Materials Map

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The Materials Map is an open tool for improving networking and interdisciplinary exchange within materials research. It enables cross-database search for cooperation and network partners and discovering of the research landscape.

The dashboard provides detailed information about the selected scientist, e.g. publications. The dashboard can be filtered and shows the relationship to co-authors in different diagrams. In addition, a link is provided to find contact information.

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The Materials Map is still under development. In its current state, it is only based on one single data source and, thus, incomplete and contains duplicates. We are working on incorporating new open data sources like ORCID to improve the quality and the timeliness of our data. We will update Materials Map as soon as possible and kindly ask for your patience.

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in Cooperation with on an Cooperation-Score of 37%

Topics

Publications (1/1 displayed)

  • 2019Homogenous recycling of transuranium elements from irradiated fast reactor fuel by the EURO-GANEX solvent extraction process61citations

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Chart of shared publication
Modolo, Giuseppe
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Geist, Andreas
1 / 6 shared
Magnusson, Daniel
1 / 1 shared
Carrott, Michael
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Bourg, Stéphane
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Wilden, Andreas
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Chart of publication period
2019

Co-Authors (by relevance)

  • Modolo, Giuseppe
  • Geist, Andreas
  • Magnusson, Daniel
  • Carrott, Michael
  • Bourg, Stéphane
  • Hérès, Xavier
  • Taylor, Robin
  • Müllich, Udo
  • Wilden, Andreas
  • Sorel, Christian
  • Malmbeck, Rikard
OrganizationsLocationPeople

article

Homogenous recycling of transuranium elements from irradiated fast reactor fuel by the EURO-GANEX solvent extraction process

  • Modolo, Giuseppe
  • Miguirditchian, Manuel
  • Geist, Andreas
  • Magnusson, Daniel
  • Carrott, Michael
  • Bourg, Stéphane
  • Hérès, Xavier
  • Taylor, Robin
  • Müllich, Udo
  • Wilden, Andreas
  • Sorel, Christian
  • Malmbeck, Rikard
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 &gt;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>

Topics
  • corrosion
  • phase
  • laser emission spectroscopy
  • nitride
  • carbide
  • Lanthanide
  • solvent extraction
  • Uranium