Mixer-settler runs for the evaluation of tri-iso-amyl phosphate (TiAP) as an alternate extractant to tri-n-butyl phosphate (TBP) for reprocessing applications

AbstractAs part of the studies on the development of alternate extractants for fast reactor fuel reprocessing, a mixer-settler facility for performing counter-current solvent extraction runs with radioactive materials has been set up and commissioned in our laboratory for flow sheet development experiments. Mixer-settler runs were carried out with 1.1 M TiAP/Heavy Normal Paraffin (HNP) as the solvent using the above facility to test the equipment as well as the behaviour of the solvent for continuous solvent extraction processes. Stage profile data generated for the extraction and stripping of nitric acid with TiAP based solvent have been reported. Studies carried out on the continuous counter-current extraction and stripping of U(VI) for 1.1 M TiAP/HNP-U(VI)-HNO

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A Dynamic Model for Radiotracer Determination of Solute Residence Time Distribution in Counter-Current Pulse Column Solvent Extraction Processes

Separation Science and Technology ◽

10.1080/01496398708068952 ◽

1987 ◽

Vol 22 (2-3) ◽

pp. 269-280 ◽

Cited By ~ 1

Author(s):

R. P. Gardner ◽

M. N. Iqbal ◽

K. Verghese

Keyword(s):

Solvent Extraction ◽

Dynamic Model ◽

Current Pulse ◽

Residence Time ◽

Time Distribution ◽

Residence Time Distribution ◽

Pulse Column ◽

Extraction Processes ◽

Counter Current

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Homogenous recycling of transuranium elements from irradiated fast reactor fuel by the EURO-GANEX solvent extraction process

Radiochimica Acta ◽

10.1515/ract-2018-3089 ◽

2019 ◽

Vol 107 (9-11) ◽

pp. 917-929 ◽

Cited By ~ 14

Author(s):

Rikard Malmbeck ◽

Daniel Magnusson ◽

Stéphane Bourg ◽

Michael Carrott ◽

Andreas Geist ◽

...

Keyword(s):

Solvent Extraction ◽

Fast Reactor ◽

Feed Solution ◽

Extraction Process ◽

Reactor Fuel ◽

Acetohydroxamic Acid ◽

Flow Sheet ◽

Transuranium Elements ◽

Fast Reactor Fuel ◽

Centrifugal Contactor

Abstract The EURO-GANEX process was developed for co-separating transuranium elements from irradiated nuclear fuels. A hot flow-sheet trial was performed in a counter-current centrifugal contactor setup, using a genuine high active feed solution. Irradiated mixed (carbide, nitride) U80Pu20 fast reactor fuel containing 20 % Pu was thermally treated to oxidise it to the oxide form which was then dissolved in HNO3. From this solution uranium was separated to >99.9 % in a primary solvent extraction cycle using 1.0 mol/L DEHiBA (N,N-di(2-ethylhexyl)isobutyramide in TPH (hydrogenated tetrapropene) as the organic phase. The raffinate solution from this process, containing 10 g/L Pu, was further processed in a second cycle of solvent extraction. In this EURO-GANEX flow-sheet, TRU and fission product lanthanides were firstly co-extracted into a solvent composed of 0.2 mol/L TODGA (N,N,N′,N′-tetra-n-octyl diglycolamide) and 0.5 mol/L DMDOHEMA (N,N′-dimethyl-N,N′-dioctyl-2-(2-hexyloxy-ethyl) malonamide) dissolved in Exxsol D80, separating them from most other fission and corrosion products. Subsequently, the TRU were selectively stripped from the collected loaded solvent using a solution containing 0.055 mol/L SO3-Ph-BTP (2,6-bis(5,6-di(3-sulphophenyl)-1,2,4-triazin-3-yl)pyridine tetrasodium salt) and 1 mol/L AHA (acetohydroxamic acid) in 0.5 mol/L HNO3; lanthanides were finally stripped using 0.01 mol/L HNO3. Approximately 99.9 % of the TRU and less than 0.1 % of the lanthanides were found in the product solution, which also contained the major fractions of Zr and Mo.

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