Affiliation:
1. Fuel Chemistry Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India
Abstract
Abstract
Studies have been carried out on removal of americium from the effluent generated during anion exchange purification of
plutonium. Americium 241, generated by the beta decay of Plutonium-241, is the major source of α activity in this highly acidic
effluent and its removal would render the waste easily disposable. A simple and effective co-precipitation method, using thorium
oxalate has been investigated for the treatment of this alpha active aqueous waste. Experiments have been carried out to identify
optimum conditions to obtain high percentage co-precipitation with minimum amount of co-precipitant. Efforts were carried out to
correlate the optimum conditions of co-precipitation of americium obtained in these experiments with solubility of thorium oxalate and
americium oxalate calculated from solubility products of these compounds, stability constants of thorium and americium oxalate
complexes taken from literature. The saturation capacity of thorium oxalate for Am(III) was also calculated by analyzing the
K
d value data using Langmuir adsorption equation. The strong tendency of americium to get co-precipitated and the high
capacity exhibited by thorium oxalate for the uptake of americium indicate feasibility of using this method for the treatment of anion
exchange effluent.
Subject
Physical and Theoretical Chemistry
Cited by
2 articles.
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