Μ. Κ. Rahman

Bio: Μ. Κ. Rahman is an academic researcher. The author has contributed to research in topics: PUREX & Ion-exchange resin. The author has an hindex of 1, co-authored 1 publications receiving 4 citations.

Clean Up of the Purex Process TBP Solvent by Macroreticular Ion Exchange Resin

Abstract: The possibility of using macroreticular ion-exchange resin A-26 and A-29 for cleaning the used purex process solvent has been investigated. The distribution co-efficients for Ru-Rh and Zr-Nb have been determined using the solution under three different conditions—active solution of pu ~ 0.5 as supplied, active solution washed with 1 M Na2C03 accompanied by rise in pu to — 5.0; Washed solution equilibrated with IN. HN03 thus bringing down the pa to ~0.5. The effects of temperature and particle size of the resins, on the distribution values have been evaluated. There is indication that distribution is preceded at least partly by decomposition of Ru-complex at higher pn and elevated temperature. Use of two different Purex process solutions revealed that distribution ratios are also dependent on the background history of the used solvents.

STUDIES ON THE UPTAKE OF Th(IV), U(VI) AND Pu(IV) ON DOWEX 50WX8 RESIN FROM TBP-SHELL SOL-T MIXTURES

Abstract: Batch equilibration studies have been carried out to understand the uptake of Th(IV), U(VI) and Pu(IV) on a conventional gel type cation exchange resin, Dowex 50WX8, from TBP-Shell Sol-T mixtures containing different amounts of nitric acid. Based on the results of the equilibration studies, column experiments have been carried out and conditions optimized to achieve separation of these elements present in binary and ternary mixtures. The influence of water content of the resin phase and the nature of the exchanging cation on the extent of uptake has also been investigated.

Ion exchange studies for the removal of plutonium and americium from organic liquid scintillator waste solution

Abstract: Removal of radioactive nuclides from effluents is important for the safe disposal of the radioactive waste. In the present work ion exchange studies were carried out using simulated alpha active organic liquid scintillator and ethyl alcohol waste solutions containing Pu and Am using different resins. The time of equilibration and batch data were obtained under different conditions for individual resins as well as their mixtures. The indigenously developed Macroporous bifunctional phosphinic acid (MPBPA) resin was found to be suitable for the removal of alpha activity mainly due to Pu and Amberlite IR-120 and Biorad 50Wx8 for removal of Am. The results indicated that the presence of alcohol in the scintillator solution helps in increasing the distribution ratio. Experiments were carried out with column containing either MPBPA resin alone or with additional resin bed of Amberlite IR-120 using active organic liquid scintillator waste (with and without dilution with alcohol). Studies were also carried out on alcoholic waste generated in the laboratory during the washing of the used liquid scintillator vials. The alcohol after removal of activity either could be reused or could be disposed off directly as a 'potentially' active waste.

Ion Exchange in Nuclear Fuel Reprocessing : Zirconium Phosphate Materials for the Separation of Trivalent Actinides and Lanthanides

Abstract: .................................................................................................................1 Acknowledgements ................................................................................................2 List of original publications .....................................................................................3 Abbreviations .........................................................................................................4