公开(公告)号：US07622090B2

公开(公告)日：2009-11-24

申请号：US10549101

申请日：2004-11-17

Applicant: Binh Dinh ,  Michaël Lecomte ,  Pascal Baron ,  Christian Sorel ,  Gilles Bernier

Inventor： Binh Dinh ,  Michaël Lecomte ,  Pascal Baron ,  Christian Sorel ,  Gilles Bernier

IPC: B01D11/00 ,  C01G56/00 ,  C01F13/00 ,  C01G57/00 ,  C01F15/00 ,  C01G43/00 ,  C01B15/16 ,  C01B25/26 ,  C01B33/20 ,  C01G28/02 ,  C01G39/00 ,  C01G28/00 ,  C01F5/02 ,  C07C1/00 ,  C09K11/04 ,  C09K11/06 ,  C01D1/00

CPC classification number: G21F9/06 ,  C01G43/003 ,  G21C19/46 ,  Y02W30/883

Abstract: The invention relates to a method for separating uranium(VI) from one or more actinides selected from actinides(IV) and actinides(VI) other than uranium(VI), characterized in that it comprises the following steps:a) bringing an organic phase, which is immiscible with water and contains the said uranium and the said actinide or actinides, in contact with an aqueous acidic solution containing at least one lacunary heteropolyanion and, if the said actinide or at least one of the said actinides is an actinide(VI), a reducing agent capable of selectively reducing this actinide(VI); andb) separating the said organic phase from the said aqueous solution.Applications: reprocessing irradiated nuclear fuels, processing rare-earth, thorium and/or uranium ores.

Abstract translation: 本发明涉及一种从铀（Ⅳ）和除铀（Ⅵ）以外的锕系元素（Ⅵ）中选择一种或多种锕系元素分离铀（Ⅵ）的方法，其特征在于包括以下步骤：a） ，其与水不混溶并且含有所述铀和所述锕系元素或锕系元素，与含有至少一个空隙杂多阴离子的酸性水溶液接触，并且如果所述锕系元素或所述锕系元素中的至少一种为锕系元素（Ⅵ ），能够选择性还原该锕系元素（VI）的还原剂; 和b）从所述水溶液中分离出所述有机相。 应用：后处理辐射核燃料，加工稀土，钍和/或铀矿。

公开(公告)号：US08795611B2

公开(公告)日：2014-08-05

申请号：US13515499

申请日：2010-12-20

Applicant: Manuel Miguirditchian ,  Pascal Baron ,  Isabelle Bisel ,  Binh Dinh ,  Christian Sorel ,  Jean Bertin

Inventor： Manuel Miguirditchian ,  Pascal Baron ,  Isabelle Bisel ,  Binh Dinh ,  Christian Sorel ,  Jean Bertin

IPC: C01G43/00

CPC classification number: C22B3/0024 ,  C22B60/0239 ,  C22B60/026 ,  G21C19/46 ,  Y02P10/234 ,  Y02W30/883

Abstract: A method with which uranium from a natural uranium concentrate may be purified, including a) extracting the uranium present as uranyl nitrate in an aqueous phase A1 resulting from the dissolution of the natural uranium concentrate in nitric acid, by means of an organic phase which contains an extractant in an organic diluent; b) washing the organic phase obtained at the end of step a), with an aqueous phase A2; and c) stripping the uranyl nitrate of the organic phase obtained at the end of step b), by circulating this organic phase in an apparatus, as a counter current against an aqueous phase A3. The extractant is an N,N-dialkylamide and the ratio between the flow rate at which the organic phase obtained at the end of step b) and the aqueous phase A3 circulate in the apparatus where step c) occurs, is greater than 1.

Abstract translation: 可以纯化来自天然铀浓缩物的铀的方法，包括：a）在天然铀浓缩物在硝酸中溶解的水相A1中提取作为硝酸铀酰存在的铀，通过含有 有机稀释剂中的萃取剂; b）用水相A2洗涤在步骤a）结束时获得的有机相; 和c）通过将该有机相循环在装置中，作为逆水相A3的逆流，汽提在步骤b）结束时获得的有机相的铀酰硝酸盐。 萃取剂为N，N-二烷基酰胺，步骤b）结束时得到的有机相与水相A3在步骤c）的装置中循环的流动速率之比大于1。

公开(公告)号：US20120247276A1

公开(公告)日：2012-10-04

申请号：US13515499

申请日：2010-12-20

Applicant: Manuel Miguirditchian ,  Pascal Baron ,  Isabelle Bisel ,  Binh Dinh ,  Christian Sorel ,  Jean Bertin

Inventor： Manuel Miguirditchian ,  Pascal Baron ,  Isabelle Bisel ,  Binh Dinh ,  Christian Sorel ,  Jean Bertin

IPC: C22B60/02

CPC classification number: C22B3/0024 ,  C22B60/0239 ,  C22B60/026 ,  G21C19/46 ,  Y02P10/234 ,  Y02W30/883

Abstract: A method with which uranium from a natural uranium concentrate may be purified, includinga) extracting the uranium present as uranyl nitrate in an aqueous phase A1 resulting from the dissolution of the natural uranium concentrate in nitric acid, by means of an organic phase which contains an extractant in an organic diluent;b) washing the organic phase obtained at the end of step a), with an aqueous phase A2; andc) stripping the uranyl nitrate of the organic phase obtained at the end of step b), by circulating this organic phase in an apparatus, as a counter current against an aqueous phase A3.The extractant is an N,N-dialkylamide and the ratio between the flow rate at which the organic phase obtained at the end of step b) and the aqueous phase A3 circulate in the apparatus where step c) occurs, is greater than 1.

Abstract translation: 可以纯化来自天然铀浓缩物的铀的方法，包括：a）在天然铀浓缩物在硝酸中溶解的水相A1中提取作为硝酸铀酰存在的铀，通过含有 有机稀释剂中的萃取剂; b）用水相A2洗涤在步骤a）结束时获得的有机相; 和c）通过将该有机相循环在装置中，作为逆水相A3的逆流，汽提在步骤b）结束时获得的有机相的铀酰硝酸盐。 萃取剂为N，N-二烷基酰胺，步骤b）结束时得到的有机相与水相A3在步骤c）的装置中循环的流动速率之比大于1。

公开(公告)号：US20120128555A1

公开(公告)日：2012-05-24

申请号：US13380456

申请日：2010-06-29

Applicant: Jean Luc Emin ,  Francois Drain ,  Francois Poncelet ,  Binh Dinh ,  Philippe Pradel ,  Pascal Baron ,  Michel Masson

Inventor： Jean Luc Emin ,  Francois Drain ,  Francois Poncelet ,  Binh Dinh ,  Philippe Pradel ,  Pascal Baron ,  Michel Masson

IPC: C01G56/00

CPC classification number: G21C19/46 ,  C01G56/001 ,  Y02W30/883

Abstract: 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.

Abstract translation: 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。

公开(公告)号：US07887767B2

公开(公告)日：2011-02-15

申请号：US11753182

申请日：2007-05-24

Applicant: Pascal Baron ,  Binh Dinh ,  Michel Masson ,  Francois Drain ,  Jean-Luc Emin

Inventor： Pascal Baron ,  Binh Dinh ,  Michel Masson ,  Francois Drain ,  Jean-Luc Emin

IPC: G21C19/00

CPC classification number: G21C19/46 ,  C01G43/003 ,  C01G43/01 ,  C01G56/00 ,  C01G56/001 ,  Y02W30/883

Abstract: The invention relates to a process for reprocessing a spent nuclear fuel and for preparing a mixed uranium-plutonium oxide, which process comprises: a) the separation of the uranium and plutonium from the fission products, the americium and the curium that are present in an aqueous nitric solution resulting from the dissolution of the fuel in nitric acid, this step including at least one operation of coextracting the uranium and plutonium from said solution by a solvent phase; b) the partition of the coextracted uranium and plutonium to a first aqueous phase containing plutonium and uranium, and a second aqueous phase containing uranium but no plutonium; c) the purification of the plutonium and uranium that are present in the first aqueous phase; and d) a step of coconverting the plutonium and uranium to a mixed uranium/plutonium oxide. Applications: reprocessing of nuclear fuels based on uranium oxide or on mixed uranium-plutonium oxide.

Abstract translation: 本发明涉及一种用于后处理废核燃料和制备混合铀 - 钚氧化物的方法，该方法包括：a）将铀和钚从裂变产物，ium和ium中分离出来， 由于燃料溶解在硝酸中而产生的硝酸水溶液，该步骤包括通过溶剂相从所述溶液中共萃取铀和钚的至少一种操作; b）将共萃取的铀和钚分配到含有钚和铀的第一水相，以及含有铀但不含钚的第二水相; c）净化存在于第一水相中的钚和铀; 和d）将钚和铀同时混合的混合铀/钚氧化物的步骤。 应用：基于氧化铀或混合铀 - 钚氧化物的核燃料的后处理。

公开(公告)号：US20070290178A1

公开(公告)日：2007-12-20

申请号：US11753182

申请日：2007-05-24

Applicant: Pascal Baron ,  Binh Dinh ,  Michel Masson ,  Francois Drain ,  Jean-Luc Emin

Inventor： Pascal Baron ,  Binh Dinh ,  Michel Masson ,  Francois Drain ,  Jean-Luc Emin

IPC: G21C19/00 ,  G21G4/00

CPC classification number: G21C19/46 ,  C01G43/003 ,  C01G43/01 ,  C01G56/00 ,  C01G56/001 ,  Y02W30/883

Abstract: The invention relates to a process for reprocessing a spent nuclear fuel and for preparing a mixed uranium-plutonium oxide, which process comprises: a) the separation of the uranium and plutonium from the fission products, the americium and the curium that are present in an aqueous nitric solution resulting from the dissolution of the fuel in nitric acid, this step including at least one operation of coextracting the uranium and plutonium from said solution by a solvent phase; b) the partition of the coextracted uranium and plutonium to a first aqueous phase containing plutonium and uranium, and a second aqueous phase containing uranium but no plutonium; c) the purification of the plutonium and uranium that are present in the first aqueous phase; and d) a step of coconverting the plutonium and uranium to a mixed uranium/plutonium oxide. Applications: reprocessing of nuclear fuels based on uranium oxide or on mixed uranium-plutonium oxide.

Abstract translation: 本发明涉及一种用于后处理废核燃料和制备混合铀 - 钚氧化物的方法，该方法包括：a）将铀和钚从裂变产物，ium和ium中分离出来， 由于燃料溶解在硝酸中而产生的硝酸水溶液，该步骤包括通过溶剂相从所述溶液中共萃取铀和钚的至少一种操作; b）将共萃取的铀和钚分配到含有钚和铀的第一水相，以及含有铀但不含钚的第二水相; c）净化存在于第一水相中的钚和铀; 和d）将钚和铀同时混合的混合铀/钚氧化物的步骤。 应用：基于氧化铀或混合铀 - 钚氧化物的核燃料后处理。

公开(公告)号：US08795610B2

公开(公告)日：2014-08-05

申请号：US13699748

申请日：2011-05-25

Applicant: Didier Saudray ,  Binh Dinh ,  Pascal Baron ,  Michel Masson ,  Christian Sorel ,  Manuel Miguirditchian

Inventor： Didier Saudray ,  Binh Dinh ,  Pascal Baron ,  Michel Masson ,  Christian Sorel ,  Manuel Miguirditchian

IPC: C22B60/00 ,  C22B3/06 ,  G21C19/46 ,  C22B7/00 ,  C22B60/04

CPC classification number: C22B60/04 ,  C22B3/065 ,  C22B7/007 ,  G21C19/46 ,  Y02P10/234 ,  Y02W30/883

Abstract: The invention relates to a process for reprocessing spent nuclear fuel which, among other advantages, does not require a plutonium-reducing stripping operation.This process finds particular application in the processing of uranium oxide fuels and uranium and plutonium mixed oxide fuels.

Abstract translation: 本发明涉及一种用于再次处理乏核燃料的方法，其中除了其它优点之外，不需要钚减少剥离操作。 该方法在处理铀氧化物燃料和铀和钚混合氧化物燃料方面具有特殊应用。

公开(公告)号：US08454913B2

公开(公告)日：2013-06-04

申请号：US12663181

申请日：2008-06-05

Applicant: Binh Dinh ,  Pascal Baron ,  Philippe Moisy ,  Laurent Venault ,  Patrick Pochon ,  Gilles Bernier

Inventor： Binh Dinh ,  Pascal Baron ,  Philippe Moisy ,  Laurent Venault ,  Patrick Pochon ,  Gilles Bernier

IPC: C22B60/00

CPC classification number: G21C19/46 ,  Y02W30/883

Abstract: The invention relates to the use of butyraldehyde oxime as an anti-nitrous agent in a plutonium stripping operation based on a reduction of this element from oxidation state (IV) to oxidation state (III). Applications: any nuclear fuel reprocessing process in which employing a compound that has the twofold property of being extractable into an organic phase and of being capable of destroying the nitrous acid therein may be useful and especially any process including one or more operations for the reductive stripping of plutonium.

Abstract translation: 本发明涉及基于将该元素从氧化态（IV）还原为氧化态（III）的方法，在钚萃取操作中使用丁醛肟作为抗氧化剂。 应用：任何核燃料后处理方法，其中使用具有可提取成有机相并且能够破坏其中的亚硝酸的具有双重性质的化合物可能是有用的，特别是包括用于还原汽提的一个或多个操作的任何方法 的钚。

公开(公告)号：US08394346B2

公开(公告)日：2013-03-12

申请号：US13380456

申请日：2010-06-29

Applicant: Jean Luc Emin ,  Francois Drain ,  Francois Poncelet ,  Binh Dinh ,  Philippe Pradel ,  Pascal Baron ,  Michel Masson

Inventor： Jean Luc Emin ,  Francois Drain ,  Francois Poncelet ,  Binh Dinh ,  Philippe Pradel ,  Pascal Baron ,  Michel Masson

IPC: C01G56/00

CPC classification number: G21C19/46 ,  C01G56/001 ,  Y02W30/883

Abstract: 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.

Abstract translation: 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。

公开(公告)号：US20090184298A1

公开(公告)日：2009-07-23

申请号：US12300705

申请日：2007-05-23

Applicant: Pascal Baron ,  Binh Dinh ,  Michel Masson ,  Francois Drain ,  Jean Luc Emin

Inventor： Pascal Baron ,  Binh Dinh ,  Michel Masson ,  Francois Drain ,  Jean Luc Emin

IPC: C09K11/04

CPC classification number: G21C19/46 ,  C01G43/003 ,  C01G43/01 ,  C01G56/00 ,  C01G56/001 ,  Y02W30/883

Abstract: A process for reprocessing a spent nuclear fuel and for preparing a mixed uranium-plutonium oxide. The process: a) separates the uranium and plutonium from fission products, americium, and curium that are present in an aqueous nitric solution resulting from dissolution of the fuel in nitric acid, the separating including at least one operation of coextracting the uranium and plutonium from the solution by a solvent phase; b) partitions the coextracted uranium and plutonium to a first aqueous phase containing plutonium and uranium, and a second aqueous phase containing uranium but no plutonium; c) purifies the plutonium and uranium that are present in the first aqueous phase; and d) coconverts the plutonium and uranium to a mixed uranium/plutonium oxide.

Abstract translation: 一种用于后处理乏核燃料和制备混合铀 - 钚氧化物的方法。 方法是：a）将铀和钚从裂变产物，ium ium和））中分离出来，这些铀和钚存在于由硝酸溶解燃料而产生的硝酸水溶液中，该分离包括将铀和钚共同提取的至少一种操作 溶液通过溶剂相; b）将共萃取的铀和钚分配到含有钚和铀的第一水相，以及含有铀但不含钚的第二水相; c）净化存在于第一水相中的钚和铀; 和d）将钚和铀同时混合到混合的铀/钚氧化物中。