scholarly journals High Level Waste Demonstration of the Caustic-Side Solvent Extraction Process with Optimized Solvent in the 2-CM Centrifugal Contactor Apparatus Using Tank 37H/44F Supernate

2003 ◽  
Author(s):  
M A Norato
Keyword(s):  
Solvent Extraction ◽  
Extraction Process ◽  
High Level Waste ◽  
Centrifugal Contactor ◽  
High Level

Demonstration Of The Caustic-side Solvent Extraction Process For The Removal Of137Cs From Savannah River Site High Level Waste

2003 ◽  
Vol 38 (12-13) ◽  
pp. 2647-2666 ◽  
Author(s):  
M. A. Norato ◽  
M. H. Beasley ◽  
S. G. Campbell ◽  
A. D. Coleman ◽  
M. W. Geeting ◽  
...  
Keyword(s):  
Solvent Extraction ◽  
Extraction Process ◽  
Savannah River Site ◽  
High Level Waste ◽  
Savannah River ◽  
High Level ◽  
River Site

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.

INTEC High-Level Waste Studies Universal Solvent Extraction Feasibility Study

2000 ◽  
Author(s):  
J. Banaee ◽  
C. M. Barnes ◽  
T. Battisti ◽  
S. Herrmann ◽  
S. J. Losinski ◽  
...  
Keyword(s):  
Solvent Extraction ◽  
Feasibility Study ◽  
High Level Waste ◽  
High Level ◽  
Waste Studies

Understanding the recovery of Ruthenium from acidic feeds by oxidative solvent extraction studies

2019 ◽  
Vol 107 (5) ◽  
pp. 423-429 ◽  
Author(s):  
Parveen Kumar Verma ◽  
Rajesh Bhikaji Gujar ◽  
Prasanta Kumar Mohapatra
Keyword(s):  
Solvent Extraction ◽  
Fission Product ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
High Level Waste ◽  
Trapping Mechanism ◽  
Nuclear Reprocessing ◽  
High Level ◽  
Trapping Agent ◽  
Simulated High Level Waste

Abstract Ruthenium (106Ru), a notorious fission product in nuclear reprocessing cycle, which gets partitioned at each step needs to be recovered. The recovery of Ru from acidic high level waste (HLW) is of great importance to the nuclear fuel cycle. Quantitative recovery of Ru was achieved from acidic feeds using oxidative trapping mechanism strategy where NaIO4 was used as an oxidant to convert different species of Ru in acidic phase to RuO4 while n-dodecane was used as trapping agent for RuO4. Stripping was attempted using NaOH and NaClO mixture. Attempt was made to optimize various parameters for 103Ru extraction and stripping. 103Ru tracer spiked simulated high level waste was used to understand the 103Ru behaviour in actual waste. The composition of stripping solution (alkaline hypochlorite) was also optimized to have >95% Ru into the aqueous phase in ca. 180 min.

Alternatives to Nitric Acid Stripping in the Caustic‐Side Solvent Extraction (CSSX) Process for Cesium Removal from Alkaline High‐Level Waste

2009 ◽  
Vol 27 (2) ◽  
pp. 172-198 ◽  
Author(s):  
Lætitia H. Delmau ◽  
Tamara J. Haverlock ◽  
Eve Bazelaire ◽  
Peter V. Bonnesen ◽  
Mary E. Ditto ◽  
...  
Keyword(s):  
Nitric Acid ◽  
Solvent Extraction ◽  
High Level Waste ◽  
Cesium Removal ◽  
High Level
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