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Patent Searching and Data


Matches 451 - 500 out of 1,209

Document Document Title
JPH0987765A
To make it possible to efficiency carry out the work to immerse and lift an adsorption bed unit. A floating body is provided with vertical through-holes 3 and the top end of frame 4 for holding the adsorption bed unit extending in the ve...  
JPH0980194A
To facilitate process control by extracting trivalent actinide and rare earth element from high acid waste liquid, reducing nitric acid concentration in the extracted solution and separating the trivalent actinide and the rare earth elem...  
JP2584853B2  
JPH0931564A
To enhance the generation efficiency of uranium vapor with respect to making electric power by pressing electrodes to both side of a sheet- or bar-shaped uranium metal under transfer and energizing these electrodes, thereby heating the u...  
JP2562985B2  
JP2546798B2  
JPH08271684A
To oxidize Am(VI) in short time without using persulfate by adding heteropolyanion(HPA) and Ag(II) to be converted to AG(II) ion to nitric acid solution containing americium Am(III) and electrolyzing. HPA capable of complexing Am and Ag(...  
JPH08269585A
PURPOSE: To obtain a method for separating and recovering platinum family elements and technetium with a high purity at a high yield from the nitric acid soln. of spent unclear fuel or the waste liquids generated from reprocessing plants...  
JP2542118B2  
JP2529457B2  
JPH08173702A
To continuously execute an extraction process within a time shortened to a large extent as compared with a conventional method, to eliminate the danger of the contamination with an external substance, to reduce operation and equipment an...  
JPH08503937A
(57) [Abstract] The present invention relates to cesium and the selection extraction method of アクチニド which use screw * crown calyx [4] Allen, those manufacturing methods, and them. Screw * crown calyx [4] Allen is the following...  
JPH08503879A
(57) It is a method for collecting metal (17) and acid valuables (48) from the source substance (22) containing summary metal fluoride, 蒸解 (10) of the source substance is carried out in sulfuric acid (20), a slurry is formed, and the...  
JPH08109024A
PURPOSE: To obtain the same effect as a conventional method by a more simplified method than a conventional method by integrating second cycle into first cycle in refining and enriching plutonium present together with uranium and fission...  
JPH0833484B2  
JPH0823598B2  
JPH085675B2  
JPH08500057A
(57) Especially summary rotary kiln is for generating a uranium dioxide from uranium hexafluoride, and has an inlet device and the heated barrel which can be rotated. Uranium hexafluoride and vapor react mutually within an inlet device, ...  
JPH07260993A
PURPOSE: To recover Np from a radioactive waste liquid simply, by adding a reducer which can reduce the Fe from the trivalence to the bivalence, in the solution of a spent fuel, so as to reduce the Np from the pentavalence to the quadriv...  
JPH07509279A  
JPH07246301A
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...  
JPH07246302A
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...  
JPH07209483A
PURPOSE: To perform a significantly simplified chemical reprocessing by reducing UO2 in a spent fuel into U by high temperature metallurgy using no aqueous solution, separating the U from other components in the form of metal, condensing...  
JPH07187679A
PURPOSE: To provide an uranium enriching device and a method thereof in which energy efficiency is heightened. CONSTITUTION: An uranium generating mechanism 100 has a gas mixing part 110 in which calcium powder is added to gaseous uraniu...  
JPH07179959A
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...  
JPH0761990B2  
JPH07120580A
PURPOSE: To ensure economy and total safety by subjecting a spent fuel pin composed of a nitride of minor actinoid, etc., to fused salt electrolysis and converting the obtained high order nitride into a mononitride. CONSTITUTION: A spent...  
JPH07118771A
PURPOSE: To produce a metal contg. U by reacting U chloride with Na vapor to produce U metal and NaCl, liquefying the reaction product by cooling and separating both gravitationally. CONSTITUTION: A liq. U chloride (UCl4, etc.) is suppli...  
JPH07104096A
PURPOSE: To provide the mutual separation method for a lanthanoid element and a trans-plutonium element (TPE) selectively extracting the trans-plutonipm element without generating a waste liquid, compatible with the continuous process, a...  
JPH0760135A
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...  
JPH0755991A
PURPOSE: To safely and easily process radioactive waste products by reducing fission products in salt after electrolytic refining to metal compound, contacting with molten metal and extracting actinide mixture. CONSTITUTION: Spent oxide ...  
JPH07500912A  
JPH06104573B2  
JPH06104869B2  
JPH06346165A
PURPOSE: To easily refine uranium contg. molybdenum and to produce an yellow cake satisfying the specifications by bringing a uranium exudation liquid contg. molybdenum into contact with a chelating resin contg. a specified group. CONSTI...  
JPH06339615A
PURPOSE: To simply separate and purify uranium isotopes by feeding a uranium isotope-containing solution to an annular chromatography while injecting an eluant to an anion exchange resin in the continuously rotating annular chromatograph...  
JPH0675673B2  
JPH0675674B2  
JPH0672946B2  
JPH06222195A
PURPOSE: To offer a method to extract uranium from uranium-containing residues at a low temp. and with atmospheric pressure. CONSTITUTION: An uranium-containing residue 10 is oxidated, crushed, and sorted into batches according to the si...  
JPH0658431B2  
JPH06506504A  
JPH06505508A  
JPH0644074B2  
JPH06148383A
PURPOSE: To provide a method for dissolving plutonium dioxide with OH- radical generated by water radiolysis, which is suitable for processing dissolved micro materials and plutonium group waste. CONSTITUTION: In a reactor 1, under prese...  
JPH06123796A
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...  
JPH0693349A
PURPOSE: To enable recovery of a metal vaporized from a long crucible for vaporizing the metal and stuck on the surface of a metal recovery plate by easily flowing the molten metal along the wetted surface. CONSTITUTION: In this device, ...  
JPH0688149A
PURPOSE: To remove the radioactive element component incorporated into a titanium-contg. material which is a raw material for production of titanium tetrachloride by a simple means. CONSTITUTION: The titanium-contg. material is subjected...  
JPH0688897A
PURPOSE: To enhance the extraction efficiency of Pu by bringing an aq. soln. containing U, Pu and a fission product into contact with a org. soln. containing a crown compd. and subsequently bringing the same into contact with water or an...  
JPH0627290A
PURPOSE: To provide a method and device wherein plutonium and/or other radioactive element present in solid or a liquid product is, by microwave heating, dissolved in an aqueous solution, and, a solid or liquid product contaminated with ...  

Matches 451 - 500 out of 1,209