P.M. GANDHI - Academia.edu (original) (raw)
Papers by P.M. GANDHI
Journal of Membrane Science, 2015
Journal of Radioanalytical and Nuclear Chemistry, 2014
ABSTRACT Radiolytic stability of solvent systems containing four commercially available calix-cro... more ABSTRACT Radiolytic stability of solvent systems containing four commercially available calix-crown-6 ligands termed as calix[4]arene-bis-crown-6 (CC), calix[4]arene-benzo-bis-crown-6 (CBC), calix[4]arene-naphtho-bis-crown-6 (CNC), and bis-(octyloxy)calix[4]arene-mono-crown-6 (CMC) dissolved in phenyl trifluoromethyl sulphone (PTMS) was studied which followed the order: CBC > CC > CNC ~ CMC. The radiolytic stability was evaluated by the absolute distribution ratio (D Cs) vales at a given concentration of nitric acid as well as the nature of the extracted species. The radiolytic degradation products were identified by GC–MS analysis. The present study indicates that CBC in PTMS can be used as a solvent for radio-cesium recovery with good recycling possibilities.
![Research paper thumbnail of Effect of room temperature ionic liquid on the extraction behavior of Plutonium (IV) using a novel reagent, bis-(2-ethylhexyl) carbamoyl methoxy phenoxy-bis-(2-ethylhexyl) acetamide [Benzodioxodiamide, BenzoDODA]](https://attachments.academia-assets.com/114355127/thumbnails/1.jpg)
](Separation and Purification Technology, 2015
Separation Science and Technology, 2013
ract, 2013
The extractant-impregnated polymeric beads (EIPBs), containing polyethersulfone as base polymer a... more The extractant-impregnated polymeric beads (EIPBs), containing polyethersulfone as base polymer and 2-ethylhexyl phosphonic acid mono-2-ethylhexyl ester (PC-88A) as an extractant, were prepared by phase inversion method. These EIPBs were characterized by FTIR, TGA and SEM techniques. The beads were found to have excellent acid stability, since these did not exhibit any structural deformation or loss of the extractant into aqueous nitric acid solution (6 M), for a period of 15 d. The feasibility of Pu(IV) extraction, using these beads, from nitric acid solution was tested by batch equilibration method. Parametric dependence of Pu(IV) extraction on experimental variables, like strength of nitric acid, equilibration time, Pu(IV) concentration, etc., was investigated. The present study also addressed the important practical issues, like maximum loading capacity and the reusability of these beads. Under optimized conditions, equilibrium capacity and maximum loading capacity for Pu(IV) we...
Journal of Chemical & Engineering Data, 2014
Research Journal of Pharmacy and Technology, 2020
LIGHTWEIGHT AGGREGATE CURRENTLY PRODUCED IN PUERTO RICO WAS EVALUATED FOR USE IN HIGHWAY AND BUIL... more LIGHTWEIGHT AGGREGATE CURRENTLY PRODUCED IN PUERTO RICO WAS EVALUATED FOR USE IN HIGHWAY AND BUILDING CONSTRUCTION. EXPANDED CLAY AND SHALE LIGHTWEIGHT AGGREGATE WERE FOUND SUITABLE FOR SURFACE TREATMENTS, FOR HOT MIX SURFACE COURSES IN ASPHALT PAVEMENTS AND ALSO IN CEMENT CONCRETE FOR BUILDINGS. AS NATURAL SANDS ARE BECOMING SCARCE ON THE ISLAND, THE LIGHTWEIGHT AGGREGATE FINES MAY BE USED AS FINE AGGREGATE TO REPLACE SAND IN CEMENT CONCRETE MIXES. IN FUTURE PHASES OF STUDY SUITABLE SOURCES OF RAW MATERIALS ON THE ISLAND FOR THE PRODUCTION OF LIGHTWEIGHT AGGREGATES WILL BE SOUGHT, AND TESTING PROCEDURES AND STANDARDS FOR PROPER QUALITY CONTROL OF LIGHTWEIGHT PRODUCTS WILL BE DEVELOPED.
Process Biochemistry, 1993
This work describes an improved downstream processing protocolfor the simultaneous separation and... more This work describes an improved downstream processing protocolfor the simultaneous separation and purif?cation of two diagnostic enzymes, lactate dehydrogenase (LDH) and pyruvate kinase (PK), from rabbit muscles. The purification scheme was specificaiiy designed so that both purtfied enzymes were comparable, in terms of specific activity and impurity content, to commercial high-purity analytical grade. The proposed protocol comprises two dye-columns (dye-sorbents), Cibacron blue 3GA and Procion yellow MX-4G both immobilised on CL-Sepharose 6B, which were integrated in the following six-step scheme: (i) muscle extract preparation, (ii) O-45% ammonium sulphate fractionation, (iii) blue-column chromatography where the two enzymes were separated and LDH was purified, (iv) blue-column chromatography, (v) thermal treatment, and (vi) yellow-column chromatography where PK was purtfied. This protocol affora!s LDH of specific activity 470 unitsfmg (no detectable PK) at 65% overall yield, and PK of specific activity 251 unitsfmg (no detectable LDH and enolase) at 40% overu I1 yield.
The present paper describes the results of solvent extraction studies carried out in batch as wel... more The present paper describes the results of solvent extraction studies carried out in batch as well as counter current mode employing 5% TBP in n-dodecane as an extractant to develop a flow-sheet for the recovery of uranium and plutonium from dissolved AHWR spent fuel. Simulated feed solutions containing thorium, uranium and plutonium in concentration levels expected in dissolver feed solutions of AHWR spent fuel was used to collect necessary extraction and stripping data in batch mode. Subsequently, the experiments were carried out in counter current mode using laboratory scale mixer-settlers. Based on those data a process flow-sheet was proposed and validated using simulated feed solution of reference burn up. Quantitative extraction of uranium and plutonium was achieved under experimental conditions leaving bulk of thorium in the raffinate. Small co-extracted thorium from the organic phase was scrubbed using 3M HNO3. Separation of plutonium from uranium was achieved by chemical re...
Decontamination of alpha contaminated metallic waste is an important aspect in the management of ... more Decontamination of alpha contaminated metallic waste is an important aspect in the management of waste generated during dismantling and decommissioning of nuclear facilities. Present work on cerium redox process targets decontamination of alpha contaminated metallic waste till it qualifies for the non alpha waste category for disposal in near surface disposal facility. Recovery of the alpha radio nuclides and cerium from aqueous secondary waste streams was also studied deploying solvent extraction process and established. The alpha-lean secondary waste stream has been immobilised in cement based matrix for final disposal.
Mineralogical Magazine, 2016
Stalagmites and stalactites, as observed within natural caves, may develop inside geological repo... more Stalagmites and stalactites, as observed within natural caves, may develop inside geological repositories during constructional and post-operational periods. It is therefore important to understand actinide sorption within such materials. Towards this, experimental studies were carried out with233U,238Np (VI),238Np (IV),239Pu and241Am radiotracers using natural speleothem samples collected from the Dharamjali cave of the Kumaon Lesser Himalayas, India. Petrological/mineralogical studies showed that natural speleothems have three general domains: (1) columnar calcite; (2) microcrystalline calcite; and (3) botryoidal aragonite – each with ferruginous materials. Results showed that all domains of speleothems can take up >99% actinides, irrespective of valence state and pH (1–6 range) of the solution. However, distribution coefficients were found to be at a maximum in aragonite for most of the actinides. Such data are very important for long-term performance and safety assessments of...
Separation Science and Technology, 2017
Solvent extraction studies on protactinum was carried out from hydrofluoric acid, hydrochloric ac... more Solvent extraction studies on protactinum was carried out from hydrofluoric acid, hydrochloric acid, and mixture of hydrchloric and hydrofluoric acid using Aliquat 336 and 231 Pa. The extraction of protactinium from hydrofluoric acid (0.025-10 M) decreased with increasing acid concentration and was less than 10% above 5 M. The extraction from hydrochloric acid (0.5 M-8 M) started only above 4 M and increased with increasing acid concentration. The extraction of protactinium from a mixture containing hydrochloric acid (0.5-8 M) and 0.03 M hydrofluoric acid decreased with increasing acid concentration reached to a minimum at about 2 M and then increased with increasing acid concentration. At low acidy, extraction of protactinium from hydrofluoric acid was higher compared to hydrochloric acid and mixture of hydrochloric and hydrofluoric acids. Nitric acid (10 M) and hydrofluoric acid (10 M) were suitable for quantitative recovery of protactinium from organic phase. The extraction of 231 Pa from real thorium lean raffinate of thorium-uranium extraction process was studied using optimized extraction conditions.
Separation Science and Technology, 2015
The extraction of Pu(IV) from nitric acid medium using TBP has been compared with two diluents us... more The extraction of Pu(IV) from nitric acid medium using TBP has been compared with two diluents using n-dodecane and a RTIL, 1-butyl-3-methylimidazolium bis(trifluoromethanesulphonyl)imide (C4mimTf2N). Kinetics of extraction was slower in RTIL compared to n-dodecane. The mechanism of extraction was found to be cation exchange at lower acidity which changes to the formation of a neutral complex at higher acidity greater than 1M HNO3 for RTIL. Back extraction of Pu from the loaded organic phase was equally effected using 0.1M oxalic acid and a mixture of guanidine carbonate and EDTA as strippant from both the extraction systems under study. Radiation stability and reusability studies showed promise for future application.
Journal of Radioanalytical and Nuclear Chemistry, 2017
High energy 60 Co c-radiation was used to graft glycidylmethacrylate onto Teflon scrap through mu... more High energy 60 Co c-radiation was used to graft glycidylmethacrylate onto Teflon scrap through mutual radiation grafting technique. The epoxy ring of grafted polyGMA chains were later converted to U selective phosphoryl group, chemically. The grafted matrix was used as solid-liquid adsorbent of uranium from alkaline waste solution. More than 98% recovery of uranium from alkaline waste (*pH 8) solution was achieved. The effect of grafting extent on adsorption kinetics was also investigated. The selectivity of uranium extraction over other fission products was established. The uptake of other fission products was \5% for equilibration time of *1 h.
Journal of Radioanalytical and Nuclear Chemistry, 2017
Understanding the mobility of radiocesium and radiostrontium within geological environment is imp... more Understanding the mobility of radiocesium and radiostrontium within geological environment is important from 'deep geological repository system'-safety assessment point of view. Cs and Sr radionuclide sorption studies have been carried out with a stalagmite sample collected from Lesser-Himalayas. Detailed microstructural studies, backed up by micro-Raman and LIBS analyses, identified three different domains within the sample; constituted of microcrystalline calcite, botryoidal aragonite and palisadic calcite respectively. Experimental studies showed that both the radionuclides exhibit moderate to low sorption coefficients within all the different domains of stalagmite under acidic environment.
Journal of Environmental Chemical Engineering, 2017
Abstract This paper gives two methods, viz. a solvent extraction method and a hollow fiber contac... more Abstract This paper gives two methods, viz. a solvent extraction method and a hollow fiber contactor based liquid membrane method, for the separation of radio-cesium from actual high level liquid waste (HLLW) solutions using calix[4]arene-crown-6 based solvent systems. While the solvent extraction method involved calix[4]arene-bis-benzo-crwon-6 (CBC) in PTMS (phenyltrifluoromethyl sulphone), the hollow fiber supported liquid membrane method used a polysulphone fiber containing contactor and bis-octyl-benzo-calix[4]arene-mono-crown-6 (CMC) in 40% iso -decanol + 60% n -dodecane. Both methods reported selective radio-cesium separation with almost no contamination from the associated fission product radionuclides. The radiolytic stability of the hollow fiber contactor was checked by keeping the contactor module in contact with the diluted HLLW for 50 days. The second run carried out after 50 days resulted in excellent reproducibility suggesting efficacy of this method for radioactive waste remediation.
RSC Advances, 2016
Retraction of ‘Selective Uptake of Uranium, Plutonium and Americium on Hydrogen Titanate Nanotube... more Retraction of ‘Selective Uptake of Uranium, Plutonium and Americium on Hydrogen Titanate Nanotubes’ by Chayan Banerjee et al., RSC Adv., 2014, DOI: 10.1039/c3ra42548g.
Journal of Hazardous Materials, 2016
A new ligand grafted polymeric resin (BenzoDODA SDVB) was synthesized by covalently attaching plu... more A new ligand grafted polymeric resin (BenzoDODA SDVB) was synthesized by covalently attaching plutonium selective ligand (BenzoDODA) on to styrene divinyl benzene (SDVB) polymer matrix. BenzoDODA SDVB resin was evaluated for separation and recovery of plutonium(IV) from nitric acid medium. Sorption of Pu(IV) was found to decrease with the increase in nitric acid concentration, with very small sorption above 7.0M HNO3. Sorption kinetics was fast enough to achieve the equilibrium within 60min of contact where the kinetic data fitted well to pseudo-second-order model. Sorption isotherm data fitted well to Langmuir model suggesting chemical interaction between the BenzoDODA moiety and plutonium(IV) ions. Sorption studies with some of representative radionuclides of high level waste showed that BenzoDODA SDVB is selective and therefore could be a promising solid sorbent for separation and recovery of plutonium. Further, the theoretical calculations done on BenzoDODA SDVB resin suggested Pu(NO3)4·BenzoDODA (1:1) sorbed complex conformed to generally observed square antiprism geometry of the plutonium complexes, with contributions from oxygen atoms of four nitrate ions as well as from four oxygen atoms present in BenzoDODA (two phenolic ether oxygen atoms and two carbonyl oxygen atoms of amidic moiety).
Journal of Membrane Science, 2015
Journal of Radioanalytical and Nuclear Chemistry, 2014
ABSTRACT Radiolytic stability of solvent systems containing four commercially available calix-cro... more ABSTRACT Radiolytic stability of solvent systems containing four commercially available calix-crown-6 ligands termed as calix[4]arene-bis-crown-6 (CC), calix[4]arene-benzo-bis-crown-6 (CBC), calix[4]arene-naphtho-bis-crown-6 (CNC), and bis-(octyloxy)calix[4]arene-mono-crown-6 (CMC) dissolved in phenyl trifluoromethyl sulphone (PTMS) was studied which followed the order: CBC > CC > CNC ~ CMC. The radiolytic stability was evaluated by the absolute distribution ratio (D Cs) vales at a given concentration of nitric acid as well as the nature of the extracted species. The radiolytic degradation products were identified by GC–MS analysis. The present study indicates that CBC in PTMS can be used as a solvent for radio-cesium recovery with good recycling possibilities.
Separation and Purification Technology, 2015
Separation Science and Technology, 2013
ract, 2013
The extractant-impregnated polymeric beads (EIPBs), containing polyethersulfone as base polymer a... more The extractant-impregnated polymeric beads (EIPBs), containing polyethersulfone as base polymer and 2-ethylhexyl phosphonic acid mono-2-ethylhexyl ester (PC-88A) as an extractant, were prepared by phase inversion method. These EIPBs were characterized by FTIR, TGA and SEM techniques. The beads were found to have excellent acid stability, since these did not exhibit any structural deformation or loss of the extractant into aqueous nitric acid solution (6 M), for a period of 15 d. The feasibility of Pu(IV) extraction, using these beads, from nitric acid solution was tested by batch equilibration method. Parametric dependence of Pu(IV) extraction on experimental variables, like strength of nitric acid, equilibration time, Pu(IV) concentration, etc., was investigated. The present study also addressed the important practical issues, like maximum loading capacity and the reusability of these beads. Under optimized conditions, equilibrium capacity and maximum loading capacity for Pu(IV) we...
Journal of Chemical & Engineering Data, 2014
Research Journal of Pharmacy and Technology, 2020
LIGHTWEIGHT AGGREGATE CURRENTLY PRODUCED IN PUERTO RICO WAS EVALUATED FOR USE IN HIGHWAY AND BUIL... more LIGHTWEIGHT AGGREGATE CURRENTLY PRODUCED IN PUERTO RICO WAS EVALUATED FOR USE IN HIGHWAY AND BUILDING CONSTRUCTION. EXPANDED CLAY AND SHALE LIGHTWEIGHT AGGREGATE WERE FOUND SUITABLE FOR SURFACE TREATMENTS, FOR HOT MIX SURFACE COURSES IN ASPHALT PAVEMENTS AND ALSO IN CEMENT CONCRETE FOR BUILDINGS. AS NATURAL SANDS ARE BECOMING SCARCE ON THE ISLAND, THE LIGHTWEIGHT AGGREGATE FINES MAY BE USED AS FINE AGGREGATE TO REPLACE SAND IN CEMENT CONCRETE MIXES. IN FUTURE PHASES OF STUDY SUITABLE SOURCES OF RAW MATERIALS ON THE ISLAND FOR THE PRODUCTION OF LIGHTWEIGHT AGGREGATES WILL BE SOUGHT, AND TESTING PROCEDURES AND STANDARDS FOR PROPER QUALITY CONTROL OF LIGHTWEIGHT PRODUCTS WILL BE DEVELOPED.
Process Biochemistry, 1993
This work describes an improved downstream processing protocolfor the simultaneous separation and... more This work describes an improved downstream processing protocolfor the simultaneous separation and purif?cation of two diagnostic enzymes, lactate dehydrogenase (LDH) and pyruvate kinase (PK), from rabbit muscles. The purification scheme was specificaiiy designed so that both purtfied enzymes were comparable, in terms of specific activity and impurity content, to commercial high-purity analytical grade. The proposed protocol comprises two dye-columns (dye-sorbents), Cibacron blue 3GA and Procion yellow MX-4G both immobilised on CL-Sepharose 6B, which were integrated in the following six-step scheme: (i) muscle extract preparation, (ii) O-45% ammonium sulphate fractionation, (iii) blue-column chromatography where the two enzymes were separated and LDH was purified, (iv) blue-column chromatography, (v) thermal treatment, and (vi) yellow-column chromatography where PK was purtfied. This protocol affora!s LDH of specific activity 470 unitsfmg (no detectable PK) at 65% overall yield, and PK of specific activity 251 unitsfmg (no detectable LDH and enolase) at 40% overu I1 yield.
The present paper describes the results of solvent extraction studies carried out in batch as wel... more The present paper describes the results of solvent extraction studies carried out in batch as well as counter current mode employing 5% TBP in n-dodecane as an extractant to develop a flow-sheet for the recovery of uranium and plutonium from dissolved AHWR spent fuel. Simulated feed solutions containing thorium, uranium and plutonium in concentration levels expected in dissolver feed solutions of AHWR spent fuel was used to collect necessary extraction and stripping data in batch mode. Subsequently, the experiments were carried out in counter current mode using laboratory scale mixer-settlers. Based on those data a process flow-sheet was proposed and validated using simulated feed solution of reference burn up. Quantitative extraction of uranium and plutonium was achieved under experimental conditions leaving bulk of thorium in the raffinate. Small co-extracted thorium from the organic phase was scrubbed using 3M HNO3. Separation of plutonium from uranium was achieved by chemical re...
Decontamination of alpha contaminated metallic waste is an important aspect in the management of ... more Decontamination of alpha contaminated metallic waste is an important aspect in the management of waste generated during dismantling and decommissioning of nuclear facilities. Present work on cerium redox process targets decontamination of alpha contaminated metallic waste till it qualifies for the non alpha waste category for disposal in near surface disposal facility. Recovery of the alpha radio nuclides and cerium from aqueous secondary waste streams was also studied deploying solvent extraction process and established. The alpha-lean secondary waste stream has been immobilised in cement based matrix for final disposal.
Mineralogical Magazine, 2016
Stalagmites and stalactites, as observed within natural caves, may develop inside geological repo... more Stalagmites and stalactites, as observed within natural caves, may develop inside geological repositories during constructional and post-operational periods. It is therefore important to understand actinide sorption within such materials. Towards this, experimental studies were carried out with233U,238Np (VI),238Np (IV),239Pu and241Am radiotracers using natural speleothem samples collected from the Dharamjali cave of the Kumaon Lesser Himalayas, India. Petrological/mineralogical studies showed that natural speleothems have three general domains: (1) columnar calcite; (2) microcrystalline calcite; and (3) botryoidal aragonite – each with ferruginous materials. Results showed that all domains of speleothems can take up >99% actinides, irrespective of valence state and pH (1–6 range) of the solution. However, distribution coefficients were found to be at a maximum in aragonite for most of the actinides. Such data are very important for long-term performance and safety assessments of...
Separation Science and Technology, 2017
Solvent extraction studies on protactinum was carried out from hydrofluoric acid, hydrochloric ac... more Solvent extraction studies on protactinum was carried out from hydrofluoric acid, hydrochloric acid, and mixture of hydrchloric and hydrofluoric acid using Aliquat 336 and 231 Pa. The extraction of protactinium from hydrofluoric acid (0.025-10 M) decreased with increasing acid concentration and was less than 10% above 5 M. The extraction from hydrochloric acid (0.5 M-8 M) started only above 4 M and increased with increasing acid concentration. The extraction of protactinium from a mixture containing hydrochloric acid (0.5-8 M) and 0.03 M hydrofluoric acid decreased with increasing acid concentration reached to a minimum at about 2 M and then increased with increasing acid concentration. At low acidy, extraction of protactinium from hydrofluoric acid was higher compared to hydrochloric acid and mixture of hydrochloric and hydrofluoric acids. Nitric acid (10 M) and hydrofluoric acid (10 M) were suitable for quantitative recovery of protactinium from organic phase. The extraction of 231 Pa from real thorium lean raffinate of thorium-uranium extraction process was studied using optimized extraction conditions.
Separation Science and Technology, 2015
The extraction of Pu(IV) from nitric acid medium using TBP has been compared with two diluents us... more The extraction of Pu(IV) from nitric acid medium using TBP has been compared with two diluents using n-dodecane and a RTIL, 1-butyl-3-methylimidazolium bis(trifluoromethanesulphonyl)imide (C4mimTf2N). Kinetics of extraction was slower in RTIL compared to n-dodecane. The mechanism of extraction was found to be cation exchange at lower acidity which changes to the formation of a neutral complex at higher acidity greater than 1M HNO3 for RTIL. Back extraction of Pu from the loaded organic phase was equally effected using 0.1M oxalic acid and a mixture of guanidine carbonate and EDTA as strippant from both the extraction systems under study. Radiation stability and reusability studies showed promise for future application.
Journal of Radioanalytical and Nuclear Chemistry, 2017
High energy 60 Co c-radiation was used to graft glycidylmethacrylate onto Teflon scrap through mu... more High energy 60 Co c-radiation was used to graft glycidylmethacrylate onto Teflon scrap through mutual radiation grafting technique. The epoxy ring of grafted polyGMA chains were later converted to U selective phosphoryl group, chemically. The grafted matrix was used as solid-liquid adsorbent of uranium from alkaline waste solution. More than 98% recovery of uranium from alkaline waste (*pH 8) solution was achieved. The effect of grafting extent on adsorption kinetics was also investigated. The selectivity of uranium extraction over other fission products was established. The uptake of other fission products was \5% for equilibration time of *1 h.
Journal of Radioanalytical and Nuclear Chemistry, 2017
Understanding the mobility of radiocesium and radiostrontium within geological environment is imp... more Understanding the mobility of radiocesium and radiostrontium within geological environment is important from 'deep geological repository system'-safety assessment point of view. Cs and Sr radionuclide sorption studies have been carried out with a stalagmite sample collected from Lesser-Himalayas. Detailed microstructural studies, backed up by micro-Raman and LIBS analyses, identified three different domains within the sample; constituted of microcrystalline calcite, botryoidal aragonite and palisadic calcite respectively. Experimental studies showed that both the radionuclides exhibit moderate to low sorption coefficients within all the different domains of stalagmite under acidic environment.
Journal of Environmental Chemical Engineering, 2017
Abstract This paper gives two methods, viz. a solvent extraction method and a hollow fiber contac... more Abstract This paper gives two methods, viz. a solvent extraction method and a hollow fiber contactor based liquid membrane method, for the separation of radio-cesium from actual high level liquid waste (HLLW) solutions using calix[4]arene-crown-6 based solvent systems. While the solvent extraction method involved calix[4]arene-bis-benzo-crwon-6 (CBC) in PTMS (phenyltrifluoromethyl sulphone), the hollow fiber supported liquid membrane method used a polysulphone fiber containing contactor and bis-octyl-benzo-calix[4]arene-mono-crown-6 (CMC) in 40% iso -decanol + 60% n -dodecane. Both methods reported selective radio-cesium separation with almost no contamination from the associated fission product radionuclides. The radiolytic stability of the hollow fiber contactor was checked by keeping the contactor module in contact with the diluted HLLW for 50 days. The second run carried out after 50 days resulted in excellent reproducibility suggesting efficacy of this method for radioactive waste remediation.
RSC Advances, 2016
Retraction of ‘Selective Uptake of Uranium, Plutonium and Americium on Hydrogen Titanate Nanotube... more Retraction of ‘Selective Uptake of Uranium, Plutonium and Americium on Hydrogen Titanate Nanotubes’ by Chayan Banerjee et al., RSC Adv., 2014, DOI: 10.1039/c3ra42548g.
Journal of Hazardous Materials, 2016
A new ligand grafted polymeric resin (BenzoDODA SDVB) was synthesized by covalently attaching plu... more A new ligand grafted polymeric resin (BenzoDODA SDVB) was synthesized by covalently attaching plutonium selective ligand (BenzoDODA) on to styrene divinyl benzene (SDVB) polymer matrix. BenzoDODA SDVB resin was evaluated for separation and recovery of plutonium(IV) from nitric acid medium. Sorption of Pu(IV) was found to decrease with the increase in nitric acid concentration, with very small sorption above 7.0M HNO3. Sorption kinetics was fast enough to achieve the equilibrium within 60min of contact where the kinetic data fitted well to pseudo-second-order model. Sorption isotherm data fitted well to Langmuir model suggesting chemical interaction between the BenzoDODA moiety and plutonium(IV) ions. Sorption studies with some of representative radionuclides of high level waste showed that BenzoDODA SDVB is selective and therefore could be a promising solid sorbent for separation and recovery of plutonium. Further, the theoretical calculations done on BenzoDODA SDVB resin suggested Pu(NO3)4·BenzoDODA (1:1) sorbed complex conformed to generally observed square antiprism geometry of the plutonium complexes, with contributions from oxygen atoms of four nitrate ions as well as from four oxygen atoms present in BenzoDODA (two phenolic ether oxygen atoms and two carbonyl oxygen atoms of amidic moiety).