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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.
Jonathan Coburn, Mohamed Bourham
Fusion Science and Technology | Volume 72 | Number 4 | November 2017 | Pages 692-698
Technical Note | doi.org/10.1080/15361055.2017.1352426
Articles are hosted by Taylor and Francis Online.
Innovative materials are investigated using a simulated electrothermal (ET) plasma to characterize erosion characteristics under ITER-relevant off-normal conditions. The tungsten alternatives investigated are mono-crystalline silicon carbides and MAX Phase ceramics. Preliminary code simulations using the ETFLOW plasma code are presented to assess erosive behavior in preparation for future experiments at ORNL’s electrothermal high heat flux experiment and the DiMES experiments for induced disruption on the DIII-D tokamak. Results indicate that erosion properties for SiC and two commercially available MAX Phases, Ti3SiC2 and Ti2AlC, compare well with tungsten and other ITER relevant components. A material-specific ablation constant, measured as total mass removed per incident heat flux per second, serves as a means for directly comparing erosion properties. Tungsten possesses the highest ablation constant value when compared to carbon, beryllium and the alternative materials α-6H SiC, Ti3SiC2, and Ti2AlC. The ablation thickness, calculated from the ablation constant and the specific density of the material, provides a comparison of surface thickness lost during a given off-normal event. Carbon (4.25 cm3/MJ) and tungsten (5.98 cm3/MJ) possess the lowest values. The alternative materials Ti3SiC2 (7.32 cm3/MJ) and α-6H SiC (8.44 cm3/MJ) exhibit the next best values, with Ti2AlC being the least effective (9.35 cm3/MJ). SiC shows the best vapor shielding efficiency of the three alternative materials, with Ti3SiC2 and Ti2AlC giving similar efficiencies. Taking into account vapor shielding effects using both opacity and fractional models, SiC exhibits the best ablation characteristics of the three materials in terms of thickness loss, with Ti3SiC2 giving similar results and overall appearing the superior of the two MAX Phases.
