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@INPROCEEDINGS{Modolo:865791,
      author       = {Modolo, Giuseppe and Wilden, Andreas and Kaufholz, Peter
                      and Marie, Cécile and Vanel, Vincent and Duchesne,
                      Marie-Thérèse and Russello, Emilie and Miguirditchian,
                      Manuel and Bourg, Stéphane and Casnati, Allessandro and
                      Geist, Andreas},
      title        = {{S}elective separation of {A}m({III}) from {PUREX}
                      {R}affinate with a {TODGA}-based solvent using innovative
                      hydrophilic complexing agents},
      publisher    = {Americal Nuclear Society},
      reportid     = {FZJ-2019-05099},
      pages        = {92-98},
      year         = {2019},
      abstract     = {Americium is the main contributor to the
                      longtermradiotoxicity and to the heat generation of
                      glassesused for HLW conditioning. To decrease these
                      impactsand to avoid the difficult recycling of curium, the
                      selectiveseparation and recovery of a pure americium
                      productdirectly from PUREX raffinate is envisaged in this
                      study.The new approach is based on the co-extraction
                      oflanthanide(III) and actinide(III) cations from a
                      PUREXraffinate into an organic phase containing
                      N,N,N’,N’-tetraoctyl-diglycolamide (TODGA) as
                      extractant,followed by the subsequent selective stripping of
                      Am(III)and separation from Cm(III) and lanthanides.
                      Threewater-soluble selective ligands were studied:
                      H4TPAENdeveloped at the CEA Marcoule, TS-BTPhen developed
                      atthe University of Reading, and SO3-Ph-BTBP developedat
                      KIT. Very promising results were achieved for allsystems
                      with a quite high Cm(III)/Am(III) selectivitybetween 3-4 to
                      carry out the difficult separation atreasonably high process
                      relevant nitric acid acidities.Numerous batch experimental
                      data were acquired for thedevelopment of the extraction
                      model. Finally, tests onsingle centrifugal contactors were
                      conducted to getinformation on the kinetic and hydraulic
                      performance ofthe system. Finally, tests on single
                      centrifugal contactorswere conducted to get information on
                      the kinetic andhydraulic performance of the system.},
      month         = {Sep},
      date          = {2019-09-22},
      organization  = {Global/Top Fuel 2019, Seattle, WA
                       (USA), 22 Sep 2019 - 26 Sep 2019},
      cin          = {IEK-6},
      cid          = {I:(DE-Juel1)IEK-6-20101013},
      pnm          = {161 - Nuclear Waste Management (POF3-161) / GENIORS - GEN
                      IV Integrated Oxide fuels recycling strategies (755171) /
                      SACSESS - Safety of ACtinide Separation proceSSes (323282)},
      pid          = {G:(DE-HGF)POF3-161 / G:(EU-Grant)755171 /
                      G:(EU-Grant)323282},
      typ          = {PUB:(DE-HGF)8},
      url          = {https://juser.fz-juelich.de/record/865791},
}