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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.
T. N. Carlstrom
Fusion Science and Technology | Volume 48 | Number 2 | October 2005 | Pages 997-1010
Technical Paper | DIII-D Tokamak - Achieving Reactor Quality Plasma Confinement | doi.org/10.13182/FST05-A1055
Articles are hosted by Taylor and Francis Online.
DIII-D contributions to H-mode transition physics and power thresholds are reviewed. Two general approaches were pursued: (a) establishing scaling relations based on empirical observations and (b) acquiring a theoretical understanding of the physics of the transition. The interaction of experiment results and the development of theories over the early 1990s led to the highly successful and widely accepted model of shear suppression of turbulence by crossed electric and magnetic fields (E × B) as the cause of improved confinement in H-mode. Experimental studies have also examined parameters at the edge of the plasma in order to identify a control parameter for the transition and to test various theories of the transition. The effect of the direction of the [nabla]B drift on the H-mode power threshold is used as a tool to further understand the physics of the L-H transition. Results on DIII-D and other tokamaks have guided researchers to study turbulent generated flows as a possible trigger for the L-H transition. Access to H-mode is controlled by a power threshold, and it is important to predict the threshold for next-generation tokamaks. In addition to electron density and toroidal field dependencies, it is found that many other parameters affect the power threshold. Studies of plasma size, magnetic configuration, and neutral effects have been performed. DIII-D data have been used in an international tokamak database to help establish scaling relations to predict power thresholds in future devices.