METHOD FOR TREATING SPENT NUCLEAR FUEL
    1.
    发明申请
    METHOD FOR TREATING SPENT NUCLEAR FUEL 有权
    处理燃料核燃料的方法

    公开(公告)号:US20120128555A1

    公开(公告)日:2012-05-24

    申请号:US13380456

    申请日:2010-06-29

    IPC分类号: C01G56/00

    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。

    Method for treating spent nuclear fuel
    2.
    发明授权
    Method for treating spent nuclear fuel 有权
    处理乏核燃料的方法

    公开(公告)号:US08394346B2

    公开(公告)日:2013-03-12

    申请号:US13380456

    申请日:2010-06-29

    IPC分类号: C01G56/00

    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。