001     862494
005     20240712084555.0
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100 1 _ |a Malmbeck, Rikard
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245 _ _ |a Homogenous Recycling of Transuranium Elements from Irradiated Fast Reactor Fuel by the EURO-GANEX Solvent Extraction Process
260 _ _ |a Berlin
|c 2019
|b ˜Deœ Gruyter
336 7 _ |a article
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520 _ _ |a 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.
536 _ _ |a 161 - Nuclear Waste Management (POF3-161)
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536 _ _ |a ACSEPT - Actinide reCycling by SEParation and Transmutation (211267)
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536 _ _ |a SACSESS - Safety of ACtinide Separation proceSSes (323282)
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536 _ _ |a GENIORS - GEN IV Integrated Oxide fuels recycling strategies (755171)
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700 1 _ |a Mugnusson, Daniel
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700 1 _ |a Bourg, Stéphane
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700 1 _ |a Carrott, Michael
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700 1 _ |a Geist, Andreas
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700 1 _ |a Hérès, Xavier
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700 1 _ |a Miguirditchian, Manuel
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700 1 _ |a Modolo, Giuseppe
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700 1 _ |a Müllich, Udo
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700 1 _ |a Miguirditchian,
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700 1 _ |a Taylor, Robin
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700 1 _ |a Wilden, Andreas
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773 _ _ |a 10.1515/ract-2018-3089
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|y 2019
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856 4 _ |u https://juser.fz-juelich.de/record/862494/files/%5BRadiochimica%20Acta%5D%20Homogenous%20recycling%20of%20transuranium%20elements%20from%20irradiated%20fast%20reactor%20fuel%20by%20the%20EURO-GANEX%20solvent%20extraction%20process.pdf
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856 4 _ |y Published on 2019-05-27. Available in OpenAccess from 2020-05-27.
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856 4 _ |y Published on 2019-05-27. Available in OpenAccess from 2020-05-27.
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