Electrochemical assessment of water|ionic liquid biphasic systems towards cesium extraction from nuclear waste
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The European nuclear fuel cycle (covering the EU-27, Switzerland and Ukraine) was modeled using material flow analysis (MFA).The analysis was based on publicly available data from nuclear energy agencies and industries, national trade offices, and nongover ...
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The complexation reactions between strontium (Sr2+) and octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) were studied at the aqueous vertical bar 1,2-dichloroethane (w vertical bar DCE) and aqueous vertical bar room-temperature ionic liqui ...
A BaCO3 slurry, containing radioactive C-14, is produced during the reprocessing of spent nuclear fuel. This slurry is encapsulated in a Portland-blastfurnace slag composite cement. The effect of BaCO3 on the hydration of OPC and Portland-blastfurnace slag ...
Ru-II(arene) complexes of the general formula [Ru-II(eta(6)-p-cymene)(PPh3)(L)Cl]PF6 with L = P- or N-donor systems have been synthesized and characterized. Carbohydrate-derived phosphites, imidazole or indazole have been chosen as co-ligands and different ...
The formation of either dinuclear double-stranded or pentanuclear circular helicates from a ligand containing two tridentate domains separated by a phenylene unit can be controlled by inter-ligand steric interactions which themselves are governed by the si ...
In recent years, higher discharge burn-ups and initial fuel enrichments have led to more and more heterogeneous core configurations in light water reactors (LWRs), especially at the beginning of cycle when fresh fuel assemblies are loaded next to highly bu ...
The long-term stability of biogenic uraninite with respect to oxidative dissolution is pivotal to the success of in situ bioreduction strategies for the subsurface remediation of uranium legacies. Batch and flow-through dissolution experiments were conduct ...
A novel ruthenium(II) compound, trans-cis-cis-[Ru(II)Cl-2(DMSO)(2)(2-amino-5-methyl-thiazole)(2)], (I), PMRu52 hereafter, that may be obtained from the previously described (cis and trans)[Ru(II)Cl-2(DMSO)(4)] complexes, was designed, synthesized and chara ...
The advanced fast reactors of the fourth generation should be capable to breed their own fuel from poorly fissile 238U and to recycle the actinides from their own spent fuel. However, this recycling or actually the closure of fuel cycle has negative impact ...
