Hauptseite > Publikationsdatenbank > Homogenous Recycling of Transuranium Elements from Irradiated Fast Reactor Fuel by the EURO-GANEX Solvent Extraction Process > print |
001 | 862494 | ||
005 | 20240712084555.0 | ||
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041 | _ | _ | |a English |
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100 | 1 | _ | |a Malmbeck, Rikard |0 P:(DE-HGF)0 |b 0 |
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 De Gruyter |
336 | 7 | _ | |a article |2 DRIVER |
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336 | 7 | _ | |a Journal Article |b journal |m journal |0 PUB:(DE-HGF)16 |s 1574344035_25087 |2 PUB:(DE-HGF) |
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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) |0 G:(DE-HGF)POF3-161 |c POF3-161 |f POF III |x 0 |
536 | _ | _ | |a ACSEPT - Actinide reCycling by SEParation and Transmutation (211267) |0 G:(EU-Grant)211267 |c 211267 |f FP7-Fission-2007 |x 1 |
536 | _ | _ | |a SACSESS - Safety of ACtinide Separation proceSSes (323282) |0 G:(EU-Grant)323282 |c 323282 |f FP7-Fission-2012 |x 2 |
536 | _ | _ | |a GENIORS - GEN IV Integrated Oxide fuels recycling strategies (755171) |0 G:(EU-Grant)755171 |c 755171 |f NFRP-2016-2017-1 |x 3 |
700 | 1 | _ | |a Mugnusson, Daniel |0 P:(DE-HGF)0 |b 1 |
700 | 1 | _ | |a Bourg, Stéphane |0 P:(DE-HGF)0 |b 2 |
700 | 1 | _ | |a Carrott, Michael |0 P:(DE-HGF)0 |b 3 |
700 | 1 | _ | |a Geist, Andreas |0 P:(DE-HGF)0 |b 4 |e Corresponding author |
700 | 1 | _ | |a Hérès, Xavier |0 P:(DE-HGF)0 |b 5 |
700 | 1 | _ | |a Miguirditchian, Manuel |0 P:(DE-HGF)0 |b 6 |
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700 | 1 | _ | |a Taylor, Robin |0 P:(DE-HGF)0 |b 10 |
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773 | _ | _ | |a 10.1515/ract-2018-3089 |0 PERI:(DE-600)2039575-9 |n 9-11 |p 917-929 |t Radiochimica acta |v 107 |y 2019 |x 0033-8230 |
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 |y Restricted |
856 | 4 | _ | |y Published on 2019-05-27. Available in OpenAccess from 2020-05-27. |u https://juser.fz-juelich.de/record/862494/files/Accepted%20Manuscript.pdf |
856 | 4 | _ | |y Published on 2019-05-27. Available in OpenAccess from 2020-05-27. |x pdfa |u https://juser.fz-juelich.de/record/862494/files/Accepted%20Manuscript.pdf?subformat=pdfa |
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