公开(公告)号：US20120128555A1

公开(公告)日：2012-05-24

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。

公开(公告)号：US07887767B2

公开(公告)日：2011-02-15

申请号：US11753182

申请日：2007-05-24

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

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

IPC分类号： G21C19/00

CPC分类号： G21C19/46 ,  C01G43/003 ,  C01G43/01 ,  C01G56/00 ,  C01G56/001 ,  Y02W30/883

摘要： 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.

摘要翻译： 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

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

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

IPC分类号： G21C19/00 ,  G21G4/00

CPC分类号： G21C19/46 ,  C01G43/003 ,  C01G43/01 ,  C01G56/00 ,  C01G56/001 ,  Y02W30/883

摘要： 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.

摘要翻译： 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：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。

公开(公告)号：US20090184298A1

公开(公告)日：2009-07-23

申请号：US12300705

申请日：2007-05-23

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

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

IPC分类号： C09K11/04

CPC分类号： G21C19/46 ,  C01G43/003 ,  C01G43/01 ,  C01G56/00 ,  C01G56/001 ,  Y02W30/883

摘要： 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.

摘要翻译： 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。