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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.
Takahiko Sugiyama, Eiji Suzuki, Masahiro Tanaka, Ichiro Yamamoto
Fusion Science and Technology | Volume 60 | Number 4 | November 2011 | Pages 1323-1326
Detritiation and Isotope Separation | Proceedings of the Ninth International Conference on Tritium Science and Technology (Part 2) | doi.org/10.13182/FST11-A12673
Articles are hosted by Taylor and Francis Online.
Experimental and analytical studies on hydrogen-tritium isotope separation by a CECE process with a LPCE column have been carried out in order to apply it to the water detritiation system for fusion reactors. Kogel catalysts and Dixon gauze rings were mixed at a certain ratio and packed in the column in a random manner. Performance tests of tritium separation by the column of 1 m length and 2.5 cm I.D. were performed at 101 kPa and 343 K. The maximum value of the separation factor was 19200 when the flow rate of hydrogen gas was 5 L/min. The optimum value of catalyst packing ratio was obtained as 35 % by the analysis using the channeling stage model. The values of separation factors predicted by the model corresponded with measured ones very well.
