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。

公开(公告)号：US07157003B2

公开(公告)日：2007-01-02

申请号：US10679462

申请日：2003-10-07

Applicant: Pascal Baron ,  Michael Lecomte ,  Xavier Heres ,  Bernard Mauborgne

Inventor： Pascal Baron ,  Michael Lecomte ,  Xavier Heres ,  Bernard Mauborgne

IPC: B01D11/00

CPC classification number: G21F9/12 ,  C01F17/0006 ,  C22B3/0005 ,  C22B59/00 ,  C22B60/0295 ,  G21F9/125 ,  Y02P10/234

Abstract: The invention concerns a cyclic method for separating at least one chemical element E1 from at least one chemical element E2 from an aqueous solution containing said elements, which employs a mixture of two extractants operating in non-overlapping chemical fields.Each cycle of said method comprises: a) co-extracting elements E1 and E2 by means of an organic phase containing a first extractant suited to causing the migration of said elements into said organic phase; b) adding to the organic phase a second extractant suited to selectively retaining the element(s) E2 in said organic phase during step c): c) selectively stripping the element(s) E1 from the organic phase; d) selectively stripping the element(s) E2 from the organic phase; e) separating the first and second extractants present in said organic phase at the end of step d).

Abstract translation: 本发明涉及一种循环方法，用于将至少一种化学元素E 1与至少一种化学元素E 2从含有所述元素的水溶液中分离，其使用在非重叠化学领域中操作的两种萃取剂的混合物。 所述方法的每个循环包括：a）通过含有适于使所述元素迁移到所述有机相中的第一萃取剂的有机相共萃取元素E 1和E 2; b）在步骤c）期间向所述有机相中加入适于选择性地将元素E 2保留在所述有机相中的第二萃取剂：c）选择性地从有机相中汽提元素E 1; d）从有机相中选择性地剥离元素E 2; e）在步骤d）结束时分离存在于所述有机相中的第一和第二萃取剂。

公开(公告)号：US20060197370A1

公开(公告)日：2006-09-07

申请号：US11366422

申请日：2006-03-03

Applicant: Jean-Pierre Mercat ,  Pascal Baron

Inventor： Jean-Pierre Mercat ,  Pascal Baron

IPC: B60B1/02

CPC classification number: B60B1/042 ,  B60B1/041

Abstract: A hub for cycle wheel including a shaft, a hub body rotatably mounted around the shaft. The hub body has, at least at one of its ends, merlons that are provided for fastening the spokes. Each of the merlons has a radial housing that opens out at its top, as well as two slots, each of the slots extending through the wall thickness between the radial housing and a distinct frontal surface of the merlon. The invention also relates to a cycle wheel having such a hub.

公开(公告)号：US20060147359A1

公开(公告)日：2006-07-06

申请号：US10549101

申请日：2004-11-17

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

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

IPC: C22B60/02

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); and b) 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：USD448825S1

公开(公告)日：2001-10-02

申请号：US29133965

申请日：2000-12-13

Applicant: Pascal Baron ,  Ivan Bosse

Designer： Pascal Baron ,  Ivan Bosse

公开(公告)号：US20120152059A1

公开(公告)日：2012-06-21

申请号：US13386017

申请日：2010-07-26

Applicant: Xavier Heres ,  Pascal Baron ,  Christian Sorel ,  Clément Hill ,  Gilles Bernier

Inventor： Xavier Heres ,  Pascal Baron ,  Christian Sorel ,  Clément Hill ,  Gilles Bernier

IPC: C22B60/02

CPC classification number: C22B60/0295 ,  C01G56/001 ,  C01P2006/80 ,  C22B3/0005 ,  G21C19/46 ,  G21F9/125 ,  Y02P10/234 ,  Y02W30/883

Abstract: A method with which americium may be selectively recovered from a nitric aqueous phase containing americium, curium and fission products including lanthanides and yttrium, but which is free of uranium, plutonium and neptunium or which only contains these three last elements in trace amounts. The method is applicable for treatment and recycling of irradiated nuclear fuels, in particular for removing americium from raffinates stemming from methods for extracting and purifying uranium and plutonium such as the PUREX and COEX™ methods.

Abstract translation: 可以从含有ium，ium和裂变产物（包括镧系元素和钇）的硝酸水相中选择性地回收amer的方法，但不含铀，钚和ium，或仅含有这三种最后一种元素。 该方法适用于辐射核燃料的处理和再循环，特别是用于从萃取和净化铀和钚的方法（如PUREX和COEX™）中除去来自萃余液的。。

公开(公告)号：US20110002823A1

公开(公告)日：2011-01-06

申请号：US12445748

申请日：2007-10-22

Applicant: Manuel Miguirditchian ,  Pascal Baron

Inventor： Manuel Miguirditchian ,  Pascal Baron

IPC: C01G56/00

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射的溶液 核燃料，在提取铀循环的下游。