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：US08778287B2

公开(公告)日：2014-07-15

申请号：US12445748

申请日：2007-10-22

Applicant: Manuel Miguirditchian ,  Pascal Baron

Inventor： Manuel Miguirditchian ,  Pascal Baron

IPC: B01D11/00

CPC classification number: G21C19/44 ,  B01D11/0488 ,  C01F17/0006 ,  C01G56/001 ,  G21F9/12 ,  Y02W30/882

Abstract: The invention relates to a process which makes it possible to separate together all the actinide(III), (IV), (V) and (VI) entities present in a highly acidic aqueous phase from fission products, in particular lanthanides, also present in this phase by using a solvating extractant in a salting-out medium.Applications: reprocessing of irradiated nuclear fuels, in particular for recovering plutonium, neptunium, americium, curium and possibly uranium, present in the form of traces, in a pooled but selective fashion with regard to lanthanides, from a solution for the dissolution of an irradiated nuclear fuel, downstream of a cycle for the extraction of uranium.

Abstract translation: 本发明涉及一种方法，其可以将存在于高度酸性的水相中的所有锕系元素（III），（IV），（V）和（VI）的实体与裂变产物，特别是镧系元素分开， 该阶段通过在盐析介质中使用溶剂萃取剂。 应用：辐照的核燃料的后处理，特别是用于回收钚，ium，ium，ium和可能的铀，以痕量的形式，从镧系元素的集合而是选择性的方式从用于溶解辐照的溶液 核燃料，在提取铀循环的下游。

公开(公告)号：US08557120B2

公开(公告)日：2013-10-15

申请号：US12297651

申请日：2007-04-19

Applicant: Xavier Heres ,  Manuel Miguirditchian ,  Pascal Baron ,  Laurence Chareyre

Inventor： Xavier Heres ,  Manuel Miguirditchian ,  Pascal Baron ,  Laurence Chareyre

IPC: B01D59/24 ,  B01D17/00

CPC classification number: G21C19/46 ,  Y02W30/883

Abstract: The invention relates to a process for collectively separating all the actinides (III), (IV), (V) and (VI) present in a strongly acidic aqueous phase, from the fission products, and in particular from the lanthanides, which are also present in this phase, using two extractants that operate in unconnected chemical fields.Applications: reprocessing of irradiated nuclear fuels, especially to recover plutonium, neptunium, americium, curium and, possibly, uranium present in trace amounts, in a grouped manner but selectively with respect to the lanthanides, from a solution for dissolution of an irradiated nuclear fuel, downstream of a uranium extraction cycle.

Abstract translation: 本发明涉及将强酸性水相中存在的所有锕系元素（III），（Ⅳ），（Ⅴ）和（Ⅵ）从裂变产物，特别是镧系元素分离的方法， 在这个阶段，使用两种在未连接的化学领域中操作的萃取剂。 应用：辐射核燃料的后处理，特别是以分组方式回收钚，ium，ium，ium和铀和可能的铀，可以选择性地从镧系元素中选择性地从用于溶解辐照的核燃料的溶液中回收 在铀萃取循环的下游。

公开(公告)号：US08371847B2

公开(公告)日：2013-02-12

申请号：US12937588

申请日：2009-04-03

Applicant: Pascal Baron ,  Christophe Gualano ,  Laurent Sempe

Inventor： Pascal Baron ,  Christophe Gualano ,  Laurent Sempe

IPC: A61C7/00

CPC classification number: A61C7/00 ,  A61C7/002 ,  A61C7/14 ,  Y10T29/49568

Abstract: A method of producing a customized orthodontic appliance (1), including brackets (12) fixed to teeth (13) of a dental arch of a patient and an orthodontic archwire (11). Each bracket (12) is fixed to a surface of a tooth (13) of the dental arch by a bracket bonding pad (121) of the bracket, and the orthodontic archwire (11) is fixed to the brackets in a housing (123) of a bracket body (122) of each bracket. The bracket is produced with a blank (50) having at least two volumes (51, 52), one volume representative of an envelope volume of a bracket bounding pad and an envelope volume of a bracket body.

Abstract translation: 一种生产定制的矫正器具（1）的方法，包括固定到患者牙弓的牙齿（13）的支架（12）和正畸弓丝（11）。 每个支架（12）通过支架的支架接合垫（121）固定到牙弓的牙齿表面（13），并且正畸弓丝（11）固定在壳体（123）中的支架上， 的每个支架的支架主体（122）。 支架由具有至少两个体积（51,52）的空白（50）制成，一个体积代表支架边界垫的包络体积和支架主体的包络体积。

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：US20120160061A1

公开(公告)日：2012-06-28

申请号：US13386012

申请日：2010-07-26

Applicant: Xavier Heres ,  Pascal Baron

Inventor： Xavier Heres ,  Pascal Baron

IPC: C22B60/02

CPC classification number: C22B3/0005 ,  C22B59/00 ,  G21C19/46 ,  G21F9/125 ,  Y02P10/234 ,  Y02W30/883

Abstract: A method using diglycolamide for increasing the separation factor between americium and curium and/or between lanthanides during an extraction operation. The operation comprising putting an acid aqueous phase, in which are found the americium, curium and/or lanthanides, in contact with an organic phase non-miscible with water, containing at least one extractant in an organic diluent. The aqueous and organic phases are then separated, and the diglycolamide is added to the aqueous phase. This method can be used for processing and recycling irradiated nuclear fuels, in particular for selectively recovering americium from high activity aqueous solutions such as raffinates stemming from the processing of irradiated nuclear fuels with a PUREX or COEX™ method; processing of rare earth ores of the monazite, xenotime or bastnaesite type, in order to facilitate separation of > rare earths from > rare earths and of yttrium, or that of two rare earths with adjacent or close atomic numbers.

Abstract translation: 在提取操作期间使用二甘醇酰胺增加ium和ium和/或镧系元素之间的分离因子的方法。 操作包括将酸性水相（其中发现amer，ium和/或镧系元素）与不含水的有机相接触，所述有机相在有机稀释剂中含有至少一种萃取剂。 然后分离水相和有机相，并将二甘醇二酰胺加入到水相中。 该方法可用于加工和再循环辐照的核燃料，特别是用PUREX或COEX TM法从高活性水溶液中选择性地回收amer，例如由辐射的核燃料的加工产生的残液; 加工稀土矿石的独居石，堇青石或巴斯特纳型，以便于从“重”稀土和钇中分离出“轻量级”稀土，或者分离具有相邻或近原子的两种稀土 数字。

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：US20110086322A1

公开(公告)日：2011-04-14

申请号：US12937588

申请日：2009-04-03

Applicant: Pascal Baron ,  Christophe Gualano ,  Laurent Sempe

Inventor： Pascal Baron ,  Christophe Gualano ,  Laurent Sempe

IPC: A61C7/14 ,  B23P13/00

CPC classification number: A61C7/00 ,  A61C7/002 ,  A61C7/14 ,  Y10T29/49568

Abstract: A method of producing a customized orthodontic appliance (1), including brackets (12) fixed to teeth (13) of a dental arch of a patient and an orthodontic archwire (11). Each bracket (12) is fixed to a surface of a tooth (13) of the dental arch by a bracket bonding pad (121) of the bracket, and the orthodontic archwire (11) is fixed to the brackets in a housing (123) of a bracket body (122) of each bracket. The bracket is produced with a blank (50) having at least two volumes (51, 52), one volume representative of an envelope volume of a bracket bounding pad and an envelope volume of a bracket body.

Abstract translation: 一种生产定制的矫正器具（1）的方法，包括固定到患者牙弓的牙齿（13）的支架（12）和正畸弓丝（11）。 每个支架（12）通过支架的支架接合垫（121）固定到牙弓的牙齿表面（13），并且正畸弓丝（11）固定在壳体（123）中的支架上， 的每个支架的支架主体（122）。 支架由具有至少两个体积（51,52）的空白（50）制成，一个体积代表支架边界垫的包络体积和支架主体的包络体积。

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。