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公开(公告)号：US11594344B2
公开(公告)日：2023-02-28
申请号：US16770836
申请日：2018-12-07
发明人： François Poncelet , Nicolas Vigier , Bénédicte Arab-Chapelet , Aurélie Gauthe , Eléonore Welcomme , Marie Hélène Noire
摘要： A method for preparing a powder comprising an intimate mixture of U3O8 particles and PuO2 particles and which may further comprise particles of ThO2 or NpO2. The method comprises: preparing, via oxalic precipitations, an aqueous suspension S1 of particles of uranium(IV) oxalate and an aqueous suspension S2 of particles of plutonium(IV) oxalate; mixing the aqueous suspension S1 with the aqueous suspension S2 to obtain an aqueous suspension S1+2; separating the aqueous suspension S1+2 into an aqueous phase and a solid phase comprising the particles of uranium(IV) oxalate and the particles of plutonium(IV) oxalate; and calcining the solid phase to convert (1) the particles of uranium(IV) oxalate to particles of triuranium octoxide and (2) the particles of plutonium(IV) oxalate to particles of plutonium(IV) dioxide, whereby the powder is obtained.
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公开(公告)号：US11285534B2
公开(公告)日：2022-03-29
申请号：US16147347
申请日：2018-09-28
摘要： A method loading powder into a mold can include immersing the mold comprising one or more microchannels into a suspension comprising the powder and a surfactant suspended in a dispersant, wherein the powder comprises particles having an average particle size of less than 100 μm, wherein the mold is substantially entirely covered by the suspension; heating the suspension having the mold immersed therein under a temperature condition suitable to lower the stability of the particles of the powder in the suspension such that the particles settle out of solution and into the one or more microchannels; and applying an ultrasonic wave to the heated suspension to further settle the particles of the powder into the one or more microchannels thereby filling the one or more microchannels of the mold with the powder.
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3.发明申请公开(公告)号：US20190300384A1
公开(公告)日：2019-10-03
申请号：US15936615
申请日：2018-03-27
摘要： One-step solution combustion synthesis (SCS) methods for fabricating durable crystalline transuranic-doped rare earth zirconium pyrochlores are described. Methods are fast, amenable to upscaling, and present a simple strategy for producing crystalline ceramic materials that meet the minimum attractiveness criteria for special nuclear material. The methods include analysis of reactants and reaction conditions to select proper fuel as well as proper fuel content so as to encourage formation of the crystalline product in a single-step synthesis procedure.
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4.发明申请公开(公告)号：US20180286527A1
公开(公告)日：2018-10-04
申请号：US15768780
申请日：2016-10-18
发明人： Xavier Heres , Gilles Bernier , Binh Dinh , Patrick Pochon , Danièle Sans , Elisabeth Zekri
CPC分类号： G21C19/46 , C01G56/001 , G21F9/06 , G21F9/125 , Y02W30/883
摘要： The use of hydroxyiminoalkanoic acids including at least four carbon atoms as anti-nitrous agents in operations of reductive stripping of plutonium. The invention may be useful in any method for processing spent nuclear fuels that includes one or more operations of reductive stripping of plutonium and, more particularly, in the PUREX method as implemented in modern nuclear fuel processing plants, as well as in processes derived therefrom.
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公开(公告)号：US10005676B2
公开(公告)日：2018-06-26
申请号：US15031105
申请日：2014-10-22
CPC分类号： C01G43/025 , C01G43/00 , C01G56/004 , C01G56/005 , C01G56/007 , C01P2002/50 , G21C3/623 , G21C19/46 , G21C21/02 , Y02E30/38 , Y02W30/883
摘要： A method for preparing a powder of a solid solution of dioxide of uranium and of at least one other actinide and/or lanthanide element comprising combusting a solution that comprises uranyl nitrate and at least one nitrate of the other actinide and/or lanthanide element and glycine, with the glycine being used in a predetermined amount so as to form, at the end of the combustion, the solid solution.
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6.发明申请PROCESS FOR PREPARING AN OXYHALOGENIDE AND/OR OXIDE OF ACTINIDE(S) AND/OR OF LANTHANIDE(S) FROM A MEDIUM COMPRISING AT LEAST ONE MOLTEN SALT 有权从含有至少一个盐的中间体制备丙二酸和/或氧化亚锡（S）和/或兰沙坦（S）的方法公开(公告)号：US20140219900A1
公开(公告)日：2014-08-07
申请号：US14345855
申请日：2012-09-25
发明人： Annabelle Laplace , Jean-Francois Vigier , Thierry Plet , Catherine Renard , Francis Abraham , Cyrine Slim , Sylvie Delpech , Gerard Picard
CPC分类号： C01G56/005 , C01F17/0043 , C01F17/0056 , C01F17/0068 , C01G43/01 , C01G43/025 , C01P2002/88 , C01P2004/20 , C01P2004/38 , G21C19/48 , G21F9/308 , Y02W30/884
摘要： The invention relates to a process for manufacturing an oxychloride or oxide of actinide(s) and/or of lanthanide(s) from a chloride of actinide(s) and/or of lanthanide(s) present in a medium comprising at least one molten salt of chloride type comprising a step of bringing said chloride of actinide(s) and/or lanthanide(s) present in said medium comprising at least one molten salt of chloride type into contact with a wet inert gas.
摘要翻译： 本发明涉及一种从介质中存在的介于锕系元素和/或镧系元素的氯化物中制备氯化an或锕系氧化物的方法，该方法包括至少一种熔融 氯化物类型的盐包括使包含至少一种氯化物型熔融盐的所述介质中存在的锕系元素和/或镧系元素的氯化物与湿惰性气体接触的步骤。
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公开(公告)号：US08475746B2
公开(公告)日：2013-07-02
申请号：US13099088
申请日：2011-05-02
申请人： Kyeong-Woo Chung , Chul-Joo Kim , Ho-Sung Yoon
发明人： Kyeong-Woo Chung , Chul-Joo Kim , Ho-Sung Yoon
CPC分类号： C22B60/0265 , G21F9/12
摘要： Disclosed herein is a uranium ion exchange adsorption method using ultrasound. The method includes placing a slurry obtained by mixing uranium ions, sulfuric acid and an ion exchange resin into a reaction bath, and stirring the slurry in the reaction bath while simultaneously applying ultrasound to the reaction bath to allow the uranium ions to be adsorbed to the ion exchange resin through ion exchange adsorption. The method has an improved ion exchange adsorption rate of the uranium ions.
摘要翻译： 本文公开了使用超声波的铀离子交换吸附方法。 该方法包括将通过将铀离子，硫酸和离子交换树脂混合获得的浆料放入反应浴中，并在反应浴中搅拌浆料同时向反应槽施加超声波，以使铀离子被吸附到 离子交换树脂通过离子交换吸附。 该方法具有改善的铀离子的离子交换吸附率。
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公开(公告)号：US08470269B2
公开(公告)日：2013-06-25
申请号：US13099089
申请日：2011-05-02
申请人： Kyeong-Woo Chung , Chul-Joo Kim , Ho-Sung Yoon
发明人： Kyeong-Woo Chung , Chul-Joo Kim , Ho-Sung Yoon
CPC分类号： C22B60/0234
摘要： A highly efficient uranium leaching method using ultrasound is disclosed. The uranium leaching method includes preparing black slate powder containing uranium by pulverizing black slate containing uranium, placing the black slate powder and water in a reaction bath, and performing uranium leaching by adding and mixing sulfuric acid and an oxidant with the black slate powder and water to prepare a mixture in the reaction bath while applying ultrasound to the reaction bath. In this method, uranium leaching efficiency can be maximized by adding sulfuric acid to the uranium ore while applying ultrasound thereto.
摘要翻译： 公开了一种使用超声波的高效铀浸出方法。 铀浸出方法包括通过粉碎含有铀的黑色板岩来制备含有铀的黑色板岩粉末，将黑色板岩粉末和水置于反应槽中，并通过将黑色石板粉和水加入并混合硫酸和氧化剂来进行铀浸出 以在反应浴中制备混合物，同时向反应浴施加超声波。 在这种方法中，通过向铀矿中加入硫酸同时对其进行超声波处理，可以最大化铀浸出效率。
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公开(公告)号：US08394346B2
公开(公告)日：2013-03-12
申请号：US13380456
申请日：2010-06-29
申请人： Jean Luc Emin , Francois Drain , Francois Poncelet , Binh Dinh , Philippe Pradel , Pascal Baron , Michel Masson
发明人： Jean Luc Emin , Francois Drain , Francois Poncelet , Binh Dinh , Philippe Pradel , Pascal Baron , Michel Masson
IPC分类号： C01G56/00
CPC分类号： G21C19/46 , C01G56/001 , Y02W30/883
摘要： A method for treating spent nuclear fuel, which includes first decontaminating the uranium, plutonium and neptunium found in a nitric aqueous phase resulting from dissolving the nuclear fuel in HNO3. The uranium, plutonium and neptunium found in the solvent phase is then split in a first aqueous phase and a second aqueous phase. Next, the first aqueous phase is stored. Following, the plutonium or other mixtures found in the first aqueous phase is purified relative to the fission products still found in said phase, in order to obtain, at the end of said purification, an aqueous solution containing a mixture of Pu and U or Pu, U and Np. Finally the resulting mixture of Pu and U or the mixture of Pu, U and Np is co-converted into a mixed oxide.
摘要翻译： 一种处理乏核燃料的方法，其中包括首先将在核酸燃料溶解于HNO 3中的硝酸水相中发现的铀，钚和first水进行净化。 然后在溶剂相中发现的铀，钚和then then分裂在第一水相和第二水相中。 接下来，存储第一水相。 以下，相对于在所述相中仍存在的裂变产物，在第一水相中发现的钚或其他混合物被纯化，以便在所述纯化结束时获得含有Pu和U或Pu的混合物的水溶液 ，U和Np。 最后将所得到的Pu和U的混合物或Pu，U和Np的混合物共转化成混合氧化物。
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10.发明申请公开(公告)号：US20110250108A1
公开(公告)日：2011-10-13
申请号：US13079897
申请日：2011-04-05
摘要： A method for reprocessing spent nuclear fuel from a light water reactor includes the step of reacting spent nuclear fuel in a voloxidation vessel with an oxidizing gas having nitrogen dioxide and oxygen for a period sufficient to generate a solid oxidation product of the spent nuclear fuel. The reacting step includes the step of reacting, in a first zone of the voloxidation vessel, spent nuclear fuel with the oxidizing gas at a temperature ranging from 200-450° C. to form an oxidized reaction product, and regenerating nitrogen dioxide, in a second zone of the voloxidation vessel, by reacting oxidizing gas comprising nitrogen monoxide and oxygen at a temperature ranging from 0-80° C. The first zone and the second zone can be separate. A voloxidation system is also disclosed.
摘要翻译： 用于从轻水反应器再处理废核燃料的方法包括将废核燃料在氧化剂容器中与具有二氧化氮和氧气的氧化气体反应足以产生废核燃料的固体氧化产物的步骤。 反应步骤包括在氧化容器的第一区域中将废核燃料与氧化气体在200-450℃范围内反应以形成氧化反应产物并再生二氧化氮的步骤 通过使包含一氧化氮和氧气的氧化气体在0-80℃的温度范围内使氧化气体的第二区域反应。第一区域和第二区域可以是分开的。 还公开了一种血液透析系统。
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