Title: Development of a New Flowsheet for Co-Separating the Transuranic Actinides: The "Euro-GANEX" Process
Authors: CARROTT MichaelBELL K.j.BROWN J.GEIST A.GREGSON CHERES XavierMAHER C.j.MALMBECK RikardMASON CMODOLO G.MULLICH UdoSARSFIELD MarkWILDEN AndreasTAYLOR Robin
Citation: SOLVENT EXTRACTION AND ION EXCHANGE vol. 32 no. 5 p. 447-467
Publisher: TAYLOR & FRANCIS INC
Publication Year: 2014
JRC N°: JRC91452
ISSN: 0736-6299
URI: http://www.tandfonline.com/doi/abs/10.1080/07366299.2014.896580
http://publications.jrc.ec.europa.eu/repository/handle/JRC91452
DOI: 10.1080/07366299.2014.896580
Type: Articles in periodicals and books
Abstract: A flowsheet for a novel GANEX (Grouped ActiNide EXtraction) process has been tested in a spiked flowsheet trial in a 32 stage plutonium-active centrifugal contactor rig with a simulant feed that contained 10 g/L plutonium as well as some fission products and other transuranic actinides. The solvent system used was a combination of 0.2 mol/L N,N,N’,N’-tetraoctyl diglycolamide (TODGA) and 0.5 mol/L N,N‘-(dimethyl-N,N‘-dioctylhexylethoxy-malonamide (DMDOHEMA) in a kerosene diluent that co-extracted actinides and lanthanides. Actinides were subsequently selectively co-stripped away from the lanthanides using a sulphonated and, therefore, hydrophilic bis-triazinyl pyridine (BTP) complexant in conjunction with acetohydroxamic acid (AHA). Plutonium and americium recoveries were high with decontamination factors across the strip contactors of ~14,000 and ~390 respectively. However, approximately 30 % of neptunium was lost to the aqueous raffinate which was due to a large recycle within the first extract-scrub section. Some recycle of strontium was also observed but in this case it was fully directed to the raffinate stream. In the stripping section, a small fraction of europium (taken as a model lanthanide ion), ca. 7 %, was found in the actinide product stream. Modelling of selected data using the PAREX code has shown that, even with a relatively simplistic treatment, reasonable agreement between modelling and experiment can be obtained; giving confidence in the use of modelling to refine the GANEX flowsheet design prior to further testing with irradiated fast reactor fuel.
JRC Directorate:Nuclear Safety and Security

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