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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.
Shameem Hasan, Tushar K. Ghosh, Mark A. Prelas, Dabir S. Viswanath, Veera M. Boddu
Nuclear Technology | Volume 159 | Number 1 | July 2007 | Pages 59-71
Technical Paper | Reprocessing | doi.org/10.13182/NT07-A3856
Articles are hosted by Taylor and Francis Online.
Chitosan was coated on an inert substrate, perlite, and was prepared as spherical beads for adsorption of uranium from aqueous solutions. The uptake capacity of chitosan-coated perlite beads for uranium varied from 98.9 to 149 000 g/g when the equilibrium concentration of uranium in the solution ranged from 11 ppb (11 g/l) to 1000 ppm (10 × 106 g/l) and the solution pH was 5. The adsorption capacity of chitosan-coated perlite beads for uranium decreased by 75% in the presence of 0.45 M NaCl, whereas the adsorption capacity decreased by 55% when TiO2 was added to the beads during their preparation. The adsorption capacity of TiO2-containing chitosan beads for uranium was found to be in the range of 2.5 to 40 g of uranium per gram of beads when the concentration of uranium was 39 to 734 g/l in the presence of 0.45 M NaCl. It was in the range of 18 to 302 g of uranium per gram of beads when the concentration was 990 to 47 000 g/l in the presence of 0.45 M Na2CO3. Chitosan-coated beads were found to preferentially adsorb uranium, Cd, and Cr from a mixture containing these ions along with Sr and Cs. Only a negligible amount of Sr and Cs was adsorbed by chitosan-coated beads. The data suggest that the chitosan-coated beads can be used for both extraction of uranium from waste streams and also from a highly acidic medium such as a reprocessing stream that uses nitric acid.