Comparison of the performance of solvent wash reagents used for the primary cleanup of degraded PUREX solvent

Author:

Mishra Satyabrata1,Mukhopadhyaya Chandan1,Patra Chayan1,Panantharayil Vishnu Anand1,Rajesh Puspalata23,Sivakumar Dasari1,Desigan Narasimhan1,Dhamodharan Krishnan1,Velavendan Periyakaruppan1,Rajeev Ramachandran Pillai1,Venkatesan Konda Athmaram13,Ananthasivan Krishnamurthy1

Affiliation:

1. Reprocessing Group, IGCAR , Kalpakkam , India

2. Water & Steam Chemistry Division , BARC Facilities , Kalpakkam , India

3. Homi Bhabha National Institute , Mumbai 400 094 , India

Abstract

Abstract The effectiveness of the solvent wash reagents such as sodium carbonate and hydrazine carbonate were compared using the lean solvent obtained during reprocessing of high plutonium content fast reactor spent nuclear fuel. The concentrations of the reagents were optimized based on the removal of retained metal ions from the lean solvent and 1.5 M hydrazine carbonate was found to be optimal and superior to sodium carbonate to be adopted as the reagent for primary cleanup of the spent solvent. Both the reagents were found to possess excellent room temperature stability and their performance was not affected upon gamma irradiation which was assessed in terms of capacity to remove di-butyl phosphate from degraded TBP/n-DD system.

Publisher

Walter de Gruyter GmbH

Subject

Physical and Theoretical Chemistry

Reference40 articles.

1. McKay, H. A. C., Miles, J. H., Swanson, J. L. The purex process. In Science and Technology of Tri Butyl Phosphate; Schulz, W. W., Burger, L. L., Navratil, J. D., Eds. CRS Press: Boca Raton, Vol. 3, 1984.

2. Pandey, N. K., Desigan, N., Ramanujam, A. PUREX and THOREX processes (aqueous reprocessing). In Reference Module in Mat. Sci. and Mat. Engg; Saleem Hashmi (editor-in-chief), Ed. Elsevier: Oxford, 2016, pp. 1–15. ISBN: 978-0-12-803581-8.

3. Tahraoui, A., Morris, J. H. Decomposition of solvent extraction media during nuclear reprocessing: literature review. Separ. Sci. Technol. 1995, 30, 2603–2630; https://doi.org/10.1080/01496399508013706.

4. Natarajan, R. Reprocessing of spent fast reactor nuclear fuels. In Reprocessing and Recycling of Spent Nuclear Fuel; Taylor, R., Ed. Woodhead Publishing Series in Energy: Oxford, 2015; pp. 213–243.

5. Amber, W., Patricia, P. H. Review of physical and chemical properties of tri butyl phosphate/diluent/nitric acid systems. Separ. Sci. Technol. 2010, 45, 1753–1762; https://doi.org/10.1080/01496395.2010.494087.

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