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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.
Robert A. Fjeld, Timothy A. DeVol, Russell W. Goff, Matthew D. Blevins, David D. Brown, Steven M. Ince, Alan W. Elzerman, Meredith E. Newman
Nuclear Technology | Volume 135 | Number 2 | August 2001 | Pages 92-108
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3208
Articles are hosted by Taylor and Francis Online.
Laboratory column tests were performed to characterize the mobilities of 60Co, 90Sr, 137Cs, 233U, 239Pu, and 241Am in a basalt sample and a composite of sedimentary interbed from the Snake River Plain at the Idaho National Engineering and Environmental Laboratory. The radionuclides were spiked into a synthetic groundwater (pH 8, ionic strength = 0.004 M) and introduced into the columns (D = 2.6 cm, L = 15.2 cm) as finite steps with a width of 1 pore volume followed by unspiked synthetic groundwater. The effluent concentrations were measured continuously for up to 200 pore volumes. Hydrogen-3 was used as a nonreactive tracer in all of the experiments to monitor for channeling. In the basalt sample, the behavior of 90Sr, 137Cs, and 233U was quite different from that of 60Co, 239Pu, and 241Am. The column effluent curves for the former were characterized by single peaks containing, within the limits of experimental uncertainty, all of the activity in the spike. The mobilities were ordered as follows: 233U ([overbar]R = 5.6) > 90Sr ([overbar]R = 29) > 137Cs ([overbar]R = 79). The curves for the other radionuclides were characterized by two or three fractions, each having a distinctly different mobility. Cobalt-60 had high- ([overbar]R = < 3), intermediate- ([overbar]R = 34), and low- (R > 200) mobility fractions. Although a majority of the 239Pu and 241Am had low mobility (R > 200), there were high-mobility (R < 3) fractions of each (17 to 29% for 239Pu and 7 to 12% for 241Am). In sedimentary interbed, mobilities were generally much lower than in basalt. Uranium-233 was the only radionuclide with 100% recovery within 200 displaced pore volumes, and it had a retardation factor of 30. However, high-mobility fractions were observed for 60Co (1 to 4%) and 239Pu (1.1 to 2.4%). These results could have important implications with respect to transport modeling. If the multiple-mobility fractions observed here are also present in the field, transport predictions based on classical modeling approaches that incorporate mobilities from batch sorption experiments are likely to be in error.
