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| Azevedo, Nuno Monteiro |
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Carrott, Michael
in Cooperation with on an Cooperation-Score of 37%
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article
Homogenous recycling of transuranium elements from irradiated fast reactor fuel by the EURO-GANEX solvent extraction process
Abstract
<jats:title>Abstract</jats:title><jats:p>The EURO-GANEX process was developed for co-separating transuranium elements from irradiated nuclear fuels. A hot flow-sheet trial was performed in a counter-current centrifugal contactor setup, using a genuine high active feed solution. Irradiated mixed (carbide, nitride) U<jats:sub>80</jats:sub>Pu<jats:sub>20</jats:sub> fast reactor fuel containing 20 % Pu was thermally treated to oxidise it to the oxide form which was then dissolved in HNO<jats:sub>3</jats:sub>. From this solution uranium was separated to >99.9 % in a primary solvent extraction cycle using 1.0 mol/L DEHiBA (<jats:italic>N</jats:italic>,<jats:italic>N</jats:italic>-di(2-ethylhexyl)isobutyramide in TPH (hydrogenated tetrapropene) as the organic phase. The raffinate solution from this process, containing 10 g/L Pu, was further processed in a second cycle of solvent extraction. In this EURO-GANEX flow-sheet, TRU and fission product lanthanides were firstly co-extracted into a solvent composed of 0.2 mol/L TODGA <jats:italic>(N</jats:italic>,<jats:italic>N</jats:italic>,<jats:italic>N</jats:italic>′,<jats:italic>N</jats:italic>′-tetra-<jats:italic>n</jats:italic>-octyl diglycolamide) and 0.5 mol/L DMDOHEMA (<jats:italic>N</jats:italic>,<jats:italic>N</jats:italic>′-dimethyl-<jats:italic>N</jats:italic>,<jats:italic>N</jats:italic>′-dioctyl-2-(2-hexyloxy-ethyl) malonamide) dissolved in Exxsol D80, separating them from most other fission and corrosion products. Subsequently, the TRU were selectively stripped from the collected loaded solvent using a solution containing 0.055 mol/L SO<jats:sub>3</jats:sub>-Ph-BTP (2,6-bis(5,6-di(3-sulphophenyl)-1,2,4-triazin-3-yl)pyridine tetrasodium salt) and 1 mol/L AHA (acetohydroxamic acid) in 0.5 mol/L HNO<jats:sub>3</jats:sub>; lanthanides were finally stripped using 0.01 mol/L HNO<jats:sub>3</jats:sub>. Approximately 99.9 % of the TRU and less than 0.1 % of the lanthanides were found in the product solution, which also contained the major fractions of Zr and Mo.</jats:p>