this granular material for a granular material, It has the stage of changing the overall aspect of the ra...
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JP2002534612A |
(57) Summary book invention offers a series of technology for processing the residue containing a uranium ore, the processed uranium, and uranium and the supply substance containing uranium like the spent fuel containing uranium. The pro...
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JP3320177B2 |
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JP3316007B2 |
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JP2002226935A |
To provide a thorium-tungsten (Th-W) alloy having Th and/or Th compound dispersed in a state of particles with ≤0.3 μm average particle size, to provide a Th-W wire, its manufacturing method, a coil having improved deformation resista...
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JP2002518591A |
(57) Summary book invention relates to the method of dissolving plutonium or the plutonium alloy by making the water dissolution mixture containing nitric acid, the carboxylic acid which has the 錯形成 characteristic to plutonium, and...
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JP2002516810A |
(57) A summary organic matter phase is contacted with the water nitric acid phase containing a zirconium, technetium, and the アクチニド metal in which at least one extraction is possible, and does in this way, In processing or the ...
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JP2002167625A |
To sequentially separate plutonium and uranium from aqueous solutions such as Pu-U containing high level radioactive waste solutions generated in a wet retreatment stage for used nuclear fuel in a nuclear power furnace, experimental wast...
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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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JP3257797B2 |
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JP2002001007A |
To provide a method for efficiently extracting Am(III), Cm(III), and Ln(III) ions existing in an aqueous acidic solution, especially in a high level wastewater generated from recycling treatment of spent nuclear fuel.Am, Cm and rare eart...
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JP2001348628A |
To provide an apparatus for preventing an adsorbent from flowing out of an adsorbing bed tank and efficiently recovering specific components in sea water.This recovering apparatus for recovering the specific components in sea water provi...
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JP2001347257A |
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 lo...
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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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JP2001523330A |
(57) In the method of converting into primary metal or its useful compound and a fluoride useful thing, or its useful compound the supply substance of the high minerals content containing a summary primary metal useful thing and a fluori...
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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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JP2001518139A |
(57) The method of extracting metal from a metal oxide directly is indicated by exposing an oxide to a summary supercritical fluid. Preferably, metal is アクチニド or a lanthanide. Metal is uranium, thorium, or plutonium more prefer...
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JP2001516809A5 |
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JP2001516809A |
(57) A summary and solution means. The present invention extracts アクチニド of 3 values from solution of H* concentration of 0.01 mol / L*2 mol / L. As a synergist アクリニド of 3 values from at least one kind of lanthanides T...
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JP2001516321A |
(57) The method and equipment which manufacture halogenation output from a summary metal halogenide. In one example, 6 uranium fluorides are processed by separating fluoride from the metal of 6 uranium fluorides. Into a 熔融 metal bath...
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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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JP2001514377A |
(57) Summary book invention relates to the method of separating アクチニド and a lanthanide by the liquid * liquid extraction by a calyx arene.
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JP2001513434A |
(57) アクチニド by which summary book invention is introduced into a division (3), and the 1st solution containing at least 1 metal chosen from the group of a lanthanide, It is related with a method for the membrane transport using ...
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JP2001511480A |
(57) Summary book invention relates to the metal-fume-fever disposal method and the continuation extraction method of metal goods which consist of at least one sort of metal, It is the stage of 溶融 (ing) metal in the 1st of an inducti...
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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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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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