Publications by authors named "Karen Van Hecke"

Partitioning and transmutation are important strategies for closing the nuclear fuel cycle. The diglycolamide extractant TODGA has played a major role in the development of solvent extraction processes for nuclear fuel reprocessing due to its good extraction performance, its hydrolytic and radiolytic stability, and its compliance with the CHON principle. However, due to drawbacks such as the tendency to form a third phase during extraction if no phase modifiers are used, continued research on diglycolamide-type extractants has led to the development of diglycolamides with decreased symmetry.

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  • Terbium-161 is a promising alternative for medical treatments due to its beta decay energy and half-life similar to lutetium-177.
  • The separation of terbium-161 from gadolinium-160 and its decay product dysprosium-161 is complicated by their similar chemical properties.
  • A new method combines electrochemical oxidation of terbium (3+) to terbium (4+) with anion exchange chromatography to improve purification efficiency for therapeutic applications.
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A new variant of the AmSel (Americium Selective Separation) system for the separation of Am(iii) from a PUREX raffinate was tested in which the aliphatic diluent was replaced by the ionic liquid Aliquat-336 nitrate. For this ionic liquid variant, the kinetics, and the influence of both the HNO concentration and the ligand concentration on the stripping were evaluated. In addition, both the original AmSel system, and the ionic liquid variant were demonstrated on a simulated highly active raffinate.

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  • Reprocessing spent nuclear fuel helps improve resource efficiency and lowers long-term radiotoxicity and heat production.
  • A new modified ligand, mTDDGA, has been proposed to simplify solvent composition in the EURO-GANEX process and enhance fission product separation.
  • Gamma irradiation tests showed that mTDDGA is more stable than the reference molecule TODGA, and some unexpected degradation compounds were identified during analysis.
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The extraction of Am(iii), Cm(iii) and Eu(iii) by 2,9-bis(5,5,8,8-tetramethyl-5,6,7,8-tetrahydro-1,2,4-benzotriazin-3-yl)-1,10-phenanthroline (CyMeBTPhen) from nitric acid solution was studied using the ionic liquid Aliquat-336 nitrate ([A336][NO]) as diluent. Results show a high selectivity of the solvent for Am(iii) and Cm(iii) over Eu(iii), but rather slow extraction kinetics. The kinetics of CyMeBTPhen were largely improved by the addition of 0.

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In the lanthanide series, Eu3+ is most easily reduced to its divalent state. Reduction of Eu3+ has been studied extensively in aqueous media that are insensitive to reducing conditions. Recently, it has been reported that reduction of Eu3+ is also feasible in aqueous nitrate solutions and that Eu2+ remained sufficiently stable in these media to conduct separation experiments.

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  • Long-lived europium-154 impurities arise during the production of medical samarium-153 in nuclear reactors.
  • A new method utilizing zinc metal and hydrophobic quaternary ammonium ionic liquid Aliquat 336 nitrate was explored for separating these europium impurities from samarium.
  • The process showed that samarium could be extracted more efficiently than europium, while an initial attempt to use dicyclohexano-18-crown-6 for capturing europium was less effective.
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Thorium-229 is a valuable, but scarce, radionuclide for nuclear clock applications or targeted alpha therapy. While it is mostly produced by the decay of U, Th can also be produced by neutron irradiation of Ra. At SCK•CEN, capsules containing mainly Th (by-product of Ra irradiation) were characterized to quantify the present amounts of Th, Th, Ac, Ra with high resolution gamma spectroscopy, after a decay period of 40 years in which Th has decayed.

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