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Uptake of Ruthenium Bearing Waste by Co-Precipitation using Lead Sulfide as Scavenger
Ajay Kumar Mishra1, B S Panigrahi2

1Ajay Kumar Mishra, Centralized Waste Management Facility, Bhabha Atomic Research Centre Facilities Kalpakkam (Tamil Nadu), India.

2B S Panigrahi, Indira Gandhi Centre for Atomic Research, Kalpakkam (Tamil Nadu), India. 

Manuscript received on 31 October 2022 | Revised Manuscript received on 18 November 2022 | Manuscript Accepted on 15 November 2022 | Manuscript published on 30 November 2022 | PP: 4-8 | Volume-2 Issue-2, November 2022 | Retrieval Number: 100.1/ijee.B1837112222 | DOI: 10.54105/ijee.B1837.112222

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© The Authors. Published by Lattice Science Publication (LSP). This is an open-access article under the CC-BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/)

Abstract: During the fission of Uranium for generating electricity, fission products are produced. Ru-106 is one among them. In the decontamination of nuclear components using decontaminating agents like EDTA, NDA, oxalic acid etc, Ruthenium gets complexed and the waste generated as liquid contains Ru-106 in the complex state. It is necessary to free Ru-106 from the complex by oxidation of the complex. This will generate Ruthenium effluent with Ru-106 in the free state amenable for further treatment. An attempt has been made to co precipitate Ruthenium along with lead sulphide. The optimum pH, dosing of chemicals needed for in situ precipitation of lead sulphide were estimated in the batch study. Column studies using lead sulphide on polyurethane foam as column material were carried out for the treatment of Ruthenium bearing effluent. The optimum flow rate for maximum removal of Ruthenium was found to be 20 BV/h. Under optimized condition the max removal of Ruthenium was found to be 84% in the batch study, and 80% in the column study.  

Keywords: Zeta Potential, Co Precipitation, Decontamination, Treatment
Article of the Scope: Social Impacts of Wastewater Collection and Treatment