41 research outputs found
Recommended from our members
Solvent extraction in the nuclear industry
The role of solvent extraction in the Purex process is discussed. 2 figures, 1 table
Recommended from our members
Double liquid membrane system for the removal of actinides and lanthanides from acidic nuclear wastes
Supported liquid membranes (SLM), consisting of an organic solution of n-octyl-(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) and tributyl-phosphate (TBP) in decalin are able to perform selective separation and concentration of actinide and lanthanide ions from aqueous nitrate feed solutions and synthetic nuclear wastes. In the membrane process a possible strip solution is a mixture of formic acid and hydroxylammonium formate (HAF). The effectiveness of this strip solution is reduced and eventually nullified by the simultaneous transfer through the SLM of nitric acid which accumulates in the strip solution. A possible way to overcome this drawback is to make use of a second SLM consisting of a primary amine which is able to extract only HNO/sub 3/ from the strip solution. In this work the results obtained by experimentally studying the membrane system: synthetic nuclear waste/CMPO-TBP membrane/HCOOH-HAF strip solution/primary amine membrane/NaOH solution, are reported. They show that the use of a second liquid membrane is effective in controlling the HNO/sub 3/ concentration in the strip solution, thus allowing the actinide and lanthanide ions removal from the feed solution to proceed to completion. 15 refs., 10 figs., 1 tab
Transfer rate of some tervalent cations in the biphasic system HClO4, water-dinonylnaphthalenesulfonic acid, toluene—II
A simple purification method for the liquid cation exchanger dinonylnaphthalene sulfonic acid (DNNSA)
Association of the cyclic polyether-alkali cation complexes with thiocyanate anions in non aqueous solvents
Interfacial behaviour of trilaurylamine and its chloride and nitrate salts at a water-organic diluent interface
Recommended from our members
Actinide separations by supported liquid membranes
The work has demonstrated that actinide removal from synthetic waste solutions using both flat-sheet and hollow-fiber SLM's is a feasible chemical process at the laboratory scale level. The process is characterized by the typical features of SLM's processes: very small quantities of extractant required; the potential for operations with high feed/strip volume ratios, resulting in a corresponding concentration factor of the actinides; and simplicity of operation. Major obstacles to the implementation of the SLM technology to the decontamination of liquid nuclear wastes are the probable low resistance of polypropylene supports to high radiation fields, which may prevent the application to high-level nuclear wastes; the unknown lifetime of the SLM; and the high Na content of the separated actinide solution