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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.
P. Deepika, K. N. Sabharwal, T. G. Srinivasan, P. R. Vasudeva Rao
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 407-416
Technical Paper | Reprocessing | doi.org/10.13182/NT12-A14172
Articles are hosted by Taylor and Francis Online.
2,6-bis(5,6-dipropyl-1,2,4-triazin-3-yl)pyridine (n-Pr-BTP) was impregnated on XAD-7 resin and the extraction performance of this n-Pr-BTP/XAD-7 resin was investigated for the uptake of Am(III) from acidic nitrate solutions. The uptake behavior of the lanthanides, La(III), Ce(III), Nd(III), Eu(III), and Gd(III), as well as elements such as Ba(II), Fe(III), Mo(VI), Ru(III), Zr(IV), Cs(I), and Sr(II) was also studied in batch experiments. It was found that the resin exhibited significantly high extraction and selectivity for Am(III) over the lanthanides and other elements. Based on the results obtained from batch studies, the separation behavior of Am(III) from Eu(III) was examined by extraction chromatography using a column packed with the n-Pr-BTP/XAD-7 resin. A complete separation between Am(III) and Eu(III) was achieved from aqueous phase containing nitric acid and ammonium nitrate in the column experiment. Based on this result, experiments were performed to investigate the separation of Am(III) from the lanthanides from octyl(phenyl)-N,N-diisobutylcarbamoylmethyl phosphine oxide (CMPO)-treated high-level waste.
