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 50W × 8 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.

Radiochemistry

“…Radioisotopes from the nuclear industry are usually dissolved in nitric acid solution and specific polymers and resins 245 have been developed to extract specific elements, such as strontium, 246 plutonium or americium 247 or groups of elements such as the actinides. 248 In the latter case a distinct improvement 249 in efficiency can be made by the use of supercritical carbon dioxide.…”