Dialkylmethyl-2-(N,N-diisobutyl)acetamidoammonium iodide as a ruthenium selective ligand from nitric acid medium

Sharma, Shikha; Ghosh, Sunil K.; Sharma, J. N.

doi:10.1016/j.jhazmat.2015.04.003

Cited by 9 publications

(4 citation statements)

References 22 publications

(32 reference statements)

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“…For extraction studies with such extractants, isodecyl alcohol (IDA) is commonly used to enhance the solubility, as well as acting as a phase modifier to suppress the formation of a third phase. 24,25 Therefore, IDA was chosen as a co-solvent to enhance the solubility and 30% IDA in n-dodecane was found to be suitable for making a clear 0.1 M solution of the OTDA 1a and 1b. The time required to attain equilibrium for the extraction of Pu(IV) was determined for 0.1 M OTDA 1a in 30% IDA/n-dodecane at a 4 M feed HNO 3 concentration.…”

Section: Extraction Studies With Otdasmentioning

confidence: 99%

Synthesis and extraction studies with a rationally designed diamide ligand selective to actinide(iv) pertinent to the plutonium uranium redox extraction process

et al. 2016

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A new class of conformationally constrained oxa-bridged tricyclo-dicarboxamide (OTDA) ligand was rationally designed for the selective extraction of tetravalent actinides pertinent to the Plutonium Uranium Redox EXtraction (PUREX) process. Two of the designed diamide ligands were synthesized and extraction studies were performed for Pu(iv) from HNO3 medium. The mechanism of extraction was investigated by studying various parameters such as feed HNO3, NaNO3 and OTDA concentrations. The nature of the extracted species was found to be [Pu(NO3)4(OTDA)]. One of the OTDA ligands was elaborately tested and showed the selective extraction of Pu(iv) and Np(iv) over other actinide species, viz., U(vi), Np(v), Am(iii), lanthanides and fission products contained in a nuclear waste from the PUREX process. DFT calculations predicted the charge density on each of the coordinating 'O' atoms of OTDA supporting its high Pu(iv) selectivity over other ions studied and also provided the energy optimized structure of OTDA and its Pu(iv) complex.

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Section: Extraction Studies With Otdasmentioning

confidence: 99%

Synthesis and extraction studies with a rationally designed diamide ligand selective to actinide(iv) pertinent to the plutonium uranium redox extraction process

et al. 2016

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“…Many numbers of reports are available on the extraction and recovery of ruthenium from the acidic medium. Similarly, separation of ruthenium from a chloride medium has been well established by several researchers due to the propensity of formation of the anionic chloro complex in a chloride/HCl medium. , Various anion exchangers containing quaternary ammonium halide and trialkylamines as active functional groups were utilized to separate the anionic chloro complexes from the aqueous chloride medium. , Separation of ruthenium from aqueous nitric acid is more difficult, which makes the ruthenium separation very challenging at the nuclear back end cycle where the overall medium is 2–3 M HNO 3 . , Ruthenium tetroxide is found to be soluble in certain organic solvents such as CCl 4 . The removal of ruthenium in the form of ruthenium tetroxide from the PUREX process waste stream has been reported with paraffin oil.…”

Section: Introductionmentioning

confidence: 99%

“…The separation of ruthenium from an alkaline medium is equally important as it is present in substantial quantity (∼2 × 10 –2 –2 mCi/L depending on fuel cooling period) in intermediate level liquid waste. − There are many sources of this waste which are as follows: (i) metallic decladding operation of spent nuclear fuel at the reprocessing site, (ii) evaporation and neutralization of process condensate during the evaporation of acidic HLLW to concentrate, and (iii) purification of degraded TBP solvent through carbonate washing. The ruthenium separation from this alkaline waste is more difficult than acidic HLLW because of alkalinity and high salt content. − For this reason, very limited literature is available on the Ru separation from alkaline ILLW.…”

Section: Introductionmentioning

confidence: 99%

“…23 , 24 Separation of ruthenium from aqueous nitric acid is more difficult, which makes the ruthenium separation very challenging at the nuclear back end cycle where the overall medium is 2–3 M HNO 3 . 25 , 26 Ruthenium tetroxide is found to be soluble in certain organic solvents such as CCl 4 . 27 The removal of ruthenium in the form of ruthenium tetroxide from the PUREX process waste stream has been reported with paraffin oil.…”

Section: Introductionmentioning

confidence: 99%

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Separation of Radioactive Ruthenium from Alkaline Solution: A Solvent Extraction and Detailed Mechanistic Approach

et al. 2022

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A solvent extraction-based technique has been utilized to study the separation of ruthenium from simulated alkaline solution using Aliquat 336 as the extractant and isodecyl alcohol (IDA) as the phase modifier in n-dodecane. The effects of various experimental parameters such as solution pH, mixing time, concentration of Aliquat 336 and IDA, role of citric acid as the aqueous phase modifier/complexing agent, and stripping agents have been evaluated. It was observed that with the increase in the solution pH, the extraction efficiency increases gradually. However, when citric acid was added into the aqueous solution, an overall increase (from ∼20 to 91%) in ruthenium extraction is observed. 20 min of the mixing time was found to be sufficient to reach the extraction equilibrium. Solution composition was optimized as 50% Aliquat 336 and 10% IDA in n-dodecane (v/v) for maximum extraction. The stripping of ruthenium from the loaded organic phase has been studied using HCl and HNO3. The result indicates that in the presence of 8 M HNO3, ∼73% of ruthenium can be back extracted to the aqueous phase in a single contact. The stripping efficiency of HNO3 was found to be higher than that of HCl. Active studies with 106Ru as the radiotracer were also performed and monitored using a HPGe detector. The same method was implemented for extraction studies with real waste solution in the presence of other radionuclides such as 137Cs, 90Sr, and 125Sb. The presence of the chemical species in aqueous as well as organic phase has been identified using UV–vis spectrophotometry, Fourier transform infrared spectroscopy, and Raman spectroscopy. Density functional theory-based quantum mechanical calculations have been performed in order to unravel the extraction mechanism with the present solvent system.

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Recovery of Ru(III) from hydrochloric acid by cloud point extraction with 2-Mercaptobenzothiazole-functionalized ionic liquid

Zhang

Yang

Liu

et al. 2017

Chemical Engineering Journal

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Dialkylmethyl-2-(N,N-diisobutyl)acetamidoammonium iodide as a ruthenium selective ligand from nitric acid medium

Cited by 9 publications

References 22 publications

Synthesis and extraction studies with a rationally designed diamide ligand selective to actinide(iv) pertinent to the plutonium uranium redox extraction process

Synthesis and extraction studies with a rationally designed diamide ligand selective to actinide(iv) pertinent to the plutonium uranium redox extraction process

Separation of Radioactive Ruthenium from Alkaline Solution: A Solvent Extraction and Detailed Mechanistic Approach

Recovery of Ru(III) from hydrochloric acid by cloud point extraction with 2-Mercaptobenzothiazole-functionalized ionic liquid

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