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@ARTICLE{Malmbeck:862494,
      author       = {Malmbeck, Rikard and Mugnusson, Daniel and Bourg, Stéphane
                      and Carrott, Michael and Geist, Andreas and Hérès, Xavier
                      and Miguirditchian, Manuel and Modolo, Giuseppe and
                      Müllich, Udo and Miguirditchian, and Taylor, Robin and
                      Wilden, Andreas},
      title        = {{H}omogenous {R}ecycling of {T}ransuranium {E}lements from
                      {I}rradiated {F}ast {R}eactor {F}uel by the {EURO}-{GANEX}
                      {S}olvent {E}xtraction {P}rocess},
      journal      = {Radiochimica acta},
      volume       = {107},
      number       = {9-11},
      issn         = {0033-8230},
      address      = {Berlin},
      publisher    = {˜Deœ Gruyter},
      reportid     = {FZJ-2019-02800},
      pages        = {917-929},
      year         = {2019},
      abstract     = {The EURO-GANEX process was developed forco-separating
                      transuranium elements from irradiatednuclear fuels. A hot
                      flow-sheet trial was performed in acounter-current
                      centrifugal contactor setup, using a genuinehigh active feed
                      solution. Irradiated mixed (carbide,nitride) U80Pu20 fast
                      reactor fuel containing 20 $\%$ Pu wasthermally treated to
                      oxidise it to the oxide form which wasthen dissolved in
                      HNO3. From this solution uranium wasseparated to >99.9 $\%$
                      in a primary solvent extraction cycleusing 1.0 mol/L DEHiBA
                      (N,N-di(2-ethylhexyl)isobutyramidein TPH (hydrogenated
                      tetrapropene) as the organicphase. The raffinate solution
                      from this process, containing10 g/L Pu, was further
                      processed in a second cycle of solventextraction. In this
                      EURO-GANEX flow-sheet, TRU andfission product lanthanides
                      were firstly co-extracted intoa solvent composed of 0.2
                      mol/L TODGA (N,N,N′,N′-tetran-octyl diglycolamide) and
                      0.5 mol/L DMDOHEMA
                      (N,N′-dimethyl-N,N′-dioctyl-2-(2-hexyloxy-ethyl)
                      malonamide)dissolved in Exxsol D80, separating them from
                      most otherfission and corrosion products. Subsequently, the
                      TRUwere selectively stripped from the collected loaded
                      solventusing a solution containing 0.055 mol/L
                      SO3-Ph-BTP(2,6-bis(5,6-di(3-sulphophenyl)-1,2,4-triazin-3-yl)pyridinetetrasodium
                      salt) and 1 mol/L AHA (acetohydroxamicacid) in 0.5 mol/L
                      HNO3; lanthanides were finally strippedusing 0.01 mol/L
                      HNO3. Approximately 99.9 $\%$ of the TRUand less than 0.1
                      $\%$ of the lanthanides were found in theproduct solution,
                      which also contained the major fractionsof Zr and Mo.},
      cin          = {IEK-6},
      ddc          = {610},
      cid          = {I:(DE-Juel1)IEK-6-20101013},
      pnm          = {161 - Nuclear Waste Management (POF3-161) / ACSEPT -
                      Actinide reCycling by SEParation and Transmutation (211267)
                      / SACSESS - Safety of ACtinide Separation proceSSes (323282)
                      / GENIORS - GEN IV Integrated Oxide fuels recycling
                      strategies (755171)},
      pid          = {G:(DE-HGF)POF3-161 / G:(EU-Grant)211267 /
                      G:(EU-Grant)323282 / G:(EU-Grant)755171},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000489293000008},
      doi          = {10.1515/ract-2018-3089},
      url          = {https://juser.fz-juelich.de/record/862494},
}