scholarly journals Caustic-Side Solvent Extraction Batch Distribution Measurements for SRS High Level Waste Samples and Dissolved Saltcake

2003 ◽  
Author(s):  
W R Wilmarth
Keyword(s):  
Solvent Extraction ◽  
High Level Waste ◽  
High Level

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

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

Separation of neptunium from actinides by monoamides: a solvent extraction study

2019 ◽  
Vol 107 (5) ◽  
pp. 369-376 ◽  
Author(s):  
Bholanath Mahanty ◽  
Avinash S. Kanekar ◽  
Seraj A. Ansari ◽  
Arunasis Bhattacharyya ◽  
Prasanta K. Mohapatra
Keyword(s):  
Solvent Extraction ◽  
Alpha Spectrometry ◽  
Selective Extraction ◽  
High Level Waste ◽  
Acetohydroxamic Acid ◽  
Mixed Solution ◽  
Separation Scheme ◽  
Extraction Study ◽  
Mutual Separation ◽  
High Level

Abstract Separation of neptunium from a mixture of actinides viz. uranium, neptunium and plutonium was evaluated using two monoamides, viz. N,N,-dihexyl octanamide (DHOA) and N,N,-dihexyl decanamide (DHDA). The extraction of actinides with these ligands followed the order: U(VI)>Np(IV)>>Pu(III). Poor extraction of Pu(III) with both the amides (DHOA and DHDA) was exploited for the mutual separation of U, Pu and Np. At 3 M HNO3, DHDA was a better extractant for all the three metal ions while Pu(III) extraction was one order magnitude lower with DHOA as compared to that seen with DHDA. Consequently, better separation factor of U(VI)/Np(IV) over Pu(III) was obtained with DHOA. In the actinide mixed solution, Pu was reduced to its +3 state followed by selective extraction of U(VI) and Np(IV). Subsequently, the mutual separation of U(VI) and Np(IV) was carried out by selective complexation and stripping of Np(IV) by acetohydroxamic acid (AHA) at 2 M HNO3, where U(VI) remained in the organic phase. The purity of the separated actinides was confirmed by alpha spectrometry. A separation scheme for the separation of Np from radioactive waste/high level waste has been proposed.

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