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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.
Nermin A. Uckan, John C. Wesley
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 398-402
Advanced Designs | doi.org/10.13182/FST01-A11963267
Articles are hosted by Taylor and Francis Online.
The physics design guidelines for a next step, high-field tokamak, burning plasma experiment (FIRE, Fusion Ignition Research Experiment) have been developed as an update of the ITER Physics Basis (IPB). The plasma performance attainable in FIRE (or any next-step device) is affected by many physics issues, including energy confinement, L-to-H-mode power transition thresholds, MHD stability/beta limit, density limit, helium accumulation/removal, impurity content, sawtooth effects, etc. Design basis and guidelines are provided in each of these areas, along with sensitivities and/or uncertainties involved. The overall basic device parameters and features for FIRE (R = 2 m, a = 0.525 m, κ95 ~ 1.8, δ95 ~ 0.4, q95 > 3, B = 10-12 T, I = 6.45-7.7 MA, Pfus ~ 100-200 MW, Q ~ 5-10) are consistent with these guidelines and uncertainties if the potential design upgrade option (12 T, 8 MA) is considered as part of the main design option.