scholarly journals Demonstration of Caustic-Side Solvent Extraction with Optimized Solvent in the 2-cm Centrifugal Contactor Apparatus Using Dissolved Salt Cake from Tank 37H

2002 ◽  
Author(s):  
M A Norato
Keyword(s):  
Solvent Extraction ◽  
Salt Cake ◽  
Centrifugal Contactor

scholarly journals The use of a centrifugal contactor for component concentration by solvent extraction

1992 ◽  
Author(s):  
R.A. Leonard ◽  
D.G. Wygmans ◽  
M.J. McElwee ◽  
M.O. Wasserman ◽  
G.F. Vandegrift
Keyword(s):  
Solvent Extraction ◽  
Component Concentration ◽  
Centrifugal Contactor

scholarly journals The use of a centrifugal contactor for component concentration by solvent extraction

1992 ◽  
Author(s):  
R Leonard ◽  
D Wygmans ◽  
M McElwee ◽  
M Wasserman ◽  
G Vandegrift
Keyword(s):  
Solvent Extraction ◽  
Component Concentration ◽  
Centrifugal Contactor

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

2019 ◽  
Vol 107 (9-11) ◽  
pp. 917-929 ◽  
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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