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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.
L. P. Ku, P. R. Garabedian
Fusion Science and Technology | Volume 50 | Number 2 | August 2006 | Pages 207-215
Technical Paper | Stellarators | doi.org/10.13182/FST06-A1237
Articles are hosted by Taylor and Francis Online.
We have identified and developed new classes of quasi-axially symmetric configurations that have attractive properties from the standpoint of both near-term physics experiments and long-term power-producing reactors. These include configurations with very small aspect ratios (~2.5) having superior quasi-symmetry and energetic particle confinement characteristics, and configurations with strongly negative global magnetic shear from the shaping fields so that the overall rotational transform, when combined with the transform from bootstrap currents at finite plasma pressures, will have a small but positive shear, making the avoidance of low-order rational surfaces at a given operating beta possible. Additionally, we have found configurations with National Compact Stellarator Experiment-like characteristics but with the biased components in the magnetic spectrum that allow us to improve the confinement of energetic particles. For each new class of configurations, we have also designed coils to ensure that the new configurations are realizable and engineering-wise feasible. The coil designs typically have the properties of R/min(C-P) 6 and R/min(C-C) 10, where R is the plasma major radius and min(C-P) and min(C-C) are the minimum coil-to-plasma and coil-to-coil separations, respectively. These coil properties allow power-producing reactors to be designed with R < 9 m for deuterium-tritium plasmas with a full breeding blanket. The good quasi-axisymmetry limits the energy loss of alpha particles to below 10%.