[PDF] Top 20 Lanthanides extraction processes in molten fluoride media. Application to nuclear spent fuel reprocessing
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Lanthanides extraction processes in molten fluoride media. Application to nuclear spent fuel reprocessing
... of extraction of lanthanide (Ln) elements from molten salts in the general frame of reprocessing nuclear wastes; one of them is chemical: the precipitation of Ln ions in ... Voir le document complet
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Electrochemical extraction of europium from molten fluoride media
... Introduction In France, alternative solutions for radioactive wastes manage- ment are under examination since 1991, in the frame of Partitioning and Transmutation (P&T) concepts aiming at significantly ... Voir le document complet
8
Electrochemical study of the Eu(III)/Eu(II) system in molten fluoride media
... dissolved in molten salt ...the lanthanides (Ln) such as Ce, Sm, Nd, Eu, Gd, Dy have very comparable chemical properties with the An, which makes the An-Ln separation very ...Furthermore, in ... Voir le document complet
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Ruthenium Speciation in Extraction Phases of Nuclear Fuel Recycling Processes
... contribution to the total radiotoxic inventory is negligible in spent nuclear ...reason, reprocessing prospects only con- sider the recovery of neptunium, americium and ...high-level ... Voir le document complet
174
Zirconium(IV) electrochemical behavior and electrorefining in molten fluoride salts
... used in various activity sectors and particularly for nuclear applications because of its physicochemical properties: a low cross-section of neutron capture, excellent mechanical and corrosion resistance ... Voir le document complet
2
Co-reduction of aluminium and lanthanide ions in molten fluorides : application to cerium and samarium extraction from nuclear waste
... the reprocessing of advanced fuels and transmutation blankets which are expected to have a high content of Pu and minor actinide and high burn ...transparent to neutrons. Pyrometallurgical ... Voir le document complet
8
New Methodology for Bias Identification and Estimation – Application to Nuclear Fuel Recycling Process
... unit to the other. The measured variables used in the DR problem are volumetric flowrates, densities for each arc, temperature, and uranium, plutonium, nitric acid and TBP composition for specific ... Voir le document complet
8
Feasibility of the electrochemical way in molten fluorides for separating Thorium and Lanthanides and extracting Lanthanides from the solvent.
... shown in figure 5, exhibits only one peak in the cathodic run at ...found to be one and so corresponds to the reduction of Sm III into Sm II ...process in this step is controlled by the ... Voir le document complet
32
Extraction du palladium par un malonamide : comportement et spécificités par rapport aux lanthanides
... coordination du palladium(II) en supposant une coordination bidentate du DMDOHEMA, via les deux atomes d’oxygène des deux carbonyles. Les études sur les troisièmes phases montrent que celles-ci se présentent le plus ... Voir le document complet
215
Reactive transport modeling in fractured media of nuclear glass for industrial application
... arrivant in fine au transport réactif à l’échelle d’un bloc industriel, en prenant en compte la variabilité du réseau et différentes conditions d’altération (stockage, expérience échelle 1 ... Voir le document complet
219
New Methodology for Bias Identification and Estimation – Application to Nuclear Fuel Recycling Process
... (DR) in case of numerous biases. DR improves the degree of confidence in available information and generates consistent ...leads to information loss and possibly an inability to apply ... Voir le document complet
7
Implementation of americium recycling demonstration from spent nuclear fuel in the highlevel shielded process line CBP in the ATALANTE facility
... CEA | 10 th OCTOBER 2016 | PAGE 12 3 rd STEP: PUREX RAFFINATE CONCENTRATION Aim of the operation The EXAm process, which allows the selective and quantitative recovery of americium from a PUREX raffinate by ... Voir le document complet
18
Direct electrochemical reduction of solid uranium oxide in molten fluoride salts
... out in LiF–CaF 2 (+2 ...anode. In this case, oxidation of oxide ions present in the melt yields O 2 gas evolution on the ...associated to oxide direct reduction were observed at a potential ... Voir le document complet
7
Study of irradiated and non-irradiated MOX fuel reprocessing
... HAL Id: cea-02394092 https://hal-cea.archives-ouvertes.fr/cea-02394092 Submitted on 24 Feb 2020 HAL is a multi-disciplinary open access archive for the deposit and dissemination of sci- entific research documents, ... Voir le document complet
3
Development of an HILIC-ESI-MS method for lanthanide speciation in nuclear fuel treatment processes
... selected to separate them [2]. Evelyne BLANCHARD 1,2* , Carole BRESSON 1 , Anthony NONELL 1 , Benoit MARTELAT 1,2 , Frédéric CHARTIER 3 1 CEA Saclay, DEN, DANS, DPC, SEARS, LANIE, Université Paris-Saclay, F-91191 ... Voir le document complet
2
molybdenum behaviour during u-al research reactor spent fuel dissolution
... above in order to retain ...described in [2]. To ensure that solubility is reached, every experiment was carried out with a large excess of molybdenum ...instance, in our operating ... Voir le document complet
11
Denitrification of groundwater using Brewer's spent grain as biofilter media
... need to develop simple, low-cost treatment sys- tems (both in terms of construction and ongoing maintenance) to remove NO 3 − from effluents and from point source discharges from drained agricultural ... Voir le document complet
3
UEE Day 2019 - Investigating gas transfers processes in argillaceous media in the framework of nuclear waste disposal
... issue In the fractured zone: development of a 2 𝑛𝑑 gradient THM model to reproduce simultaneously the fluid flows mechanisms and the strain localisation process In the low-permeable sound rock: ... Voir le document complet
1
Verification of Dose Rate Calculations for PWR Spent Fuel Assemblies
... created in UOX fuel during irradiation and sometimes recycled in the form of mixed oxide (MOX) fuel can be an acquisition target for those wishing to obtain it for weapons ...MOX ... Voir le document complet
6
Assessment of the $^{153}$Eu and $^{154}$Eu neutron capture cross sections from the Integral Data Assimilation of spent nuclear fuel experiments
... that in some specific cases, the independent replicas method could propagate numerical biases along the successive transport / depletion steps ...reported in Table ... Voir le document complet
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