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JP2868264B2 |
PCT No. PCT/SE90/00203 Sec. 371 Date Nov. 25, 1991 Sec. 102(e) Date Nov. 25, 1991 PCT Filed Mar. 29, 1990 PCT Pub. No. WO90/11826 PCT Pub. Date Oct. 18, 1990.A uranium adsorbent is prepared by reacting a polymer containing nitrile groups...
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JPH1123784A |
To provide actinoid elements not generating waste which is hard to treat by a method in which a strict concentration management is not required, a very high partition efficiency (partition coefficient) is provided, and an easy partition ...
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JP2840363B2 |
Thorium is removed from raffinate effluent by pre-washing with odorless kerosene to remove organic contaminants, followed by solvent extraction counter-currently with tri-n-octylphosphine oxide in odorless kerosene. The loaded solvent fr...
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JP2840364B2 |
Thorium is removed from raffinate by reaction with unsupported biomass at ambient temperature. The biomass is then eluted with an alkali or an acid eluant, and thorium hydroxide precipitated from the eluate. The thorium hydroxide is then...
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JP2839585B2 |
PURPOSE:To attain reduction of the use amount of elements of the platinum group and others by using a substance having high affinity for proton as a catalyst and by using hydrazine, hydroxylamine, a hydrate or a salt of each of them, or ...
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JPH10273743A |
To separate and remove salt from the fused salt electrolyzing cathode deposit consisting of a lanthanuide and/or an actinide. Cadmium is added to the cathode deposit consisting of a lanthanide and/or a actinide, the mixture is melted to ...
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JP2788648B2 |
In a solvent extraction method a contactor comprises a forward extraction (FX) section comprising sub-sections 10A, 10B and a back extraction (BX) section comprising sub-sections 12A, 12B. To enable higher concentrations of solute to be ...
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JPH10212532A |
To efficiently recover Ta, Nb and Sc from a composite raw material contg. metals and having significant-level radioactivity by conducting a succession of acid cooking and alkali reaction after sulfation-roasting and applying wet refining...
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JPH10153688A |
To provide a method using electrolysis for processing liquid water waste containing radioactive fission products (alkali solution containing organic matter, but not limited). Radioactive waste liquid flow 12 has high pH and contains wide...
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JPH10130080A |
To obtain an excellent antibacterial effect at a low cost by using a glaze mixed with the fine powder of a trace natural radioactive element such as ZUIBYOGAN to produce the glaze. The <150 to 300-mesh fine powder of a trace natural radi...
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JP2681508B2 |
A method for a quantitative separation of scandium from thorium comprises adsorption of both metals on a cation exchange resin followed by selective elution of scandium with an acidic solution of a chelating agent followed by the elution...
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JPH09510690A |
Diphosphine dioxides for removing actinides such as Pu, Am and Np from aqueous effluents and fission product concentrates from waste nuclear fuel reprocessing plants. The diphosphine dioxides have one of the following formulae (I) and (I...
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JPH09268335A |
To provide an apparatus capable of easily laying unit useful metal capturing members into the sea and taking out and exchanging the same. This apparatus for recovering the useful metals in the sea water consists of a device 1 for capturi...
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JPH09509918A |
PCT No. PCT/AU95/00112 Sec. 371 Date Oct. 28, 1996 Sec. 102(e) Date Oct. 28, 1996 PCT Filed Mar. 8, 1995 PCT Pub. No. WO95/24510 PCT Pub. Date Sep. 14, 1995A process for facilitating removal of one or more impurities from titaniferous ma...
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JPH09243788A |
To provide a method for separating actinoid elements from rare earth elements which has high separating efficiency (coefficient of separation) without requiring a strict concentration control, can easily fractionate the actinoid element ...
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JPH09194961A |
To easily produce a pure metal and an enriched uranium by using high frequency heating to make a specific metal atomic and further laser- ionizing. A metallic rod 1 for refining (or uranium for enriching) is melted and vaporized by a hig...
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JPH09124318A |
To reduce impurities of a radioactive nuclide to a permissible level in the case producing TiO2 by a chlorination method by carrying out specific treatment prior to reduction and baking, in a method for selecting out titanium- containing...
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JP2601856B2 |
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JP2532907Y2 |
A pulse nozzle of a reaction apparatus which obtains a very low temperature by expanding high-pressure and normal-temperature gas in heat insulation manner includes a fixed slit member disposed at an inlet of the nozzle and having a plur...
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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...
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JP2584853B2 |
Process for reextracting into aqueous solution plutonium present in an organic solvent, capable of being employed especially for uranium-plutonium separation. According to this process, the organic solvent is placed in contact with an ac...
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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...
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JP2562985B2 |
Process for obtaining metallic uranium from an oxidised uranium compound, characterised in that, in a first stage, this oxidised compound is treated with chlorine and carbon to obtain a chloride which is reduced, in a second stage, by el...
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JP2546798B2 |
PURPOSE:To obtain a readily handleable uranium adsorbent, consisting of a polyethyleneimine having a specific calix[n]arene derivative residue in the side chain and having excellent affinity and selectivity for uranyl ions. CONSTITUTION:...
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JP2542118B2 |
A method of converting uranium dioxide into a metallic uranium lump is provided The method comprises mixing a reducing agent comprised of metallic calcium, a slag solvent comprised of calcium chloride and a eutectic comprised of at least...
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JP2529457B2 |
A method of concentrating a plutonium nitrate solution comprising the steps of cooling the plutonium nitrate solution to a temperature of -60 DEG to -40 DEG C. to produce a frozen matter comprising water and nitric acid, and filtering th...
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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...
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JPH0833484B2 |
The disclosed invention is an improvement in the so-called "Purex" solvent extraction and separation process for recovering uranium from scrap material or spent fuel comprising treating the uranium containing scrap or spent fuel with nit...
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JPH0823598B2 |
PURPOSE:To enable an effective capture of radioactive substances, by providing an absorber filled part which is composed of an oxygen/hydrogen absorber, a radioactive corrosion products and a radioactive fission products absorber as a ra...
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JPH085675B2 |
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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...
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JPH07509279A |
PCT No. PCT/AU93/00381 Sec. 371 Date Apr. 6, 1995 Sec. 102(e) Date Apr. 6, 1995 PCT Filed Jul. 28, 1993 PCT Pub. No. WO94/03160 PCT Pub. Date Feb. 17, 1994A process for facilitating the removal of impurities e.g. radionuclides, such as u...
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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...
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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...
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JPH0761990B2 |
The invention relates to novel extracting agents and novel propane diamides, their use for the recovery of actinides and/or lanthanides and their preparation process. These extracting agents are constituted by propane diamides of formula...
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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...
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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...
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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...
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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 ...
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JPH06104573B2 |
The invention relates to a process for the extraction of uranium (VI) and/or plutonium (IV) present in an aqueous solution by means of N,N-dialkylamides. These N,N-dialkylamides are in accordance with formula: (I) in which R1 is a straig...
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JPH06104869B2 |
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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...
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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...
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JPH0675673B2 |
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JPH0675674B2 |
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JPH0672946B2 |
Process for separating off the technetium present in an organic solvent in the first stage of treatment of irradiated nuclear fuels. In the reprocessing plant the solvent leaving the extractor 1 contains uranium, plutonium, zirconium and...
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JPH0658431B2 |
Process for preventing the extraction of technetium and/or rhenium, particularly during the extraction of uranium and/or plutonium by an organic solvent. This process permitting the extraction of a chemical element, such as uranium or pl...
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JPH06506504A |
Magnesium is separated from magnesium slag containing radioactive thorium and its daughters by solubilizing magnesium from magnesium slurry using carbon dioxide and separating magnesium from magnesium slurry containing thorium and its da...
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JPH06505508A |
PCT No. PCT/FR92/01124 Sec. 371 Date Jul. 27, 1993 Sec. 102(e) Date Jul. 27, 1993 PCT Filed Dec. 2, 1992 PCT Pub. No. WO93/11113 PCT Pub. Date Jun. 5, 1993.The invention relates to a process for the selective extraction of (III) actinide...
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JPH0644074B2 |
A process for treating a waste water containing uranium and fluorine comprises a neutralizing precipitation step wherein slaked lime is added to the waste water containing uranium and fluorine and precipitate thus formed in separated and...
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