Water soluble anionic and cationic bis-triazine ligands are able to suppress (mask) the extraction of corrosion and fission products such as Ni(II) and Pd(II) that are found in PUREX raffinates. Thus it is possible to separate these elements from the minor actinide Am(III). Although some masking agents have previously been developed that retard the extraction of Pd(II), this is the first time a masking agent has been developed for Ni(II).
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http://dx.doi.org/10.1039/c5cc02336j | DOI Listing |
Materials (Basel)
December 2024
European Commission, Joint Research Centre (JRC), 76125 Karlsruhe, Germany.
This work presents the synthesis, purification, and characterization of a molten salt fuel for the irradiation experiment SALIENT-03 (SALt Irradiation ExperimeNT), a collaborative effort between the Nuclear Research and Consultancy Group and the Joint Research Centre, European Commission. The primary objective of the project is to investigate the corrosion behavior of selected Ni-alloy based structural materials which are being considered for the construction of fluoride molten salt reactors. During the test, these materials will be exposed to selected liquid molten fuel salts under irradiation in the High Flux Reactor in Petten, the Netherlands.
View Article and Find Full Text PDFInorg Chem
December 2024
Canadian Nuclear Laboratories, Chalk River Laboratories, Chalk River, ON K0J1J0, Canada.
We investigate the trapping properties of iodine, cesium, and tellurium in uranium dioxide, using the Hubbard-corrected density functional theory (DFT+). In order to avoid the metastable states inherent to this method, we use the occupation matrix control (OMC) scheme, which also allows us to monitor the oxidation states of the different species. The most favorable trapping sites, oxidation states, and solubility of I, Cs, and Te are evaluated in stoichiometric UO.
View Article and Find Full Text PDFMaterials (Basel)
November 2024
Univ. Lille, CNRS, Centrale Lille, Univ. Artois, UMR 8181, UCCS-Unité de Catalyse et Chimie du Solide, F-59000 Lille, France.
Beryllium metal is used as neutron moderator and reflector or multiplier in certain types of fission or fusion reactors. Dismantling of these reactors will produce radioactive beryllium waste, classified as low- or intermediate-level waste, that will need to be stabilised and solidified before being sent to disposal. The cementation process is under consideration because it may offer a good compromise between simplicity of implementation, cost, and quality of the final cemented wasteform.
View Article and Find Full Text PDFACS Appl Mater Interfaces
August 2024
Materials Science and Chemical Engineering, Stony Brook University, Stony Brook, New York 11794, United States.
Materials (Basel)
July 2024
Dutch Institute for Fundamental Energy Research (DIFFER), 5612 AJ Eindhoven, The Netherlands.
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