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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.
C. Koehly, L. Bühler, C. Mistrangelo
Fusion Science and Technology | Volume 75 | Number 8 | November 2019 | Pages 1010-1015
Technical Paper | doi.org/10.1080/15361055.2019.1607705
Articles are hosted by Taylor and Francis Online.
The water-cooled lead lithium (WCLL) blanket is one of the European concepts for a Demonstration nuclear fusion reactor (DEMO). The spatial distribution of the water-cooling pipes inside the liquid metal blanket breeder zone is a critical issue since efficient heat removal from the liquid metal has to be ensured, avoiding local hot spots in the fluid or in blanket walls. Convective motion, driven by density gradients due to volumetric heat sources in the liquid breeder and heat removal by cooling pipes, is affected by magnetohydrodynamic interactions of the electrically conducting lead lithium with the external magnetic field. For the recent complex design of the DEMO WCLL blanket, prediction of the liquid metal flow is quite difficult. Preliminary numerical and experimental studies are necessary to determine the flow distribution resulting from the combined interaction of electromagnetic forces, buoyancy, and pressure. A test section based on a simplified model geometry supported by preliminary numerical simulations has been designed for experiments in the MEKKA laboratory at the Karlsruhe Institute of Technology and is presented in this paper.