Home / Publications / Journals / Nuclear Technology / Volume 54 / Number 2
Nuclear Technology / Volume 54 / Number 2 / August 1981 / Pages 208-214
Technical Paper / Material / dx.doi.org/10.13182/NT81-A32736
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An electrolytic plutonium decontamination process for stainless steel was developed for use as the final step in a proposed radioactive waste handling and decontamination facility to be constructed at the Rockwell International Rocky Flats plutonium handling facility. The process utilizes a basic (pH > 7) electrolyte which has been patented (U.S. Patent 4 193 853). Filtration can be used to separate most radioactive contaminants and dissolved metal from the electrolyte. A test plan was executed comparing the basic electrolyte with phosphoric acid and nitric acid electrolytes. Laboratory-scale testing was done with stainless steel exposed to plutonium and americium. The alpha activity was reduced to <0.14 dis/min-cm-2. The amount of wet sludge generated with the basic electrolyte was ∼170 mg/cm2 of surface decontaminated.