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Assessing the feasibility study of highly efficient and selective co-sequestration process for cesium and strontium utilizing calix-crown and crown-ether based combined solvent systems

Journal of radioanalytical and nuclear chemistry, 2022-03, Vol.331 (3), p.1473-1481

2022

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Simultaneous quantification of low Z elements in phosphorus containing alkali borosilicate glass samples by in situ Current normalized external (in air) PIGE method utilizing proton beam from FOTIA

Journal of radioanalytical and nuclear chemistry, 2021-05, Vol.328 (2), p.519-526

2021

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Removal of radioactive caesium from low level radioactive waste (LLW) streams using cobalt ferrocyanide impregnated organic anion exchanger

Journal of hazardous materials, 2009-07, Vol.166 (2), p.1148-1153

2009

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Separation of strontium from low level radioactive waste solutions using hydrous manganese dioxide composite materials

Journal of nuclear materials, 2010-09, Vol.404 (2), p.138-143

2010

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Treatment of low level radioactive liquid waste containing appreciable concentration of TBP degraded products

Journal of hazardous materials, 2011-11, Vol.196, p.22-28

2011

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Synthesis and characterization of cobalt ferrocyanides loaded on organic anion exchanger

Journal of nuclear materials, 2009-02, Vol.384 (2), p.146-152

2009

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Comparative uptake studies on trivalent f-cations from acidic feeds using two extraction chromatography resins containing a diglycolamide in molecular diluent and ionic liquid

Journal of Chromatography A, 2021-03, Vol.1641, p.461999, Article 461999

2021

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Correction: Mechanism unravelling for highly efficient and selective 99 TcO 4 - sequestration utilising crown ether based solvent system from nuclear liquid waste: experimental and computational investigations

RSC advances, 2022-02, Vol.12 (10), p.5978-5978

2022

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Mechanism unravelling for highly efficient and selective 99 TcO 4 - sequestration utilising crown ether based solvent system from nuclear liquid waste: experimental and computational investigations

RSC advances, 2022-01, Vol.12 (6), p.3216-3226

2022

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A comparative study on the structural aspects of sodium borosilicate glasses and barium borosilicate glasses: Effect of Al2O3 addition

Journal of non-crystalline solids, 2016-09, Vol.447, p.283-289

2016

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Study of plutonium recovery from acidic feed using polyethersulfone encapsulating TBP, DEHPA, and mixture of TBP and DEHPA beads

Separation science and technology, 2023-11, Vol.58 (15-16), p.2846-2855

2023

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Correction to: Removal of 99Tc from low level radioactive liquid waste using di‑tert‑butyldibenzo‑18‑crown‑6 impregnated sorbent

Journal of radioanalytical and nuclear chemistry, 2021, Vol.330 (3), p.1623-1623

2021

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Removal of 99Tc from low level radioactive liquid waste using di-tert-butyldibenzo-18-crown-6 impregnated sorbent

Journal of radioanalytical and nuclear chemistry, 2021, Vol.328 (1), p.113-119

2021

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Evaluation of cerium–zirconium mixed oxides for separation of 125Sb from radioactive liquid waste

Journal of radioanalytical and nuclear chemistry, 2022, Vol.331 (7), p.2903-2909

2022

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Separation of 99Tc from low level radioactive liquid waste using hollow fiber supported liquid membrane: optimisation and performance evaluation

Journal of radioanalytical and nuclear chemistry, 2021, Vol.330 (3), p.811-820

2021

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Correction: Mechanism unravelling for highly efficient and selective 99TcO4− sequestration utilising crown ether based solvent system from nuclear liquid waste: experimental and computational investigations

RSC advances, 2022-02, Vol.12 (10), p.5978-5978

2022

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Mechanism unravelling for highly efficient and selective 99TcO4− sequestration utilising crown ether based solvent system from nuclear liquid waste: experimental and computational investigations

RSC advances, 2022-01, Vol.12 (6), p.3216-3226

2022

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Removal of ruthenium from high-level radioactive liquid waste generated during reprocessing of spent fuel

Desalination and water treatment, 2014, Vol.52 (1-3), p.514-525

2014

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Preparation and characterisation of glass product with modified composition for vitrification of high level radioactive waste

Journal of thermal analysis and calorimetry, 2013-04, Vol.112 (1), p.103-108

2013

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Studies on modified borosilicate glass for enhancement of solubility of molybdenum

Journal of non-crystalline solids, 2019-04, Vol.510, p.172-178

2019

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Evaluation of Metal Antimonate Compounds for the Removal of Radiostrontium from Radioactive Liquid Waste: Characterization and Sorption Behavior

Separation science and technology, 2011-07, Vol.46 (11), p.1776-1787

2011

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Evaluation of Nickel Sulphide Prepared by Different Routes for Removal of 106Ru from Alkaline Radioactive Liquid Waste

Separation science and technology, 2010-09, Vol.45 (14), p.2064-2075

2010

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Sequestration of Actinides by an Extraction Chromatography Resin Containing a Triaza-9-crown‑3 Functionalized Diglycolamide

Industrial & engineering chemistry research, 2023-09, Vol.62 (35), p.13966-13973

2023

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Radioactive waste processing using membranes: State of the art technology, challenges and perspectives

Separation and purification reviews, 2022-04, Vol.51 (2), p.143-173

2022

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Emerging functionalized magnetic nanoparticles: from synthesis to nuclear fuel cycle application: where do we stand after two decade?

Materials Today Sustainability, 2023-12, Vol.24, p.100489, Article 100489

2023

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Assessing the feasibility study of highly efficient and selective co-sequestration process for cesium and strontium utilizing calix-crown and crown-ether based combined solvent systems

Simultaneous quantification of low Z elements in phosphorus containing alkali borosilicate glass samples by in situ Current normalized external (in air) PIGE method utilizing proton beam from FOTIA

Removal of radioactive caesium from low level radioactive waste (LLW) streams using cobalt ferrocyanide impregnated organic anion exchanger

Separation of strontium from low level radioactive waste solutions using hydrous manganese dioxide composite materials

Treatment of low level radioactive liquid waste containing appreciable concentration of TBP degraded products

Synthesis and characterization of cobalt ferrocyanides loaded on organic anion exchanger

Comparative uptake studies on trivalent f-cations from acidic feeds using two extraction chromatography resins containing a diglycolamide in molecular diluent and ionic liquid

Correction: Mechanism unravelling for highly efficient and selective 99 TcO 4 - sequestration utilising crown ether based solvent system from nuclear liquid waste: experimental and computational investigations

Mechanism unravelling for highly efficient and selective 99 TcO 4 - sequestration utilising crown ether based solvent system from nuclear liquid waste: experimental and computational investigations

A comparative study on the structural aspects of sodium borosilicate glasses and barium borosilicate glasses: Effect of Al2O3 addition

Study of plutonium recovery from acidic feed using polyethersulfone encapsulating TBP, DEHPA, and mixture of TBP and DEHPA beads

Correction to: Removal of 99Tc from low level radioactive liquid waste using di‑tert‑butyldibenzo‑18‑crown‑6 impregnated sorbent

Removal of 99Tc from low level radioactive liquid waste using di-tert-butyldibenzo-18-crown-6 impregnated sorbent

Evaluation of cerium–zirconium mixed oxides for separation of 125Sb from radioactive liquid waste

Separation of 99Tc from low level radioactive liquid waste using hollow fiber supported liquid membrane: optimisation and performance evaluation

Correction: Mechanism unravelling for highly efficient and selective 99TcO4− sequestration utilising crown ether based solvent system from nuclear liquid waste: experimental and computational investigations

Mechanism unravelling for highly efficient and selective 99TcO4− sequestration utilising crown ether based solvent system from nuclear liquid waste: experimental and computational investigations

Removal of ruthenium from high-level radioactive liquid waste generated during reprocessing of spent fuel

Preparation and characterisation of glass product with modified composition for vitrification of high level radioactive waste

Studies on modified borosilicate glass for enhancement of solubility of molybdenum

Evaluation of Metal Antimonate Compounds for the Removal of Radiostrontium from Radioactive Liquid Waste: Characterization and Sorption Behavior

Evaluation of Nickel Sulphide Prepared by Different Routes for Removal of 106Ru from Alkaline Radioactive Liquid Waste

Sequestration of Actinides by an Extraction Chromatography Resin Containing a Triaza-9-crown‑3 Functionalized Diglycolamide

Radioactive waste processing using membranes: State of the art technology, challenges and perspectives

Emerging functionalized magnetic nanoparticles: from synthesis to nuclear fuel cycle application: where do we stand after two decade?

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