000865791 001__ 865791
000865791 005__ 20240708133919.0
000865791 037__ $$aFZJ-2019-05099
000865791 041__ $$aEnglish
000865791 1001_ $$0P:(DE-Juel1)130383$$aModolo, Giuseppe$$b0$$eCorresponding author
000865791 1112_ $$aGlobal/Top Fuel 2019$$cSeattle, WA$$d2019-09-22 - 2019-09-26$$wUSA
000865791 245__ $$aSelective separation of Am(III) from PUREX Raffinate with a TODGA-based solvent using innovative hydrophilic complexing agents
000865791 260__ $$bAmerical Nuclear Society$$c2019
000865791 300__ $$a92-98
000865791 3367_ $$2ORCID$$aCONFERENCE_PAPER
000865791 3367_ $$033$$2EndNote$$aConference Paper
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000865791 3367_ $$0PUB:(DE-HGF)8$$2PUB:(DE-HGF)$$aContribution to a conference proceedings$$bcontrib$$mcontrib$$s1571645164_26208
000865791 520__ $$aAmericium 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.
000865791 536__ $$0G:(DE-HGF)POF3-161$$a161 - Nuclear Waste Management (POF3-161)$$cPOF3-161$$fPOF III$$x0
000865791 536__ $$0G:(EU-Grant)755171$$aGENIORS - GEN IV Integrated Oxide fuels recycling strategies (755171)$$c755171$$fNFRP-2016-2017-1$$x1
000865791 536__ $$0G:(EU-Grant)323282$$aSACSESS - Safety of ACtinide Separation proceSSes (323282)$$c323282$$fFP7-Fission-2012$$x2
000865791 7001_ $$0P:(DE-Juel1)130438$$aWilden, Andreas$$b1
000865791 7001_ $$0P:(DE-Juel1)156235$$aKaufholz, Peter$$b2
000865791 7001_ $$0P:(DE-HGF)0$$aMarie, Cécile$$b3
000865791 7001_ $$0P:(DE-HGF)0$$aVanel, Vincent$$b4
000865791 7001_ $$0P:(DE-HGF)0$$aDuchesne, Marie-Thérèse$$b5
000865791 7001_ $$0P:(DE-HGF)0$$aRussello, Emilie$$b6
000865791 7001_ $$0P:(DE-HGF)0$$aMiguirditchian, Manuel$$b7
000865791 7001_ $$0P:(DE-HGF)0$$aBourg, Stéphane$$b8
000865791 7001_ $$0P:(DE-HGF)0$$aCasnati, Allessandro$$b9
000865791 7001_ $$0P:(DE-HGF)0$$aGeist, Andreas$$b10
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000865791 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)130383$$aForschungszentrum Jülich$$b0$$kFZJ
000865791 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)130438$$aForschungszentrum Jülich$$b1$$kFZJ
000865791 9131_ $$0G:(DE-HGF)POF3-161$$1G:(DE-HGF)POF3-160$$2G:(DE-HGF)POF3-100$$3G:(DE-HGF)POF3$$4G:(DE-HGF)POF$$aDE-HGF$$bEnergie$$lNukleare Entsorgung und Sicherheit sowie Strahlenforschung$$vNuclear Waste Management$$x0
000865791 9141_ $$y2019
000865791 920__ $$lyes
000865791 9201_ $$0I:(DE-Juel1)IEK-6-20101013$$kIEK-6$$lNukleare Entsorgung und Reaktorsicherheit$$x0
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