Skills (1)
Education
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Jul 2005–
Mar 2007Cochin University of Science and Technology
Chemistry · M.ScIndia · Cochin
Other
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LanguagesEnglish, Malayalam, Tamil, Hindi
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Scientific MembershipsIANCAS, SACSE
Questions and Answers (5) View all
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Answer added in Molecular Dynamics23 Software used to prepare input files for MD simulations?You cannot rely on a single programme to produce the inputs. You can use chemsketch, chemdraw, avogadro, vmd, rasmol. It also depends up on what input... [more]
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Answer added in Mass Spectrometry32 Problem with Thermo Finnigan LCQ duo msit could be due to the problems in MS electronic board. You can check up whether it is working or not?
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Answer added in Simulation and Modeling29 Do all computational chemists have to learn Linux programming?It is not necessary to learn LINUX for computer programming. LINUX is flexible platform for doing simulation and secure. It occupies less memory as co... [more]
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Answer added in Cheminformatics and Computational Chemistry3 Any force field (AMBER or CHARM) is available for Uranium metal ionThank you
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Question asked in Cheminformatics and Computational Chemistry3 Any force field (AMBER or CHARM) is available for Uranium metal ionHi Can any body tell me any AMBER or CHARM force field is available for uranium metal ion
Publications (5) View all
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Article: Mutual separation of americium (III) and europium (III) using glycolamic acid and thioglycolamic acid
Radiochimica Acta. 01/2012; -
Article: Separation of Trivalent Actinides from High-Active Waste
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ABSTRACT: A typical high-active waste (HAW) arising from reprocessing of (U0.3Pu0.7)C fuel irradiated to the burn-up of 155 GWd/Te in a fast breeder test reactor (FBTR) was characterized. Partitioning of trivalent actinides from HAW was demonstrated using a solvent, 0.2 M n-octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) – 1.2 M tri-n-butylphosphate (TBP) in n-dodecane (n-DD), in a mixer settler. The results established quantitative separation of trivalents (Am(III) + Ln(III)) from HAW and recovery (> 99%) using a citric acid-nitric acid formulation. The mutual separation of lanthanides and actinides from the stripped product was studied by using bis(2-ethylhexyl)diglycolamic acid (HDEHDGA), synthesized in our laboratory.Procedia Chemistry. 01/2012; 7:130-138. -
Article: Extraction Behavior of Some Actinides and Fission Products from Nitric Acid Medium by a New Unsymmetrical Diglycolamide
Solvent Extraction and Ion Exchange. 01/2011; 29:86-105. -
Article: Development of a CMPO based extraction process for partitioning of minor actinides and demonstration with geneuine fast reactor fuel solution (155 GWd/Te)
Radiochim. Acta. 01/2011; 99:207-215. -
Article: Lanthanide–actinide separation by bis-2-ethylhexylphosphoric acid from citric acid–nitric acid medium
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ABSTRACT: Abstract High-level liquid waste from fast reactor fuel reprocessing stream contains significant quantities of lanthanides and trivalent minor actinides. The lanthanides and minor actinides (MA) have been separated from the fast reactor high-level liquid waste (FR-HLLW) using TRUEX solvent, which is a mixture of 0.2 M octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO)-1.2 M tri-n-butylphosphate (TBP) in n-dodecane. A new stripping composition, 0.1 M HNO3 and 0.1 M citric acid (CA), has been employed for back extraction of them from the TRUEX solvent. In order to separate lanthanides from actinides present in the strip solution, the extraction behavior of 241Am(III) and (152+154)Eu(III) from CA–HNO3 medium by a solution of bis-2-ethylhexylphosphoric acid (HDEHP) in n-dodecane has been studied. Separation factors (SF = D Eu/D Am) has been reported as a function of various parameters such as pH, concentrations of HDEHP, diethylenetriamine-N,N,N′,N′′,N′′′-pentaaceticacid (DTPA), 1-octanol and TBP in this paper.Journal of Radioanalytical and Nuclear Chemistry. 01/2010; 285:653-658.
