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31. 发明授权

US4476099A Method of recovering uranium 失效
标题翻译：回收铀的方法
公开(公告)号：US4476099A
公开(公告)日：1984-10-09
申请号：US219715
申请日：1980-12-24
申请人： Floyd E. Camp , Amy B. Swartzlander
发明人： Floyd E. Camp , Amy B. Swartzlander
IPC分类号： C22B60/02 , C01G43/00
CPC分类号： C22B60/0282 , C22B60/026 , C22B60/0278
摘要： Uranium is recovered from a carbonate leach solution containing a dissolved uranium salt and a monovalent ion. The pH of the leach solution is adjusted to about 5 to about 7.5, and preferably to about 6 to about 7. Phosphate ion is then added to typical in-situ leach solutions in an amount from about 10 to about 30 mole % in excess of the amount needed to stoichiometrically react with the uranium in said solution. This results in the precipitation of a compound made up of the monovalent ion, uranium, and the phosphate ion, which is insoluble in the solution. The precipitate is then separated from the solution preferably by means of a centrifuge or a vortex clarifier. It can then be dissolved in acid, and the uranium extracted into an organic solvent such as DEHPA-TOPA in kerosene.
摘要翻译：从含有溶解的铀盐和一价离子的碳酸盐浸出液中回收铀。将浸出溶液的pH调节至约5至约7.5，优选至约6至约7.然后将磷酸根离子加入到典型的原位浸提溶液中，其量为约10至约30摩尔％，超过与所述溶液中的铀化学计量地反应所需的量。这导致由不溶于溶液的一价离子，铀和磷酸根离子组成的化合物沉淀。然后将沉淀物优选通过离心机或涡流澄清器从溶液中分离出来。然后将其溶解在酸中，并将铀萃取到有机溶剂如DEHPA-TOPA中的煤油中。

32. 发明授权

US4461746A Reduction of iron in a reductive stripping process for the recovery of uranium from wet process phosphoric acid 失效
标题翻译：在还原汽提过程中还原铁，用于从湿法磷酸中回收铀
公开(公告)号：US4461746A
公开(公告)日：1984-07-24
申请号：US349026
申请日：1982-02-16
申请人： Laurence W. Bierman , Samual M. Polinsky
发明人： Laurence W. Bierman , Samual M. Polinsky
IPC分类号： C01G43/00 , C22B60/02
CPC分类号： C01G43/00 , C22B60/0282
摘要： A two stage reductive stripping process for recovering uranium from wet process phosphoric acid, wherein the ferrous ions required for the first-stage reductive strip are supplied by heating a portion of acid raffinate phosphoric acid from the first-stage extraction in the presence of pressurized hydrogen gas. The pressurized hydrogen gas reduces the ferric ions in the raffinate to the ferrous state without any addition of metallic iron or other impurity, so that the uranium-enhanced reductive strip solution supplied to the second stage from the first stage reductive strip has a low concentration of iron impurity, and no further purification to remove iron impurity is required.
摘要翻译：用于从湿法磷酸中回收铀的二级还原脱除方法，其中第一级还原带所需的亚铁离子通过在加压氢气存在下从第一阶段萃取中加热一部分酸性残液磷酸而得到加油站。加压氢气将提余液中的铁离子还原成亚铁状态，而不会添加金属铁或其他杂质，使得从第一级还原带供应到第二级的铀增强还原带溶液的浓度低铁杂质，并且不需要进一步纯化以除去铁杂质。

33. 发明授权

US4460547A Separating actinide ions from aqueous, basic, carbonate containing solutions using mixed tertiary and quaternary amino anion exchange resins 失效
标题翻译：使用混合的叔和季氨基阴离子交换树脂从含水，碱性，含碳酸盐溶液中分离锕系离子
公开(公告)号：US4460547A
公开(公告)日：1984-07-17
申请号：US437511
申请日：1982-10-28
申请人： Ali Sameh , Jurgen Haag
发明人： Ali Sameh , Jurgen Haag
IPC分类号： C01G43/00 , B01J20/22 , B01J20/26 , B01J41/04 , C01G56/00 , C02F1/42 , C22B60/02 , G21C19/46 , G21F9/00 , G21F9/06 , G21F9/12
CPC分类号： C01G56/002 , B01J41/04 , C22B3/42 , Y02P10/234
摘要： A process for the separation of actinide ions from aqueous, basic, carbonate containing solutions with the use of basic ion exchangers. The actinide ions are sorbed at a weakly basic anion exchanger comprised of a polyalkene matrix provided in the majority with tertiary and in the minority with quaternary amino groups. The charged ion exchanger is separated from the solution and then the actinide ions are eluted from the exchanger with nitric acid.
摘要翻译：使用碱性离子交换剂从含水，碱性，含碳酸盐溶液中分离锕系离子的方法。锕系离子在弱碱性阴离子交换剂中吸附，该阴离子交换剂由大多数具有叔胺的聚烯烃基质组成，少数含有季氨基。将带电离子交换剂与溶液分离，然后用硝酸从交换器洗脱锕系离子。

34. 发明授权

US4451438A Process for recovering niobium and/or tantalum metal compounds from such ores further containing complexes of uranium, thorium, titanium and/or rare earth metals 失效
标题翻译：从这样的矿石中回收铌和/或钽金属化合物的方法，还含有铀，钍，钛和/或稀土金属络合物
公开(公告)号：US4451438A
公开(公告)日：1984-05-29
申请号：US427244
申请日：1982-09-29
申请人： Wilfried Floeter , Gerhard Schoening , Klaus Schroeer
发明人： Wilfried Floeter , Gerhard Schoening , Klaus Schroeer
IPC分类号： C22B3/26 , C22B34/12 , C22B34/24 , C22B60/00 , C22B60/02 , C01G43/00 , C01F15/00 , C01G33/00 , C01G35/00
CPC分类号： C22B60/0291 , C22B3/0021 , C22B34/125 , C22B34/24 , C22B60/00 , C22B60/0208 , C22B60/0226 , C22B60/023 , C22B60/0234 , C22B60/0239 , C22B60/0247 , C22B60/0278 , Y02P10/234
摘要： A process for recovering one or more non-radioactive transition metal compounds from an ore containing one or more compounds of said transition metal or metals and further containing at least one complex of a member selected from the group consisting of uranium, thorium, radium, titanium, and rare earth metals, which comprises decomposing said ore in crushed condition by means of an acid so that a portion of the ore is brought into solution in a liquid phase and another portion of the ore remains in a solid phase, said compound or compounds of the transition metal or metals to be recovered passing into only the liquid or into only the solid phase, the uranium in the crushed ore being treated so as to cause substantially all of said uranium to be present in an oxidation state in which it cannot, during the decomposition step, pass into the phase containing the transition metal compound or compounds.
摘要翻译：一种从含有一种或多种所述过渡金属或金属化合物的矿石中回收一种或多种非放射性过渡金属化合物的方法，还含有至少一种选自铀，钍，镭，钛的成员络合物和稀土金属，其包括通过酸在粉碎状态下分解所述矿石，使得一部分矿石在液相中溶解并且另一部分矿石保持在固相中，所述化合物或化合物的待回收的过渡金属或金属仅通过液体或仅进入固相，处理的粉碎矿石中的铀基本上使所有的铀基本上以不能在其中的氧化态存在，在分解步骤期间，进入含有过渡金属化合物或化合物的相。

35. 发明授权

US4442071A Extraction of plutonium ions from aqueous sulfuric acid solutions with D.sub.2 EHPA or D.sub.2 EHPA/TOPO 失效
标题翻译：用D2EHPA或D2EHPA / TOPO从硫酸水溶液中提取钚离子
公开(公告)号：US4442071A
公开(公告)日：1984-04-10
申请号：US286168
申请日：1981-07-23
申请人： Karl H. Lieser , Bernd Stojanik
发明人： Karl H. Lieser , Bernd Stojanik
IPC分类号： B01D11/04 , C01G56/00 , C22B3/32 , C22B3/38 , C22B3/40 , C22B60/04 , G21F9/06 , C01G43/00
CPC分类号： C22B3/0095 , C01G56/001 , C01G56/003 , C22B3/0025 , C22B3/0068 , C22B3/0091 , C22B60/04 , Y02P10/234
摘要： Method for separating plutonium ions from an aqueous solution containing sulfuric acid. The method comprises introducing into the aqueous solution 0.1 to 1.5 moles of nitrate ions per liter of aqueous solution. To the aqueous solution containing nitrate ions, there is added an organic phase comprising a solution of 0.1 to 1.0 M di-2-ethylhexylphosphoric acid in kerosene in a volume ratio of the aqueous solution containing nitrate ions to the organic phase of between 1:1 and 4:1 to extract the plutonium ions into the organic phase. The organic phase containing plutonium ions is then separated from the aqueous solution. A re-extractant aqueous solution containing 0.2 to 1.0 M oxalic acid, and 0 to 0.5 M nitric acid is then added to the separated organic phase to re-extract the plutonium ions into the re-extractant aqueous solution. The re-extractant aqueous solution containing plutonium ions is then separated from the organic phase.
摘要翻译：从含有硫酸的水溶液中分离钚离子的方法。该方法包括每升水溶液将0.1-1.5摩尔硝酸根离子引入水溶液中。向含有硝酸根离子的水溶液中加入有机相，其中含有0.1〜1.0M二-2-乙基己基磷酸的煤油溶液，其含有硝酸根离子与有机相的水溶液的体积比为1:1 和4：1以将钚离子萃取到有机相中。然后将含有钚离子的有机相与水溶液分离。然后将含有0.2〜1.0M草酸和0〜0.5M硝酸的再萃取剂水溶液加入到分离的有机相中，将钚离子重新萃取到再萃取剂水溶液中。然后将含有钚离子的再萃取剂水溶液与有机相分离。

36. 发明授权

US4430308A Heated ion exchange process for the recovery of uranium 失效
标题翻译：用于回收铀的加热离子交换过程
公开(公告)号：US4430308A
公开(公告)日：1984-02-07
申请号：US449125
申请日：1982-12-13
申请人： Argell Fletcher
发明人： Argell Fletcher
IPC分类号： C22B60/02 , C01G43/00
CPC分类号： C22B60/0265
摘要： The present invention relates to an improved method for the recovery of uranium values from a uranium-containing lixiviant by passing the lixiviant through a heated ion exchange resin to cause the resin to retain uranium values. The uranium values are subsequently recovered from the ion-exchange resin.
摘要翻译：本发明涉及一种用于通过使浸出剂通过加热的离子交换树脂来回收铀含量的改进方法，以使树脂保留铀值。随后从离子交换树脂中回收铀值。

37. 发明授权

US4428910A PROCESS FOR STRIPPING URANIUM FROM ALKYL PYROPHOSPHORIC ACID 失效
标题翻译：从碱性磷酸中分离铀的方法
公开(公告)号：US4428910A
公开(公告)日：1984-01-31
申请号：US26747381
申请日：1981-05-27
申请人： PRODECO INC
发明人： WORTHINGTON RALPH E , MAGDICS ALEX
IPC分类号： B01D11/04 , C01B25/238 , C01G20060101 , C01G43/00 , C22B60/02
CPC分类号： C22B60/026 , Y02P10/212
摘要： A process is described for the recovery of tetravalent uranium from wet-process phosphoric acid utilizing an alkyl pyrophosphoric acid extractant or the like. After extracting the tetravalent uranium from wet-process acid, iron is stripped from the pregnant extractant into an oxalic acid stripping solution and then the tetravalent uranium is stripped from the pregnant extractant into an oxalate stripping solution. The oxalate stripping solution is an aqueous solution of an alkali metal or ammonium oxalate. The barren extractant is recycled for contacting with fresh wet-process acid. The uranium is oxidized and then precipitated in the oxalate stripping solution. The precipitated solids are separated from the solution, and the uranium is dried to a UO3 product.
摘要翻译：描述了使用烷基焦磷酸萃取剂等从湿法磷酸中回收四价铀的方法。从湿法酸提取四价铀后，将铁从怀孕的萃取剂中剥离成草酸剥离溶液，然后将四价铀从怀孕的萃取剂中剥离成草酸溶液。草酸盐剥离溶液是碱金属或草酸铵的水溶液。贫瘠的萃取剂被再循环用于与新鲜的湿法酸接触。铀被氧化，然后在草酸盐剥离溶液中沉淀。将沉淀的固体与溶液分离，并将铀干燥成UO 3产物。

38. 发明授权

US4427640A Sequential process for extraction and recovery of vanadium and uranium from wet process acids 失效
标题翻译：从湿法酸提取和回收钒和铀的顺序过程
公开(公告)号：US4427640A
公开(公告)日：1984-01-24
申请号：US194444
申请日：1980-10-06
申请人： P. David Bowerman , Michael F. Lucid
发明人： P. David Bowerman , Michael F. Lucid
IPC分类号： C01G31/00 , C01G43/00 , C22B3/38 , C22B60/02
CPC分类号： C01G43/00 , C01G31/003 , C22B3/0052 , C22B3/0091 , C22B60/026 , Y02P10/234
摘要： A process for preferentially extracting and recovering vanadium and uranium from wet process acids. The wet process acid first is contacted with a neutral organo-phosphorus compound to extract the vanadium values. The resulting loaded organic phase is separated from the wet process acid due to immiscibility of the acid and organic phases. The vanadium values then are separated from the organic phase by stripping. The raffinate separated from the first organic extractant then is contacted with a second organic extractant comprising a dialkylphosphoric acid and a neutral organo-phosphorus compound to extract the uranium values. The resulting loaded organic phase is separated from the wet process acid due to immiscibility of the acid and organic phases. The organic phase is stripped with a reductive stripping solution and the stripping solution then is oxidized to convert the uranium values to the hexavalent oxidation state. The oxidized solution then is contacted with another organic extractant to reextract the uranium to thereby concentrate the uranium product which then is stripped from the organic product with ammonium carbonate to form ammonium uranyl carbonate.
摘要翻译：从湿法酸中优先提取和回收钒和铀的方法。首先将湿法酸与中性有机磷化合物接触以提取钒值。由于酸和有机相的不混溶，所得负载的有机相与湿法酸分离。然后通过汽提将钒值与有机相分离。然后将与第一有机萃取剂分离的萃余液与包含二烷基磷酸和中性有机磷化合物的第二有机萃取剂接触以提取铀值。由于酸和有机相的不混溶，所得负载的有机相与湿法酸分离。有机相用还原汽提溶液汽提，然后将汽提溶液氧化，将铀值转化为六价氧化态。然后将氧化溶液与另一种有机萃取剂接触以再提取铀，从而浓缩铀产物，然后用碳酸铵从有机产物中汽提出铀产物，形成碳酸铀酰铵。

39. 发明授权

US4425307A Hydrogen peroxide in sulfuric acid extraction of uranium ores 失效
标题翻译：过氧化氢在硫酸中提取铀矿
公开(公告)号：US4425307A
公开(公告)日：1984-01-10
申请号：US256675
申请日：1981-04-22
申请人： Frederick W. DeVries
发明人： Frederick W. DeVries
IPC分类号： C22B60/02 , E21B43/28 , C01G43/00 , C22B3/00
CPC分类号： C22B60/0234 , E21B43/28
摘要： Uranium can be extracted from its ores at a pH of 2.5 to 5.5 using sulfuric acid, hydrogen peroxide, trace of iron and a sulfate. The extraction process is applicable to both tank leaching of conventionally mined ores and in situ leaching.
摘要翻译：可以使用硫酸，过氧化氢，痕量的铁和硫酸盐，在2.5至5.5的pH值下从其矿石中提取铀。提取工艺适用于常规开采的矿石和原位浸出两种罐体浸出。

40. 发明授权

US4416860A Method and apparatus for recovering raw material, especially uranium, from natural waters, especially from the sea 失效
标题翻译：从天然水，特别是海洋中回收原料，特别是铀的方法和设备
公开(公告)号：US4416860A
公开(公告)日：1983-11-22
申请号：US262829
申请日：1981-05-12
申请人： Dieter Heitkamp , Peter Inden
发明人： Dieter Heitkamp , Peter Inden
IPC分类号： B01D15/00 , B01D15/02 , B01J20/28 , B01J47/00 , B01J47/018 , C01G43/00 , C02F1/62 , C22B60/02 , E21C45/00 , C02F1/28
CPC分类号： B01J20/28014 , B01D15/02 , B01J20/28004 , B01J20/28019 , B01J20/28021 , B01J20/28023 , B01J20/28042 , B01J20/28045 , B01J20/2805 , B01J47/007 , C22B60/0265 , E21C50/00 , B01D2215/021
摘要： A method and apparatus for recovering raw material, especially uranium, f natural waters, especially from the sea. Carrier bodies capable of sinking are permitted to pass, in a free fall, through a layer of water, especially a natural sea current or stream, by concentration on the carrier bodies, which are collected at an appropriate depth and are then conveyed from there for further treatment. Carrier bodies of inert material are used having a protected outer surface with a thin layer, capable of being concentrated, coated thereon. The distance of falling amounts to approximately 100 meters. The apparatus for carrying out the method includes a carrier body discharge located below water level. One end of a carrier body path has a collection device for collecting carrier bodies and is directed toward the conveyor path. The apparatus also has a conveying device operating especially hydraulically according to the principle of communicating pipes. The conveying device returns the carrier bodies to the outlet or discharge by way of a further treatment location.
摘要翻译：从天然水，特别是海洋中回收原材料，特别是铀的方法和装置。允许下沉的载体能够自由落体通过一层水，特别是天然海流或流，通过集中在载体上，这些载体在适当的深度被收集，然后从那里传送出来进一步治疗。使用惰性材料的载体，其具有被保护的外表面，其具有可以被浓缩的薄层。下降距离约为100米。用于执行该方法的装置包括位于水位下方的载体体排出物。载体主体路径的一端具有用于收集载体的收集装置并被引向输送路径。该设备还具有根据连通管道的原理特别液压地操作的输送装置。输送装置通过另外的处理位置将载体返回出口或排出。

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