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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.
G. Luthardt, W. Mallener
Fusion Science and Technology | Volume 8 | Number 2 | September 1985 | Pages 2379-2383
Material Property and Tritium Control | Proceedings of the Second National Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Dayton, Ohio, April 30 to May 2, 1985) | doi.org/10.13182/FST85-A24634
Articles are hosted by Taylor and Francis Online.
Hydrogen permeation through high-temperature resistant metals can be reduced by three orders of magnitude at 800 °C by means of protective layers of several jam thickness produced by controlled preoxidation. The coating conditions must be adjusted individually to the various alloys. With the alloys under investigation, the following parameters have proven successful: steam or steam/H2, 900 to 1000°C, thermocycling mode of oxidation with intermediate cooling periods.
