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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.
J.-M. Travere, M.-H. Aumeunier, M. Joanny, T. Loarer, M. Firdaouss, E. Gauthier, V. Martin, V. Moncada, L. Marot, D. Chabaud, E. Humbert, J.-J. Fermé, C. Thellier
Fusion Science and Technology | Volume 64 | Number 4 | November 2013 | Pages 735-740
Technical Paper | doi.org/10.13182/FST13-A24093
Articles are hosted by Taylor and Francis Online.
The ITER actively cooled tokamak is the next-generation fusion device that will allow study of the burning plasma over hundreds of seconds. ITER plasma-facing component (PFC) real-time protection will be mandatory to minimize operational risks as water leaks and critical heat flux lead to degradation of PFCs. The protection systems routinely used on Tore Supra (TS) or JET are based on infrared (IR) imaging systems controlling and monitoring the power load on the PFCs through surface temperature measurements. Thanks to TS expertise in actively cooled tokamak and long-pulse operation, three urgent research and development domains are discussed in this paper addressing the feasibility and the performance of the PFC protection function for the new and harsh environment of ITER: (a) the understanding of IR signals in a reflective environment using a physics-based light model simulation; (b) a PFC protection data processing architecture for event detection and identification; and (c) the feasibility, performance, and prototyping of the first optical component of the imaging systems - actively cooled, facing the plasma - which will impact the image quality and therefore PFC protection performance.