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Latest News
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.
Satoshi Fukada, Samsun-Baharin Mohamad, Hiroshi Fujiwara, Masabumi Nishikawa
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 1082-1086
Isotope Separation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22750
Articles are hosted by Taylor and Francis Online.
Chromatographic separation of hydrogen isotopes, protium and deuterium, was carried out experimentally using a four-column Pd bed system. The system was operated under the conditions of atmospheric hydrogen pressure and swing of column temperature of 303 K to 473 K. Maximum deuterium enrichment ratio defined as the ratio of the deuterium concentration in product to that in feed was around 100 independent of the deuterium concentration. The deuterium recovery ratio was more than 0.5. Effluent curves were analyzed by the numerical simulation by the plate model. Close agreement was obtained between experiment and analysis. High enrichment of deuterium was also successfully achieved by frontal chromatography using a comparatively large column.
