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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Latest News
Spent fuel transfer project completed at INL
Work crews at Idaho National Laboratory have transferred 40 spent nuclear fuel canisters into long-term storage vaults, the Department of Energy’s Office of Environmental Management has reported.
S. Chaudhury, S. A. Ansari, P. K. Mohapatra, D. M. Noronha, J. S. Pillai, Ashutosh Srivastava, I. C. Pius
Nuclear Technology | Volume 205 | Number 5 | May 2019 | Pages 727-735
Technical Paper | doi.org/10.1080/00295450.2018.1510699
Articles are hosted by Taylor and Francis Online.
Laboratory-scale studies were carried out to develop an analytical methodology for the processing of plutonium-bearing analytical laboratory waste at liter scale using hollow fiber–supported liquid membrane (HFSLM) technique by selective recovery of plutonium from uranium, americium, and other laboratory chemicals. In the first stage, uranium and plutonium were selectively transported from the feed to the receiver phase using 30% tri-n-butyl phosphate/n-dodecane which was used as the carrier in HFSLM. From the thus separated uranium and plutonium mixture, Pu(III) was selectively precipitated as ammonium plutonium(III)-oxalate [NH4Pu(C2O4)2 · 3H2O], leaving most of the uranium in the supernatant solution. A combination of HFSLM method followed by ammonium plutonium–oxalate precipitation is faster, gives lower radiation exposure to working personnel, and generates lesser volume of secondary waste as compared to traditional precipitation/ion-exchange technique. Furthermore, the present methodology signifies its importance in providing a very good yield of Pu recovery (>99%) from waste solution.