[en] Removal of uranium from the effluent stream of the fuel fabrication facilities and other related nuclear industries upto the extent of the allowed discharge limit of 60 ppb is an active area of studies. Chemical coagulation using a mixture of coagulants or polyelectrolytes, electro coagulation using a sacrificial anode and reverse osmosis are amongst the methods used for the purpose. The residue in all of these methods is a mixture of different ionic species along with uranium. A methodology for uranium removal based on precipitation of uranium as its oxoperoxocomplex, UO₂O₂⁰ which has a formation constant of 1.1 ´ 10³² has been evaluated

[en] The symposium covers a wide range of topics like, separation in nuclear fuel cycle, membrane science and technology, treatment of industrial effluents, chromatography and pyrochemical separations, computational chemistry in separation science, radiochemical separations, speciation of radionuclides in the environment etc. Papers relevant to INIS are indexed separately

[en] Rare earth elements (REEs) are a set of seventeen elements in the periodic table that include fifteen lanthanides plus scandium and yttrium. They have similar chemical properties due to common oxidation state III. The present talk will highlight the methodology adopted to devise a separation process flow-sheet to obtain the targeted rare earths from their mixture originating from mineral like monazite. Additionally the talk will also include some of the recent advances made in separation technology of rare earths

[en] The appropriate management of liquid radioactive waste is necessary due to the potential hazard that radioactive substances may cause to human health and the surrounding environment. The choice of processing method depends on its capital and operating costs, as well as on the characteristics of the waste, its quantity and the objectives to be achieved in the process: decontamination rate and volume reduction. This invited talk presents the overview of different membrane technologies and their commercial applications in chemical and nuclear industries including current scenario of these techniques applied world wide. Authors also cover some of the results obtained in laboratory using ‘concentration’ and ‘pressure driven’ based membrane techniques for treating waste generated by radioactive plants. Attempts are made to focus future progresses in membrane engineering

[en] The choice of equipment and the design of the process flowsheet for any solvent extraction process depends primarily on the kinetics of the extraction of the solute under consideration under the given process conditions. In this respect, studies on the kinetics of transfer of uranyl nitrate from Purex solvent (30% TBP in n-dodecane) to nitric acid under the conditions typically prevailing during the stripping cycle of Purex process was initiated. Various parameters that influence this transfer rates are mixing intensity, temperature, concentration of the solute, concentrations of the solvent and strip acid and the interfacial area. A constant area stirred cell was employed for this purpose. The present article reports the effect of the mixing intensity and temperature on the transfer rate of uranyl nitrate from 4 N nitric acid containing about 40 g/L of uranyl ion into 0.01 N nitric acid

[en] Zr-Nb alloys are used in the nuclear reactors and have stringent specification limit for chlorine (0.5ppm). The refractive nature of this material limits the pyrohydrolysis separation of chlorine as the matrix does not open even at 1000°C under moist O₂ atmosphere. This study has been initiated with a view to separate chlorine by a high temperature pyrohydrolysis apparatus specially designed to heat the sample above 1000°C. The developed method was employed for the determination of Cl impurity in real samples

[en] In today's engineering world, glass is a material serving a variety of applications from ornamental to industrial. One such application that we have considered for our research work is the vitrification of high level radioactive waste wherein different radio-nuclides of the waste are embedded inside glass matrix, followed by interim storage and ultimately deep geological repository. Analysis of one such system on lab scale is arduous since molten component and radioactive elements can’t be handle easily and leaching rates of radioactive elements is very small to be measured in the lab. The aid to this is molecular dynamics simulation

[en] Room temperature ionic liquids (RTILs) have extensively been used as the suitable alternate to the molecular diluents for the separation of actinides and fission products. In this context, couple of recent literatures highlights the extraction behavior of lanthanides/actinides using ionic liquid phase containing several molecular extractants. Among them, diglycolamides (DGA) are the well known CHON based extractants proposed for separation of minor actinides and lanthanides. Though, there is detail literatures available for the solvent extraction of Ln(III) and An(III) in DGA/ionic liquid mixture, their electrochemical behavior and the feasibility of electrodeposition in DGA-ionic liquid mixture is very scarce in the literature. The aim of the paper is to study the electrochemical behavior of europium(III), a representative lanthanide in DGA/ionic liquid mixture. N,N,N’,N’-tetra(ethylhexyl)diglycolamides (T2EHDGA) was choosen as the extractant from DGA based ligands in conjunction with the ionic liquid diluent: 1-alkyl-3- methylimidazolium bis(trifluoromethanesulfonyl)imide ((Cnmim)(NTf2)) as the electrolyte for the study

[en] Solvent extraction studies were carried out for the selective separation of thorium from uranium which is important for Indian nuclear programm. In this study we have used an acidic extractant, a Pyrazolones, HPMBP(1- phenyl- 3- methyl 4- benzoyl pyrazolone-5) which have a lower pK value of around 4.2. In this connection some basic studies on the extraction of thorium were carried out. Equal volumes of aqueous solutions of thorium and HPMBP were equilibrated and phases were separated. After centrifugation, from the aqueous phase known volumes were withdrawn and absorbance values were measured by spectrophotometric method using arsenazoIII as chromogenic reagent against corresponding blank. Absorbance of original thorium solution was also measured in the same way. From the absorbance value of aqueous thorium solution before and after equilibration the absorbance due to thorium extracted into the organic phase was found out by difference

[en] Recovery of scarce, expensive and biologically hazardous uranium from aqueous systems is an increasing worldwide problem which affects the environment and health. Development of suitable cost-effective approach for the recovery of uranium is a prime challenge. The biosorption process (the passive sorption of uranium by non-living biological materials) has recently gained attention because it has shown sorption efficacy and economic suitability. The biosorption capacity of several low-cost biosorbents derived from natural origins has been investigated in our previous studies. The enhanced recovery of uranium from contaminated water by the use of functionalized Panicum vergatum (common name is switch grass) bio-waste is demonstrated in this study