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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.
W. L. Barr, R. H. Bulmer, L. J. Perkins, S. A. Cohen, K. A. Werley
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1416-1420
International Thermonuclear Experimental Reactor | doi.org/10.13182/FST92-A29920
Articles are hosted by Taylor and Francis Online.
We have just completed a comparison of predictions for the scrape-off layer (SOL) plasma, from a physics model [1] with the more accurate ones from a two-dimensional fluid code, the B2 code [2]. The results presented here show rather good agreement on values of plasma temperature in the SOL and of divertor heat load, for a rather wide range of Tokamak sizes and parameters. We are therefore confident that this model will provide a suitable divertor module for both the new ITER systems code, SUPERCODE [3], and other applications requiring fast but accurate modelling of edge plasma parameters, at least within the range of the present benchmarks.
