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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.
D. A. Spong
Fusion Science and Technology | Volume 50 | Number 3 | October 2006 | Pages 343-351
Technical Paper | Stellarators | doi.org/10.13182/FST06-A1255
Articles are hosted by Taylor and Francis Online.
Recent stellarator optimization efforts have targeted transport measures such as quasi-symmetry, effective ripple, and alignment of particle guiding center orbits with flux surfaces. This has resulted in significant reductions in neoclassical losses so that, at least for near-term experiments, the neoclassical transport of particles and energy can be made small compared to anomalous transport. However, momentum transport properties within magnetic flux surfaces provide an additional dimension for characterizing optimized stellarators. The momentum and flow damping features of optimized stellarators can vary widely, depending on their magnetic structure, ranging from systems with near-tokamak-like properties where toroidal flows dominate to those in which poloidal flows dominate and toroidal flows are suppressed. A set of tools has been developed for self-consistently evaluating the flow characteristics of different stellarators. Application of this model to existing and planned devices indicates that plasma flow properties vary significantly. Comparisons across devices can aid in unfolding the interplay between anomalous and neoclassical damping effects as well as the impact of momentum transport properties on related plasma phenomena such as turbulence suppression, shielding of resonant magnetic error fields, and impurity transport.