6 results match your criteria: "Institute for Nuclear Materials Science Boeretang 200[Affiliation]"
Study on the sorption and desorption behavior of La and Bi by bis(2-ethylhexyl)phosphate modified activated carbon.
RSC Adv
October 2024
Belgian Nuclear Research Centre (SCK CEN), Institute for Nuclear Materials Science Boeretang 200 B-2400 Mol Belgium.
Article Synopsis
- * Various experimental factors like pH, salt concentration, and gamma irradiation were tested, showing that HDEHP/AC has a strong capacity for La (a substitute for Ac) while Bi's sorption was negatively impacted by salt concentration.
- * The study indicates that HDEHP/AC could be effective for creating a radionuclide generator for medical uses, although further optimization is necessary to refine the separation process.
Separation of americium from highly active raffinates by an innovative variant of the AmSel process based on the ionic liquid Aliquat-336 nitrate.
RSC Adv
December 2023
Belgian Nuclear Research Center (SCK CEN), Institute for Nuclear Materials Science Boeretang 200 2400 Mol Belgium
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.
View Article and Find Full Text PDFGamma radiation effects on AG MP-50 cation exchange resin and sulfonated activated carbon for bismuth-213 separation.
RSC Adv
October 2023
Belgian Nuclear Research Centre (SCK CEN), Institute for Nuclear Materials Science Boeretang 200, Mol B-2400 Belgium
Medical Ac/Bi radionuclide generators are designed to provide a local supply of the short-lived Bi for cancer treatment. However, radiation-induced damage to the sorbents commonly used in such radionuclide generators remains a major concern. In this study, the effects of gamma radiation on AG MP-50 cation exchange resin and sulfonated activated carbon (SAC) were studied by analyzing the changes in the morphological characteristics, functional groups, and the La/Bi sorption performance, with La being a suitable non-radioactive substitute for Ac.
View Article and Find Full Text PDFGamma radiolytic stability of the novel modified diglycolamide 2,2'-oxybis(,-didecylpropanamide) (mTDDGA) for grouped actinide extraction.
RSC Adv
April 2022
Belgian Nuclear Research Centre (SCK CEN), Institute for Nuclear Materials Science Boeretang 200 2400 Mol Belgium
Article Synopsis
- 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.
Selective extraction of trivalent actinides using CyMeBTPhen in the ionic liquid Aliquat-336 nitrate.
RSC Adv
February 2021
Belgian Nuclear Research Center (SCK CEN), Institute for Nuclear Materials Science Boeretang 200 2400 Mol Belgium
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.
View Article and Find Full Text PDFSeparation of samarium and europium by solvent extraction with an undiluted quaternary ammonium ionic liquid: towards high-purity medical samarium-153.
RSC Adv
May 2018
SCK•CEN, Belgian Nuclear Research Centre, Institute for Nuclear Materials Science Boeretang 200 B-2400 Mol Belgium
Article Synopsis
- 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.