scholarly journals Temperature management of centrifugal contactor for caustic-side solvent extraction of cesium from tank waste.

2001 ◽  
Author(s):  
H A Arafat ◽  
R A Leonard
Keyword(s):  
Solvent Extraction ◽  
Temperature Management ◽  
Centrifugal Contactor ◽  
Tank Waste

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.

scholarly journals DEVELOPING AND TESTING AN ALKALINE-SIDE SOLVENT EXTRACTION PROCESS FOR TECHNETIUM SEPARATION FROM TANK WASTE

1999 ◽  
Vol 34 (6-7) ◽  
pp. 1043-1068 ◽  
Author(s):  
Ralph A. Leonard ◽  
Cliff Conner ◽  
Matthew W. Liberatore ◽  
Peter V. Bonnesen ◽  
Derek J. Presley ◽  
...  
Keyword(s):  
Solvent Extraction ◽  
Extraction Process ◽  
Alkaline Side ◽  
Tank Waste

Proof-of-Concept Flowsheet Tests for Cesium Removal from Tank Waste by Caustic-Side Solvent Extraction

2002 ◽  
Vol 713 ◽  
Author(s):  
David B. Chamberlain ◽  
Scott Aase ◽  
Hassan A. Arafat ◽  
Cliff Conner ◽  
Ralph A. Leonard ◽  
...  
Keyword(s):  
Solvent Extraction ◽  
National Laboratory ◽  
Argonne National Laboratory ◽  
Decontamination Factor ◽  
High Level Waste ◽  
Savannah River ◽  
Alkyl Aryl ◽  
Oak Ridge ◽  
Cesium Removal ◽  
Tank Waste

ABSTRACTA caustic-side solvent extraction (CSSX) process to remove cesium from Savannah River Site (SRS) high-level waste has been developed through a joint program with Oak Ridge National Laboratory (ORNL), the Savannah River Technical Center (SRTC), and Argonne National Laboratory (ANL). The CSSX solvent consists of four components: (1) an extractant, a calixarene crown, calix[4]arene-bis(tert-octylbenzo-crown-6) designated BOBCalixC6, (2) a modifier, an alkyl aryl polyether, 1-(2,2,3,3,-tetrafluoropropoxy)-3-(4-sec-butylphenoxy)-2-propanol, also called Cs-7SB, (3) a suppressant, an alkyl amine, trioctylamine (TOA), and (4) a diluent, Isopar®L. The solvent composition is 0.01 M BOBCalixC6, 0.50 M Cs-7SB, and 0.001 M TOA in Isopar®L. In this program we have developed and demonstrated a flowsheet that can be used to process SRS tank waste. To this end, a series of flowsheet tests were completed using simulated waste in a 2-cm centrifugal contactor at ANL. Three short-term (3-4 hours) tests were completed to demonstrate various aspects of the flowsheet. These tests were followed by a 71-h test where the solvent was recycled 42 times. In each case, we met or exceeded the key process goals: (1) cesium removal from the waste with a decontamination factor greater than 40,000, (2) concentration of cesium in the aqueous strip effluent by a factor of 15 using dilute nitric acid, and (3) stripping the solvent sufficiently to allow it to be recycled many times. The results from the 71-h test are discussed.

Development and testing of a cobalt dicarbollide based solvent extraction process for the separation of cesium and strontium from acidic tank waste

2002 ◽  
Vol 37 (8) ◽  
pp. 1807-1831 ◽  
Author(s):  
R. S. Herbst ◽  
J. D. Law ◽  
T. A. Todd ◽  
V. N. Romanovskii ◽  
V. A. Babain ◽  
...  
Keyword(s):  
Solvent Extraction ◽  
Extraction Process ◽  
Tank Waste
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