This title appears in the Scientific Report :
2019
Please use the identifier:
http://hdl.handle.net/2128/23429 in citations.
Please use the identifier: http://dx.doi.org/10.1515/ract-2018-3089 in citations.
Homogenous Recycling of Transuranium Elements from Irradiated Fast Reactor Fuel by the EURO-GANEX Solvent Extraction Process
Homogenous Recycling of Transuranium Elements from Irradiated Fast Reactor Fuel by the EURO-GANEX Solvent Extraction Process
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 conta...
Saved in:
Personal Name(s): | Malmbeck, Rikard |
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Mugnusson, Daniel / Bourg, Stéphane / Carrott, Michael / Geist, Andreas (Corresponding author) / Hérès, Xavier / Miguirditchian, Manuel / Modolo, Giuseppe / Müllich, Udo / Miguirditchian, / Taylor, Robin / Wilden, Andreas | |
Contributing Institute: |
Nukleare Entsorgung; IEK-6 |
Published in: | Radiochimica acta, 107 (2019) 9-11, S. 917-929 |
Imprint: |
Berlin
De Gruyter
2019
|
DOI: |
10.1515/ract-2018-3089 |
Document Type: |
Journal Article |
Research Program: |
GEN IV Integrated Oxide fuels recycling strategies Safety of ACtinide Separation proceSSes Actinide reCycling by SEParation and Transmutation Nuclear Waste Management |
Link: |
Restricted Published on 2019-05-27. Available in OpenAccess from 2020-05-27. Published on 2019-05-27. Available in OpenAccess from 2020-05-27. |
Publikationsportal JuSER |
Please use the identifier: http://dx.doi.org/10.1515/ract-2018-3089 in citations.
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. |