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1. 发明授权

US08182773B2 Process for separating a chemical element from uranium (VI) starting from a nitric aqueous phase, in an extraction cycle for the uranium 有权
标题翻译：在铀萃取循环中从硝酸水相开始分离化学元素与铀（VI）的方法
公开(公告)号：US08182773B2
公开(公告)日：2012-05-22
申请号：US12307264
申请日：2007-07-02
申请人： Jean-Paul Moulin , Gilbert Andreoletti , Patrick Bourdet
发明人： Jean-Paul Moulin , Gilbert Andreoletti , Patrick Bourdet
IPC分类号： C01G56/00
CPC分类号： G21C19/46 , B01D11/0446 , B01D11/0488 , B01D11/0492 , G21F9/06 , Y02W30/883
摘要： A chemical element to be very efficiently separated from uranium starting from an acid aqueous phase, in an extraction cycle for the uranium, when this chemical element is present in said phase at a concentration less than that of the uranium, or even as a trace element, and when it is moreover less extractable by the extractant used in this extraction cycle than is the uranium. The chemical element can notably be neptunium(IV) or thorium 228.
摘要翻译：在铀的萃取循环中，当该化学元素以相对于铀的浓度存在于所述相中时，甚至作为微量元素，从酸性水相开始非常有效地与铀分离的化学元素，而且当该萃取循环中使用的萃取剂比铀更少时可萃取。化学元素可以显着地是ium（IV）或钍228。

2. 发明授权

US5603811A Process for the treatment of an aqueous solution mainly containing nitric acid and hydrofluoric acid 失效
标题翻译：用于处理主要含有硝酸和氢氟酸的水溶液的方法
公开(公告)号：US5603811A
公开(公告)日：1997-02-18
申请号：US210412
申请日：1994-03-18
申请人： Philippe Lucas , Jean-Paul Moulin , Olivier Halna du Fretay , Joseph Roussel , Jany Petit , Claude Saintouil , Claude Toussaint
发明人： Philippe Lucas , Jean-Paul Moulin , Olivier Halna du Fretay , Joseph Roussel , Jany Petit , Claude Saintouil , Claude Toussaint
IPC分类号： B01D3/14 , C01B7/19 , C01B21/46 , C02F1/04 , C23G1/36 , B01D3/10 , B01D3/36
CPC分类号： C02F1/048 , B01D3/146 , C01B21/46 , C01B7/196 , C23G1/36 , Y10S159/15 , Y10S159/19
摘要： A process for treating an aqueous solution mainly containing nitric acid and hydrofluoric acid. The process involves distilling to provide an aqueous solution concentrated in nitric acid and hydrofluoric acid for the separation thereof, then separating by distillation.
摘要翻译：一种处理主要含有硝酸和氢氟酸的水溶液的方法。该方法包括蒸馏以提供浓缩在硝酸和氢氟酸中的水溶液进行分离，然后通过蒸馏分离。

3. 发明授权

US07731870B2 Purex method and its uses 有权
标题翻译： Purex方法及其用途
公开(公告)号：US07731870B2
公开(公告)日：2010-06-08
申请号：US11793891
申请日：2005-12-27
申请人： Jean-Paul Moulin
发明人： Jean-Paul Moulin
IPC分类号： C09K11/04
CPC分类号： G21C19/46 , Y02W30/883
摘要： The invention relates to a method constituting an improvement of the PUREX method, which makes it possible to obtain separation of uranium from the other actinides (Pu, Np, Th, . . . ) in a single purification cycle.This method successively comprises: a) co-extracting the uranium(VI), plutonium(IV) and other actinides(IV) or (VI) from an aqueous nitric solution by using solvent phase and scrubbing the latter; b) back-extracting the plutonium in oxidation state (III) from the solvent phase by using an aqueous nitric solution; c) back-extracting the uranium in oxidation state (VI) from the solvent phase by using an aqueous nitric solution; d) concentrating the aqueous nitric solution resulting from step c) with respect to uranium(VI); and it is characterized in that some of the uranium(VI)-concentrated aqueous solution obtained in step d) is used for back-extracting the actinide(IV) or actinides(IV) from the solvent phase during step b) or between steps b) and c).Uses: reprocessing of spent nuclear fuels based on UO2, (U,Pu)O2 or (U,Th)O2 mixed oxide.
摘要翻译：本发明涉及一种构成PUREX方法改进的方法，其可以在单个纯化循环中从其他锕系元素（Pu，Np，Th等）中获得铀的分离。该方法依次包括：a）通过使用溶剂相并将其洗涤，从硝酸水溶液中共同萃取铀（VI），钚（IV）和其他锕系元素（Ⅳ）或（Ⅵ） b）通过使用硝酸水溶液从溶剂相中回收处于氧化态（III）的钚; c）通过使用硝酸水溶液从溶剂相中回收处于氧化态（Ⅵ）的铀; d）浓缩步骤c）得到的硝酸水溶液相对于铀（VI）; 其特征在于，使用步骤d）中获得的一些铀（VI） - 浓缩水溶液用于在步骤b）期间或在步骤b之间从溶剂相中反萃取锕系元素（Ⅳ）或锕系元素（Ⅳ））和c）。用途：基于UO2，（U，Pu）O2或（U，Th）O2混合氧化物对废核燃料进行后处理。

4. 发明申请

US20100034713A1 PROCESS FOR SEPARATING A CHEMICAL ELEMENT FROM URANIUM (VI) STARTING FROM A NITRIC AQUEOUS PHASE, IN AN EXTRACTION CYCLE FOR THE URANIUM 有权
标题翻译：从铀（VI）中分离化学元素的过程在硝酸的萃取循环中从硝酸水相中开始
公开(公告)号：US20100034713A1
公开(公告)日：2010-02-11
申请号：US12307264
申请日：2007-07-02
申请人： Jean-Paul Moulin , Gilbert Andreoletti , Patrick Bourdet
发明人： Jean-Paul Moulin , Gilbert Andreoletti , Patrick Bourdet
IPC分类号： C22B60/00 , C22B60/02
CPC分类号： G21C19/46 , B01D11/0446 , B01D11/0488 , B01D11/0492 , G21F9/06 , Y02W30/883
摘要： A chemical element to be very efficiently separated from uranium starting from an acid aqueous phase, in an extraction cycle for the uranium, when this chemical element is present in said phase at a concentration less than that of the uranium, or even as a trace element, and when it is moreover less extractable by the extractant used in this extraction cycle than is the uranium. The chemical element can notably be neptunium(IV) or thorium 228.
摘要翻译：在铀的萃取循环中，当该化学元素以相对于铀的浓度存在于所述相中时，甚至作为微量元素，从酸性水相开始非常有效地与铀分离的化学元素，而且当该萃取循环中使用的萃取剂比铀更少时可萃取。化学元素可以显着地是ium（IV）或钍228。

5. 发明申请

US20080089819A1 Purex Method and its Uses 有权
标题翻译： Purex方法及其用途
公开(公告)号：US20080089819A1
公开(公告)日：2008-04-17
申请号：US11793891
申请日：2005-12-27
申请人： Jean-Paul Moulin
发明人： Jean-Paul Moulin
IPC分类号： C22B60/02 , C09K11/04
CPC分类号： G21C19/46 , Y02W30/883
摘要： The invention relates to a method constituting an improvement of the PUREX method, which makes it possible to obtain separation of uranium from the other actinides (Pu, Np, Th, . . . ) in a single purification cycle. This method successively comprises: a) co-extracting the uranium(VI), plutonium(IV) and other actinides(IV) or (VI) from an aqueous nitric solution by using solvent phase and scrubbing the latter; b) back-extracting the plutonium in oxidation state (III) from the solvent phase by using an aqueous nitric solution; c) back-extracting the uranium in oxidation state (VI) from the solvent phase by using an aqueous nitric solution; d) concentrating the aqueous nitric solution resulting from step c) with respect to uranium(VI); and it is characterized in that some of the uranium(VI)-concentrated aqueous solution obtained in step d) is used for back-extracting the actinide(IV) or actinides(IV) from the solvent phase during step b) or between steps b) and c). Uses: reprocessing of spent nuclear fuels based on UO2, (U,Pu)O2 or (U,Th)O2 mixed oxide.
摘要翻译：本发明涉及一种构成PUREX方法改进的方法，其可以在单个纯化循环中从其他锕系元素（Pu，Np，Th等）中获得铀的分离。该方法依次包括：a）通过使用溶剂相并将其洗涤，从硝酸水溶液中共同萃取铀（VI），钚（IV）和其他锕系元素（Ⅳ）或（Ⅵ） b）通过使用硝酸水溶液从溶剂相中回收处于氧化态（III）的钚; c）通过使用硝酸水溶液从溶剂相中回收处于氧化态（Ⅵ）的铀; d）浓缩步骤c）得到的硝酸水溶液相对于铀（VI）; 其特征在于，使用步骤d）中获得的一些铀（VI） - 浓缩水溶液用于在步骤b）期间或在步骤b之间从溶剂相中反萃取锕系元素（Ⅳ）或锕系元素（Ⅳ））和c）。用途：基于UO 2，（U，Pu）O 2或（U，Th）O 2 2混合氧化物的废核燃料的后处理。

6. 发明授权

US06517788B2 Method and device for separating caesium, strontium and transuranium elements contained in sodium waste 有权
标题翻译：用于分离钠废物中所含的铯，锶和铀元素的方法和装置
公开(公告)号：US06517788B2
公开(公告)日：2003-02-11
申请号：US09794179
申请日：2001-02-26
申请人： Marie-Françoise Debreuille , Nathalie Hubert , Jean-Paul Moulin
发明人： Marie-Françoise Debreuille , Nathalie Hubert , Jean-Paul Moulin
IPC分类号： C22B6000
CPC分类号： G21C19/46 , G21F9/10 , Y02W30/883
摘要： The present invention relates to a method for the continuous separation of caesium, strontium and transuranium elements contained in sodium waste which comprises the use of NaTPB, and to a device for the implementation of this method. The method of the invention comprises, in line, the following steps: (a) filling at least one of at least two feed tanks with the waste; (b) analysis of the content of Cs+, Sr++, Na+ and transuranium elements in the waste; (c) pre-treatment, adapted in relation to analysis results, of the solution in the feed tank intended to insolubilise the strontium and transuranium elements; (e1) a first caesium separation treatment; and e1a) a second caesium separation treatment, the method being conducted in continuous manner by means of the alternate use of the feed tanks.
摘要翻译：本发明涉及一种连续分离包含在钠废物中的铯，锶和铀元素的方法，该方法包括使用NaTPB，以及用于实施该方法的装置。本发明的方法包括，以下步骤：（a）用废物填充至少两个进料罐中的至少一个; （b）废物中Cs +，Sr ++，Na +和铀元素含量的分析; （c）相对于分析结果调整用于使锶和铀元素不溶的进料罐中的溶液的预处理; （e1）第一次铯分离处理; 和e1a）第二次铯分离处理，所述方法通过交替使用进料罐连续进行。

7. 发明授权

US4481135A Process for the treatment of basic aqueous effluents 失效
标题翻译：碱性含水废水处理方法
公开(公告)号：US4481135A
公开(公告)日：1984-11-06
申请号：US389281
申请日：1982-06-17
申请人： Alain Aspart , Bernard Guillaume , Jean-Paul Moulin
发明人： Alain Aspart , Bernard Guillaume , Jean-Paul Moulin
IPC分类号： G21F9/06 , G21F9/00 , G21F9/08
CPC分类号： G21F9/08 , Y10S159/12
摘要： The invention relates to a process for the treatment of basic aqueous effluents containing plutonium and possibly uranium.According to this process, the effluents are concentrated by evaporation under reduced pressure, at a temperature such that plutonium precipitation is substantially avoided. Advantageously, the effluents are evaporated at a temperature of 50.degree. to 80.degree. C. for a time such that a concentration factor of at least 6 is obtained.Application to the treatment of aqueous effluents obtained by the alkaline washing of organic solvents used in installations for the reprocessing of irradiated nuclear fuels.
摘要翻译：本发明涉及一种处理含有钚和可能的铀的碱性含水废水的方法。根据该方法，通过在减压下蒸发浓缩排出物，使得基本上避免了钚沉淀。有利地，在50至80℃的温度下蒸发出一段时间，使得得到至少6的浓度系数。应用于通过碱洗涤被照射的核燃料后处理用设备中使用的有机溶剂来处理含水废水。

8. 发明授权

US08221520B2 Production of thorium 228 starting from a natural thorium salt 有权
标题翻译：从天然钍盐开始生产钍228
公开(公告)号：US08221520B2
公开(公告)日：2012-07-17
申请号：US12531543
申请日：2008-03-18
申请人： Gilbert Andreoletti , Michel Belieres , Pascal Nardoux , Jean-Paul Moulin , Anne Montaletang , Patrick Bourdet
发明人： Gilbert Andreoletti , Michel Belieres , Pascal Nardoux , Jean-Paul Moulin , Anne Montaletang , Patrick Bourdet
IPC分类号： C22C43/00
CPC分类号： C01F15/00 , A61K51/1096 , A61K51/12 , C01P2006/88
摘要： The invention relates to a process for producing 228Th from a natural thorium salt, which comprises in succession: a) the separation of the radium from the other radioelements present in this salt, by at least one coprecipitation of the radium by barium sulphate, this coprecipitation comprising: i) the addition of sulphuric acid and a barium salt to an aqueous solution of said natural thorium salt in order to form a barium-radium sulphate coprecipitate and ii) the separation of the coprecipitate from the medium in which it has formed; b) the extraction of the thorium 228 coming from the decay of radium 228 from the coprecipitate thus separated; and, optionally c) the purification and concentration of the 228Th thus extracted. Applications: manufacture of radiopharmaceutical products useful in nuclear medicine, in particular in radioimmunotherapy for the treatment of cancers and AIDS.
摘要翻译：本发明涉及一种从天然钍盐生产228Th的方法，其连续包括：a）通过硫酸钡至少一次共沉淀镭来分离镭与该盐中存在的其它放射性元素，这种共沉淀包括：i）将硫酸和钡盐加入到所述天然钍盐的水溶液中以形成硫酸钡 - 共沉淀物，和ii）从其形成的介质中分离共沉淀物; b）从分离的共沉淀物中提取来自镭228的腐蚀的钍228; 并且任选地c）纯化和浓缩由此提取的228Th。应用：制造用于核医学的放射性药物产品，特别是用于治疗癌症和艾滋病的放射免疫疗法。

9. 发明申请

US20100104467A1 PRODUCTION OF THORIUM 228 STARTING FROM A NATURAL THORIUM SALT 有权
标题翻译：从天然硫酸钠开始生产228
公开(公告)号：US20100104467A1
公开(公告)日：2010-04-29
申请号：US12531543
申请日：2008-03-18
申请人： Gilbert Andreoletti , Michel Belieres , Pascal Nardoux , Jean-Paul Moulin , Anne Montaletang , Patrick Bourdet
发明人： Gilbert Andreoletti , Michel Belieres , Pascal Nardoux , Jean-Paul Moulin , Anne Montaletang , Patrick Bourdet
IPC分类号： C22C43/00 , C22B60/02
CPC分类号： C01F15/00 , A61K51/1096 , A61K51/12 , C01P2006/88
摘要： The invention relates to a process for producing 228Th from a natural thorium salt, which comprises in succession: a) the separation of the radium from the other radioelements present in this salt, by at least one coprecipitation of the radium by barium sulphate, this coprecipitation comprising: i) the addition of sulphuric acid and a barium salt to an aqueous solution of said natural thorium salt in order to form a barium-radium sulphate coprecipitate and ii) the separation of the coprecipitate from the medium in which it has formed; b) the extraction of the thorium 228 coming from the decay of radium 228 from the coprecipitate thus separated; and, optionally c) the purification and concentration of the 228Th thus extracted. Applications: manufacture of radiopharmaceutical products useful in nuclear medicine, in particular in radioimmunotherapy for the treatment of cancers and AIDS.
摘要翻译：本发明涉及一种从天然钍盐生产228Th的方法，其连续包括：a）通过硫酸钡至少一次共沉淀镭来分离镭与该盐中存在的其它放射性元素，这种共沉淀包括：i）将硫酸和钡盐加入到所述天然钍盐的水溶液中以形成硫酸钡 - 共沉淀物，和ii）从其形成的介质中分离共沉淀物; b）从分离的共沉淀物中提取来自镭228的腐蚀的钍228; 并且任选地c）纯化和浓缩由此提取的228Th。应用：制造用于核医学的放射性药物产品，特别是用于治疗癌症和艾滋病的放射免疫疗法。

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