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21.发明授权
公开(公告)号：US3510273A
公开(公告)日：1970-05-05
申请号：US3510273D
申请日：1967-04-06
申请人： REPUBLIC STEEL CORP
发明人： FITZHUGH EDWARD F JR , SEIDEL DON C
CPC分类号： C01G43/01 , C01G31/02 , C01G39/02 , C01P2006/80 , C22B3/46 , Y02P10/234
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22.发明授权Multicomponent fluid feed apparatus with preheater and mixer for a high temperature chemical reactor 失效具有高温化学反应器预热器和混合器的多组分流体输送装置
公开(公告)号：US5935528A
公开(公告)日：1999-08-10
申请号：US783512
申请日：1997-01-14
CPC分类号： B01J12/02 , B01J19/26 , B01J8/1827 , C01G43/01 , C01G43/025 , B01J2219/00099 , B01J2219/00119 , B01J2219/00135 , B01J2219/00159
摘要： A multicomponent fluid feed apparatus is disclosed that independently preheats and then mixes two or more fluid streams being introduced into a high temperature chemical reactor to promote more rigorous and complete reactions using assemblies of inert tubular elements and an integral mixing orifice plate. The design allows use of ceramic and speciality alloy materials for high temperature service with particularly corrosive halide feeds such as UF.sub.6 and HF. Radiant heat transfer to the tubular elements from external means gives the necessary system high temperatures without excessive temperatures to cause material failure. Preheating of the gaseous reactants in a separate step prior to mixing and injecting the gaseous reactants into a high temperature chemical reactor was found to provide an improved thermal conversion of UF.sub.6 to uranium oxides.
摘要翻译： 公开了一种多组分流体输送装置，其独立地预热然后将引入到高温化学反应器中的两种或更多种流体流混合，以使用惰性管状元件和整体混合孔板的组件来促进更严格和完整的反应。 该设计允许使用陶瓷和特种合金材料进行高温维护，特别是腐蚀性卤化物进料如UF6和HF。 从外部装置向管状元件的辐射热传递给出必要的系统高温，而没有过多的温度导致材料失效。 发现在气态反应物混合并将气态反应物注入高温化学反应器之前，在单独的步骤中预热气态反应物以提供UF 6与氧化铀的改进的热转化。
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公开(公告)号：US4243637A
公开(公告)日：1981-01-06
申请号：US840791
申请日：1977-10-11
申请人： James L. Bradford , Fernando Ore
发明人： James L. Bradford , Fernando Ore
IPC分类号： C01B25/238 , C22B60/02 , C01G43/00 , C01G43/02
CPC分类号： C01B25/238 , C22B60/026
摘要： Impure phosphoric acid containing uranium values is pretreated with a water immiscible organic sulfonic acid, preferably in conjunction with a water immiscible organic acid phosphate compound, for extraction of ionic metallic impurities and organic impurities to produce pretreated phosphoric acid containing uranium values. Pretreated phosphoric acid is contacted with a water immiscible extractant comprising an organic uranium-extracting agent, preferably an organophosphorus compound, dissolved in a water immiscible organic diluent to produce uranium-depleted phosphoric acid and uranium-enriched extractant. Uranium is recovered from the uranium-enriched extractant.
摘要翻译： 含有不纯的含铀价值的磷酸用水不混溶的有机磺酸预处理，优选与水不混溶的有机酸式磷酸盐化合物结合，用于萃取离子金属杂质和有机杂质以产生含有铀值的预处理磷酸盐。 将预处理的磷酸与包含溶解在与水不混溶的有机稀释剂中的有机铀提取剂，优选有机磷化合物的水不混溶的萃取剂接触以产生贫铀磷酸和富铀萃取剂。 从富铀萃取剂中回收铀。
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公开(公告)号：US4060497A
公开(公告)日：1977-11-29
申请号：US638662
申请日：1975-12-08
申请人： Hans Huschka , Martin Kadner
发明人： Hans Huschka , Martin Kadner
摘要： Uniform spherical fuel and/or fertile particles are formed by conversion of an oscillating liquid stream of a uranium and/or thorium compound solution flowing from at least one nozzle in an amount of more than 3,000 drops per minute by allowing these drops to fall into an ammonia solution and subsequently drying and sintering the particles thus formed. Before immersion in the ammonia solution the drops are first allowed to pass through a falling zone free of ammonia, this zone is so regulated that the drops have taken on their exact spherical form and then the drops are passed through a second falling zone containing flowing ammonia gas, whereby the ammonia gas is introduced into this second falling zone through at least one inlet conduit in such manner that there is guaranteed not only an ammonia gas flow in the opposite direction to that of the falling drops but also a horizontal cross current of the ammonia gas through the space between the drops and this second falling zone is so regulated that the spherical drops are sufficiently hardened before immersion in the ammonia solution.
摘要翻译： 通过使来自至少一个喷嘴的铀和/或钍化合物溶液的振荡液体流以每分钟3000滴以上的量转化而形成均匀的球形燃料和/或可育颗粒， 然后干燥和烧结由此形成的颗粒。 在浸入氨溶液之前，首先允许液滴通过没有氨的下落区域，该区域受到如此调节，使得液滴具有准确的球形，然后液滴通过含有流动氨的第二下降区域 气体，由此氨气通过至少一个入口管道被引入该第二落下区域，使得不仅保证氨气流与落下的液滴的方向相反的方向流动，而且还保证了 通过液滴和该第二下降区之间的空间的氨气被调节，使得球滴在浸入氨溶液之前被充分硬化。
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25.发明授权
公开(公告)号：US4024216A
公开(公告)日：1977-05-17
申请号：US592376
申请日：1975-07-02
申请人： Robert E. Finch , Robert H. Scala
发明人： Robert E. Finch , Robert H. Scala
CPC分类号： C01G43/01 , B03B9/00 , C22B60/0278 , C01P2006/80
摘要： Uranium yields, derived from alkaline leaching of a uranium ore, are increased and at the same time the need for fresh water to dissolve a flocculant is eliminated by using sodium polyacrylate as the flocculant, diluted with and dissolved by system water.
摘要翻译： 来自铀矿的碱性浸出的铀产量增加，同时通过使用聚丙烯酸钠作为絮凝剂消除淡水溶解絮凝剂的需要，用系统水稀释并溶解。
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公开(公告)号：US3966873A
公开(公告)日：1976-06-29
申请号：US411886
申请日：1973-11-01
CPC分类号： C22B60/026 , Y02P10/212
摘要： Uranium is separated from contaminating cations in an aqueous liquor containing uranyl ions. The liquor is mixed with sufficient recycled uranium complex to raise the weight ratio of uranium to said cations preferably to at least about three. The liquor is then extracted with at least enough non-interfering, water-immiscible, organic solvent to theoretically extract about all of the uranium in the liquor. The oganic solvent contains a reagent which reacts with the uranyl ions to form a complex soluble in the solvent. If the aqueous liquor is acidic, the organic solvent is then scrubbed with water. The organic solvent is stripped with a solution containing at least enough ammonium carbonate to pecipitate the uranium complex. A portion of the uranium complex is recycled and the remainder can be collected and calcined to produce U.sub.3 O.sub.8 or UO.sub.2.
摘要翻译： 铀与含有铀酰离子的含水液体中的污染阳离子分离。 将该液体与足够的再循环铀配合物混合以提高铀与所述阳离子的重量比优选至少约3。 然后用至少足够的无干扰，水不混溶的有机溶剂萃取液体，以理论上提取酒中所有的铀。 有机溶剂含有与铀酰离子反应形成可溶于溶剂的络合物的试剂。 如果含水液体是酸性的，则用水洗涤有机溶剂。 有机溶剂用含有至少足够的碳酸铵的溶液汽提，以捣固铀配合物。 铀络合物的一部分被再循环，其余部分可被收集并煅烧以产生U3O8或UO2。
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公开(公告)号：US3941870A
公开(公告)日：1976-03-02
申请号：US326537
申请日：1973-01-24
CPC分类号： C01G43/066
摘要： The production of UF.sub.6 in which UF.sub.4 is reacted with air or oxygen in the presence of a catalyst at 500.degree. to 700.degree.C. The solid byproduct of this reaction is reduced with hydrogen in the presence of a catalyst at 400.degree. to 600.degree.C. Fresh UO.sub.3 may also be reduced with hydrogen in the same reactor as UO.sub.2 F.sub.2. The reduction product or products are reacted with hydrogen fluoride at 400.degree. to 600.degree.C, producing UF.sub.4 which would be recycled for further reaction to produce UF.sub.6.
摘要翻译： 在500℃〜700℃下，在催化剂存在下，UF4与空气或氧气反应的UF6的生成。该反应的固体副产物在催化剂存在下在400〜600℃下用氢气还原 新鲜的UO3也可以在与UO2F2相同的反应器中用氢还原。 还原产物在400〜600℃下与氟化氢反应，生成UF4，再循环再进行反应生成UF6。
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公开(公告)号：US3937784A
公开(公告)日：1976-02-10
申请号：US418731
申请日：1973-11-23
申请人： Richard Beutner , Friedrich Ploger
发明人： Richard Beutner , Friedrich Ploger
IPC分类号： C01G43/025 , C01G56/00 , C01G43/02
CPC分类号： C01G56/005 , C01G43/025 , C01P2006/80
摘要： A fluorine containing heavy-metal oxide powder, particularly UO.sub.2 powder, is subjected to a pyrohydrolysis treatment under the most complete exclusion of hydrogen.
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公开(公告)号：US3880980A
公开(公告)日：1975-04-29
申请号：US31101272
申请日：1972-11-30
申请人： ALLIED CHEM
发明人： WAMSER CHRISTIAN A
IPC分类号： C01B25/234 , C01G43/01 , C01G43/06 , C22B60/02 , C01G43/02
CPC分类号： C22B60/0265 , C01B25/234 , C01G43/01 , C01G43/06
摘要： Uranium is recovered from a solution containing phosphoric acid, uranium in the hexavalent state and a chloride salt from the group consisting of alkali metal chloride, alkaline earth metal chloride, ammonium chloride and mixtures thereof, such as a solution obtained by hydrochloride acid digestion of phosphate rock. The phosphoric acid is extracted from the solution before the uranium is recovered from the remaining constituents thereof. Extraction degradation and emulsification of the organic layer previously employed in organic solvent extraction methods are eliminated, and the uranium is recovered at low cost and in a highly efficient manner.
摘要翻译： 从含有磷酸，六价态的铀和由碱金属氯化物，碱土金属氯化物，氯化铵及其混合物组成的组的氯化物溶液中回收铀，例如通过盐酸酸解磷酸盐 岩。 在从其剩余成分回收铀之前，从溶液中提取磷酸。 先前在有机溶剂萃取方法中使用的有机层的提取降解和乳化被消除，并且以低成本和高效率的方式回收铀。
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公开(公告)号：US3869536A
公开(公告)日：1975-03-04
申请号：US8890470
申请日：1970-11-12
发明人： JAMES DEAN B
CPC分类号： B01D59/30 , G01N30/02 , B01D15/422
摘要： A salient part of the disclosure describes a method for separating U235 isotope from U238 isotope comprising introducing a solution containing a reducing cation such as Ti 3 into a cation-exchange resin column, thereafter introducing a uranyl solution containing both U235 and U238 isotopes, followed by introduction of a solution containing an oxidizing agent such as Fe 3 and thereafter separately recovering uranyl solutions containing uranium which is enriched in U235 isotope and uranium which is correspondingly depleted in U235 isotope.
摘要翻译： 本公开的重要部分描述了一种从U238同位素中分离U235同位素的方法，包括将含有还原阳离子如Ti 2+的溶液引入阳离子交换树脂柱中，之后引入含有U235和U238同位素两者的铀酰溶液 ，然后引入含有Fe 3+的氧化剂的溶液，然后分别回收含有U235同位素和相当于U235同位素耗尽的铀的含有铀的铀酰溶液。
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