001     865791
005     20240708133919.0
037 _ _ |a FZJ-2019-05099
041 _ _ |a English
100 1 _ |a Modolo, Giuseppe
|0 P:(DE-Juel1)130383
|b 0
|e Corresponding author
111 2 _ |a Global/Top Fuel 2019
|c Seattle, WA
|d 2019-09-22 - 2019-09-26
|w USA
245 _ _ |a Selective separation of Am(III) from PUREX Raffinate with a TODGA-based solvent using innovative hydrophilic complexing agents
260 _ _ |c 2019
|b Americal Nuclear Society
300 _ _ |a 92-98
336 7 _ |a CONFERENCE_PAPER
|2 ORCID
336 7 _ |a Conference Paper
|0 33
|2 EndNote
336 7 _ |a INPROCEEDINGS
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336 7 _ |a conferenceObject
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336 7 _ |a Output Types/Conference Paper
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336 7 _ |a Contribution to a conference proceedings
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|s 1571645164_26208
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520 _ _ |a 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.
536 _ _ |a 161 - Nuclear Waste Management (POF3-161)
|0 G:(DE-HGF)POF3-161
|c POF3-161
|f POF III
|x 0
536 _ _ |a GENIORS - GEN IV Integrated Oxide fuels recycling strategies (755171)
|0 G:(EU-Grant)755171
|c 755171
|f NFRP-2016-2017-1
|x 1
536 _ _ |a SACSESS - Safety of ACtinide Separation proceSSes (323282)
|0 G:(EU-Grant)323282
|c 323282
|f FP7-Fission-2012
|x 2
700 1 _ |a Wilden, Andreas
|0 P:(DE-Juel1)130438
|b 1
700 1 _ |a Kaufholz, Peter
|0 P:(DE-Juel1)156235
|b 2
700 1 _ |a Marie, Cécile
|0 P:(DE-HGF)0
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700 1 _ |a Vanel, Vincent
|0 P:(DE-HGF)0
|b 4
700 1 _ |a Duchesne, Marie-Thérèse
|0 P:(DE-HGF)0
|b 5
700 1 _ |a Russello, Emilie
|0 P:(DE-HGF)0
|b 6
700 1 _ |a Miguirditchian, Manuel
|0 P:(DE-HGF)0
|b 7
700 1 _ |a Bourg, Stéphane
|0 P:(DE-HGF)0
|b 8
700 1 _ |a Casnati, Allessandro
|0 P:(DE-HGF)0
|b 9
700 1 _ |a Geist, Andreas
|0 P:(DE-HGF)0
|b 10
909 C O |o oai:juser.fz-juelich.de:865791
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910 1 _ |a Forschungszentrum Jülich
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913 1 _ |a DE-HGF
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914 1 _ |y 2019
920 _ _ |l yes
920 1 _ |0 I:(DE-Juel1)IEK-6-20101013
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981 _ _ |a I:(DE-Juel1)IFN-2-20101013


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