P. Velavendan

Indira Gandhi Centre for Atomic Research

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N. K. Pandey

Indira Gandhi Centre for Atomic Research

U. Kamachi Mudali

Central Ground Water Board

R. Natarajan

Alagappa University

S. Ganesh

SRM Institute of Science and Technology

Mohamed Ahmed

University of Khartoum

R. Rajeev

Indira Gandhi Centre for Atomic Research

N. Desigan

Indira Gandhi Centre for Atomic Research

Satyabrata Mishra

Indira Gandhi Centre for Atomic Research

K. A. Venkatesan

Sri Ramakrishna Institute of Paramedical Sciences

Fahmida Khan

National Institute of Technology Raipur

Cooperative Institutions

Indira Gandhi Centre for Atomic Research

Homi Bhabha National Institute

Bhabha Atomic Research Centre

SRM Institute of Science and Technology

Vel Tech Rangarajan Dr. Sagunthala R&D Institute of Science and Technology

National Institute of Technology Raipur

Department of Atomic Energy

Vellore Institute of Technology University

Atomic Energy Regulatory Board

Atomic Minerals Directorate for Exploration and Research

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Flow Injection Analysis of Hydrazine in the Aqueous Streams of Purex Process by Liquid Chromatography System Coupled with UV-Visible Detector

Journal of Analytical Sciences Methods and Instrumentation (2012)

P. Velavendan N. K. Pandey S. Ganesh N. K. Pandey U. Kamachi Mudali R. Natarajan

Present study describes the development of a rapid, sensitive and selective flow injection analysis of hydrazine in the aqueous streams of purex process by liquid chromatography system coupled with UV-Visible detector. The method is based on the formation of yellow coloured azine complex by reaction of hydrazine with para-dimethy laminobenzaldehyde (pDMAB). The formed yellow coloured complex is stable in acidic medium and has a maximum absorption at 460 nm. The presence of uranium in hydrazine solution is not interfering in the analysis. Under optimum condition, the absorption intensity linearly increased with the concentration of hydrazine in the range from 0.05-10 mg?L–1 with a correlation coefficient of R2=0.9999 (n=7). The experimental detection limit is 0.05mgL–1. The sampling frequency is 15 samples h–1 and the relative standard deviation was 2.1% for 0.05 mg?L–1. This method is suitable for automatic and continuous analysis and successfully applied to determine the concentration of hydrazine in the aqueous stream of nuclear fuel reprocessing.

PUREX

Hydrazine (antidepressant)

Flow injection analysis

Azine

10.4236/jasmi.2012.23025

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Citations (2)

Modeling and simulation of diluent recovery unit in PUREX solvent regeneration system

Progress in Nuclear Energy (2017)

P. Vishnu Anand R. Rajeev P. Velavendan N. K. Pandey U. Kamachi Mudali

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Diluent

Subcooling

10.1016/j.pnucene.2017.01.011

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Citations (5)

Ozone Oxidation Process for the Mineralization of Solvent Degradation Product- Di-N-Butyl Phosphate

Academic Journal of Chemistry (2018)

P. Velavendan N. K. Pandey A. Ravishankar

An experimental study usingÂ semi-batch reaction vessel to evaluate the applicability of ozone oxidation process for the mineralization of di-n-butyl phosphate, which is one of the major degradation product of PUREX solvent (Tri-n-Butyl phosphate). Power law kinetic model for prediction of the conversion profiles of DBP fitted with the experimental results well. From the analysis of experimental data it is found that first - order kinetic is appropriate to describe the oxidation kinetics of DBP. The influence of temperature and the combined effect of ozone on the oxidation efficiency of DBP have been carried out. The global reaction rate constants are found to be in the range of 10-3 min-1.

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Degradation

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Direct spectrophotometric determination of ruthenium in aqueous streams of nuclear reprocessing

Journal of Radioanalytical and Nuclear Chemistry (2012)

S. Ganesh P. Velavendan N. K. Pandey U. Kamachi Mudali R. Natarajan

Nitric acid

Relative standard deviation

10.1007/s10967-012-2229-5

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Citations (2)

Estimation of free acidity in some hydrolysable metal ions present in reprocessing streams by fiber optic aided spectrophotometry

Journal of Radioanalytical and Nuclear Chemistry (2014)

S. Ganesh P. Velavendan N. K. Pandey U. Kamachi Mudali R. Natarajan

Spectrophotometry

10.1007/s10967-014-3658-0

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Citations (4)

Development of an analytical method for estimating the composition of NO x gas using ion chromatography

N. Desigan P. Velavendan Remya Murali Elizabeth Augustine N. K. Pandey

Ion chromatography

Source

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Adsorption of di-butyl phosphate on activated alumina: equilibrium and kinetics

Desalination and Water Treatment (2013)

N. K. Pandey P. Velavendan U. Kamachi Mudali R. Natarajan

The rate of removal of di-n-butyl phosphate (DBP) by sorption on activated alumina (AA) has been studied in batch conditions. The rate of adsorption of DBP is initially rapid for about 10–20 min and reaches a maximum in about two hours. The Langmuir and Freundlich isotherm equations have been used to describe the partitioning behavior of the system. Kinetic modeling analysis of the pseudo-first-order, pseudo-second-order, and pore diffusion model, coupled with the observed Langmuir or Freundlich isotherm equations showed that pseudo-second-order equation and pore diffusion model to be the most appropriate models for the description of transport of DBP within AA particles. The agreement between the model predictions and experimental data indicated that adsorption and diffusion of DBP can be simulated by the proposed models. From analysis of the experimental kinetic data, effective diffusivity has also been estimated and is found to be in the range of 10−9 cm2/s.

Langmuir adsorption model

10.1080/19443994.2013.839397

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Citations (3)

Studies on solubility of TBP in aqueous solutions of fuel reprocessing

Journal of Radioanalytical and Nuclear Chemistry (2012)

P. Velavendan S. Ganesh N. K. Pandey R. Geetha Mohamed Ahmed

Nitric acid

Diluent

Raffinate

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Tributyl phosphate

Nuclear fission product

Dodecane

10.1007/s10967-012-1945-1

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Citations (19)

Comparative studies on the determination of di-n-butyl phosphate in degraded solvent of PUREX process by ion chromatography and gas chromatography methods

Desalination and Water Treatment (2012)

P. Velavendan S. Ganesh N. K. Pandey U. Kamachi Mudali R. Natarajan

Abstract This paper describes comparative studies on the determination of di-n-butyl phosphate (DBP) by ion chromatography (IC) and gas chromatography (GC) techniques in spent solvent of PUREX process used for the reprocessing of spent nuclear fuels. The ion chromatography method involves the separation of DBP from 30% TBP–NPH (tri-n-butylphosphate diluted in normal paraffin hydrocarbon) containing heavy metal ion like uranium and nitric acid by extraction of DBP into alkaline medium. DBP was subsequently eluted by ion-exchange separation in ion chromatography column and followed by suppressed conductivity detection. DBP is quantified to a lower limit of about 1 ppm with 3% RSD. However, in order to determine DBP by gas chromatography technique DBP is first quantitatively converted into its volatile and stable derivatives by using diazomethane prior to analysis by GC. Results obtained with ion chromatographic technique are compared with those of obtained by standard gas chromatographic technique. It was observed that IC technique involves minimum steps and is much faster than GC analysis. The effect of mobile phase flow rate on the detector response, retention time, and column pressure are also investigated.

Ion chromatography

Nitric acid

PUREX

Thermal conductivity detector

10.1080/19443994.2012.708208

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Citations (4)

Adsorption Kinetics and Breakthrough Behaviour of Tri-n-butyl Phosphate on Amberlite XAD-4 Resin

Journal of Nuclear Science and Technology (1998)

N. K. Pandey P. Velavendan R. GEETHA Mohamed Ahmed S. B. Koganti

Adsorption behaviour of tri-n-butyl phosphate (TBP) from aqueous solution (dilute HNO3) on Amberlite XAD-4 has been investigated experimentally. Factors affecting the adsorption rates and breakthrough curves have been studied in batchwise and semicontinuous fixed bed adsorber. The adsorption isotherm of TBP on Amberlite XAD-4 resin have also been determined and the Freundlich model of adsorption is used to describe adsorption equilibrium. For the case of nonlinear equilibrium a simplified method proposed by Chi Tein is used to estimate intraparticle diffusion coefficient. The intraparticle diffusion coefficient is found to be in the range of 10−8 cm2·s−1. Results of fixed bed column are used to estimate mass transfer zone (MTZ) length, length of unused bed (LUB), breakthrough capacity corresponding to fixed value of effluent concentration (5 mg/l of TBP) and degree of saturation of bed at breakthrough. The MTZ length was found to vary from 21.8 cm to 37.3cm when flow rate changed from 13.5 ml/min to 52 ml/min, whereas column utilization ranged from 65.1% for the lowest flow rate to 43.5% for the highest flow rate.

Amberlite

Saturation (graph theory)

Ion-exchange resin

10.1080/18811248.1998.9733874

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Citations (15)