公开(公告)号：US20010033814A1

公开(公告)日：2001-10-25

申请号：US09845110

申请日：2001-04-27

发明人： Valeriy Nicholiavich Romanovskiy ,  Igor V. Smirnov ,  Vasiliy A. Babain ,  Terry A. Todd ,  Ken N. Brewer

IPC分类号： C22B060/02 ,  C22B026/20 ,  C22B026/10 ,  C22B059/00

CPC分类号： C01G56/001 ,  C22B3/004 ,  G21C19/46 ,  G21F9/125 ,  Y02P10/234 ,  Y02W30/883 ,  Y10S423/14

摘要： 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 wastes. More specifically, the invention relates to extracting agent solvent compositions comprising complex organoboron compounds, substituted polyethylene glycols, and neutral organophosphorus compounds in a diluent. The preferred solvent comprises a chlorinated cobalt dicarbollide, diphenyl-dibutylmethylenecarbamoylphosphine oxide, PEG-400, and a diluent of phenylpolyfluoroalkyl sulfone. The invention also provides a method of using the invention extracting agents to recover cesium, strontium, rare earths and actinides from liquid radioactive waste.

摘要翻译： 本发明涉及用于从液体放射性废物中选择性提取和回收放射性核素，特别是铯和锶，稀土和锕系元素的溶剂和方法。 更具体地，本发明涉及在稀释剂中包含复合有机硼化合物，取代的聚乙二醇和中性有机磷化合物的萃取剂溶剂组合物。 优选的溶剂包括二氯化钴二溴化物，二苯基 - 二丁基亚甲基氨基甲酰基氧化膦，PEG-400和苯基多氟烷基砜的稀释剂。 本发明还提供了使用本发明提取剂从液体放射性废物中回收铯，锶，稀土和锕系元素的方法。

公开(公告)号：US20030113247A1

公开(公告)日：2003-06-19

申请号：US09947349

申请日：2001-09-07

发明人： Harvinderpal Singh ,  Shyamkant Laxmidutt Mishra ,  Ravishankar Vijayalakshmi ,  Ashok Basawanthappa Giriyalkar ,  Chiranjib Kumar Gupta

IPC分类号： C22B060/02

CPC分类号： C22B60/0243 ,  C22B60/026

摘要： An improved process of extraction of uranium from phosphoric acid and in particular uranium VI from phosphoric acid especially strong phosphoric acid using a selective synergistic extractant mix of an organo-phosphorous acid and a neutral extraction agent. The process basically involves the steps of extraction comprising contacting said acid with a selective synergistic extractant system of di-nonyl phenyl phosphoric acid (DNPPA) and a neutral agent selected from di-butyl butyl phosphonate (DBBP) and tri-n-octyl phosphine oxide (TOPO); and recovering the uranium values from the loaded organic phase. The above process would provide for an improved process for recovery of uranium both from weak and strong phosphoric acids using a stable and relatively cheap extractant system. The process is directed to improved recovery of U-VI from phosphoric acid by way of a simple, industrially applicable and cost-effective process.

摘要翻译： 使用有机亚磷酸和中性提取剂的选择性协同萃取剂混合物，从磷酸，特别是磷酸提取铀的改进方法，特别是铀VI。 该方法基本上包括提取步骤，包括使所述酸与二壬基苯基磷酸（DNPPA）和选自二丁基膦酸二丁酯（DBBP）和三正辛基氧化膦的选择性协同提取剂体系 （TOPO）; 并从装载的有机相中回收铀值。 上述方法将提供使用稳定且相对便宜的萃取剂体系从弱磷酸和强磷酸回收铀的改进方法。 该方法旨在通过简单的工业应用和成本有效的方法从磷酸提高U-VI的回收率。

公开(公告)号：US20040247504A1

公开(公告)日：2004-12-09

申请号：US10486507

申请日：2004-02-11

发明人： Harvinderpal Singh ,  Shyamkant Laxmidutt Mishra ,  Anitha Mallavarapu ,  Vijayalakshmi Ravishankar ,  Ashok Giriyalkar ,  Manojkumar Kedarnath Kotekar ,  Tapan Kumar Mukherjee

IPC分类号： C22B060/02

CPC分类号： C22B3/0068 ,  C22B60/0243 ,  C22B60/026 ,  C22B60/0282 ,  Y02P10/234

摘要： 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) phosphoric acid (D2EHPA) and tri-n-butyl phosphate (TBP) with refined kerosene as synergistic extractant system on hydrogen peroxide treated phosphoric acid, and stripping the loaded extract with strong phosphoric acid containing metallic iron to lower redox potential. The loaded-stripped acid is diluted with water back to weak phosphoric acid state and its redox potential raised by adding hydrogen peroxide and re-extracted with same extractant system. This extract is first scrubbed with sulfuric acid and then stripped with alkali carbonate separating iron as a precipitate, treated with sodium hydroxide precipitating sodium uranate, which is re-dissolved in sulfuric acid and converted with hydrogen peroxide to highly pure yellow cake of uranium peroxide.

公开(公告)号：US20040052705A1

公开(公告)日：2004-03-18

申请号：US10247016

申请日：2002-09-18

发明人： Troy J. Tranter ,  Terry A. Todd ,  Leroy C. Lewis ,  Joseph P. Henscheid

IPC分类号： C22B060/02 ,  C01G057/00 ,  C01G043/00

CPC分类号： G21F9/06 ,  C22B60/0239 ,  C22B60/0291 ,  G21G4/08

摘要： 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 isotope is generated and collected from the first isotope. The invention includes a method of producing an actinium-225/bismuth-213 product from a material containing thorium-229 and thorium-232. A solution is formed containing nitric acid and the material and iodate is added to form a thorium iodate precipitate. A supernatant is separated from the thorium iodate precipitate and a second volume of nitric acid is added to the precipitate. The precipitate is stored and a decay product comprising actinium-225 and bismuth-213 is generated in the second volume of nitric acid which is then separated from the thorium iodate precipitate, filtered, and treated using at least one chromatographic procedure. The invention also includes a system for producing an actinium-225/bismuth-213 product.

摘要翻译： 本发明包括从溶液中含有至少两种同位素的混合物中分离同位素的方法。 第一同位素沉淀并从溶液中收集。 从第一个同位素产生和收集一个女儿同位素。 本发明包括从含有钍-229和钍-232的材料制备锕-225 /铋-213产物的方法。 形成含有硝酸的溶液，并加入物质和碘酸盐以形成碘酸钍沉淀物。 将上清液从碘化钍沉淀物中分离出来，向沉淀物中加入第二体积的硝酸。 储存沉淀物，并在第二体积的硝酸中产生包含锕-225和铋-213的衰变产物，然后将其从碘化钍沉淀中分离出来，过滤并使用至少一个色谱法进行处理。 本发明还包括用于制备锕-225 /铋-213产物的系统。

公开(公告)号：US20030127395A1

公开(公告)日：2003-07-10

申请号：US10177828

申请日：2002-06-21

发明人： Andrew H. Bond ,  John J. Hines ,  John E. Young ,  E. Philip Horwitz

IPC分类号： C22B060/02 ,  C02F001/42

CPC分类号： G21G1/0005 ,  B01D15/265 ,  B01D15/362 ,  B01J39/04 ,  G01N30/468 ,  G01N30/88 ,  G01N2030/085 ,  G01N2030/77 ,  G01N2030/8804 ,  G01N2030/8868 ,  G01N2030/8872 ,  G21G4/08

摘要： 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 medium and a processor. An uncoiled conduit extends between a third port of a second multi-port valve and a first multi-port valve. A processor is operably coupled to a pump, and the plurality of multi-port valves. A method for separating a solution of substantially impurity-free daughter product from an associated parent load solution is also disclosed.

摘要翻译： 用于分离基本上无杂质的子产物与相关母体负载溶液的无气体系统包括泵，多个多口阀，分离介质和处理器。 开卷管道在第二多口阀的第三端口和第一多口阀之间延伸。 处理器可操作地耦合到泵和多个多端口阀。 还公开了从相关的母体负载溶液中分离基本上无杂质的子产物的溶液的方法。

公开(公告)号：US20020111525A1

公开(公告)日：2002-08-15

申请号：US09902533

申请日：2001-07-09

发明人： Dhiraj Pal ,  Karl W. Yost ,  Steven A. Chisick

IPC分类号： C22B060/02

CPC分类号： G21F9/304 ,  B09B3/0041 ,  B09C1/08 ,  C02F11/008 ,  C02F2101/006 ,  C02F2101/20 ,  C04B28/34 ,  C04B28/342 ,  C04B28/344 ,  C04B28/346 ,  C04B2111/00767 ,  G21F9/302 ,  Y02W30/91 ,  C04B14/041 ,  C04B18/0472

摘要： A process for chemical fixation of radionuclides and radioactive compounds present in soils, solid materials, sludges and liquids. Radionuclides and other radioactive compounds are converted to low-temperature Apatite-Group structural isomorphs (general composition: (AB)5(XO4)3Z), usually phosphatic, that are insoluble, non-leachable, non-zeolitic, and pH stable by contacting with a suspension containing a sulfate, hydroxide, chloride, fluoride and/or silicate source and a phosphate anion. The Apatitic-structure end product is chemically altered from the initial material and reduced in volume and mass. The end product can be void of free liquids and exhibits sufficiently high levels of thermal stability to be effective in the presence of heat generating nuclear reactions. The process occurs at ambient temperature and pressure.

摘要翻译： 化学固定在土壤，固体物质，污泥和液体中的放射性核素和放射性化合物的过程。 放射性核素和其他放射性化合物通过接触被转化为低温磷灰石组结构同晶（通常组成：（AB）5（XO4）3Z），通常是磷酸盐，其是不溶的，不可浸出的，非沸石的和pH稳定的 含有硫酸盐，氢氧化物，氯化物，氟化物和/或硅酸盐源和磷酸盐阴离子的悬浮液。 磷灰石结构最终产品从初始材料化学改变，体积和质量减小。 最终产品可以没有游离液体，并且表现出足够高的热稳定性水平，以便在发生热反应的情况下有效。 该过程发生在环境温度和压力下。