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Electrochemical assessment of water|ionic liquid biphasic systems towards cesium extraction from nuclear waste

Related publications (40)

Multiphysical Modelling of Soils with a Focus on Microbially Induced Calcite Precipitation

In recent years, the complexity of geomechanical problems has greatly increased as a result of the demand for new and intricate types of applications. Experimental characterization and numerical prediction by means of multiphysical approaches are in that c ...

EPFL2012

Synthesis of [Ru-II(eta(6)-p-cymene)(PPh3)(L)Cl]PF6 complexes with carbohydrate-derived phosphites, imidazole or indazole co-ligands

Christian Hartinger, Alexey Nazarov, Muhammad Hanif

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 ...

Elsevier2012

Interfacial Complexation Reactions of Sr2+ with Octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine Oxide for Understanding Its Extraction in Reprocessing Spent Nuclear Fuels

Hubert Girault, Yu Lu, Thomas James Stockmann, Zhifeng Ding

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 ...

2011

Interaction between BaCO3 and OPC/BFS composite cements at 20 degrees C and 60 degrees C

Emmanuel Gallucci

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 ...

Elsevier2011

Fission Rates Measured Using High-Energy Gamma-Rays from Short Half-Life Fission Products in Fresh and Spent Nuclear Fuel

Hanna Kröhnert

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 ...

EPFL2011

Nuclear Energy in Europe: Uranium Flow Modeling and Fuel Cycle Scenario Trade-Offs from a Sustainability Perspective

Claudia Rebeca Binder Signer

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 ...

2011

Controlling the formation of metallosupramolecular assemblies by metal ionic radii

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 ...

2010

Trans-cis-cis-[RuCl2(DMSO)(2)(2-amino-5-methyl-thiazole)(2)], (PMRu52), a novel ruthenium(II) compound acting as a strong inhibitor of cathepsin B

Angela Casini

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 ...

2010

Comparative dissolution kinetics of biogenic and chemogenic uraninite under oxidizing conditions in the presence of carbonate

Rizlan Bernier-Latmani, Harish Veeramani, Jonathan Sharp

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 ...

Elsevier2009

EQL3D: ERANOS based equilibrium fuel cycle procedure for fast reactors

Konstantin Mikityuk, Jiri Krepel

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 ...

Elsevier2009

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