Purification of americium from assorted analytical waste in hydrochloric acid medium |
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Authors: | A Sengupta S K Thulasidas V C Adya P K Mohapatra S V Godbole V K Manchanda |
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Institution: | (1) Radiochemistry Division, Bhabha Atomic Research Centre, Trombay, India;(2) Department of Energy Science, Sungkyunkwan University, Suwon, 440-746, Republic of Korea |
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Abstract: | During the simultaneous extraction of plutonium and uranium using anion exchange chromatographic technique from analytical
waste in hydrochloric acid medium, 241Am which is invariably present in the plutonium bearing fuel samples remains in the effluent. A two step separation scheme
was developed for the recovery and purification of Am from the assorted waste to facilitate the disposal of large volume of
aqueous waste and the purified Am solution was utilized for spectroscopic investigation. The separation scheme involved solvent
extraction using 0.1 M TODGA + 0.5 M DHOA for separation of americium from Fe, Pb, Ni and Na followed by extraction chromatographic
technique using CMPO on inert support as stationary phase for separation of Ca from Am. A systematic study on the extraction
behavior of Am from hydrochloric acid medium revealed that out of four extraction systems well known for actinide partitioning
namely 0.1 M TODGA + 0.5 M DHOA, 1 M DMDBTDMA, 0.2 M CMPO + 1.2 M TBP and 30% TRPO, only 0.1 M TODGA + 0.5 M DHOA extracts
americium from 7.5 M HCl feed acidity. A comparative study involving CMPO solvent extraction and column chromatographic technique
revealed that elution of Am from column is satisfactory as compared to inefficient stripping of Am from organic phase in solvent
extraction technique using 0.1 M HNO3. The purity of the final solution was checked for 17 elements of interest and was found to be 98% pure, while the overall
recovery of this two step separation scheme was found to be 95%. |
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