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ANS Student Conference 2025
April 3–5, 2025
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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
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.