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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.
A. Aiello, I. Ricapito, G. Benamati, R. Valentini
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 872-876
Material Interaction and Permeation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST41-872
Articles are hosted by Taylor and Francis Online.
In considering structural materials for fusion reactors a detailed understanding of the transport parameters and solubility of hydrogen and its isotopes is an important issue which deal with safety and blanket performance aspects. The experimental activities were focused on the determination of hydrogen/deuterium transport parameters through Eurofer 97 in the temperature range 423+723K using a time dependant permeation technique The hydrogen permeation and diffusivity at room temperature and density of trapping sites were also evaluated using Devanathan's technique. Hydrogen / deuterium permeation experiments on Eurofer 97 showed a non-negligible decrease in permeability with respect to other fusion oriented martensitic steels, even if it remains about one order of magnitude higher compared with that of austenitic AISI 316L steel.