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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. R. Jarboe, C. J. Hansen, A. C. Hossack, G. J. Marklin, K. D. Morgan, B. A. Nelson, D. A. Sutherland, B. S. Victor
Fusion Science and Technology | Volume 66 | Number 3 | November 2014 | Pages 369-384
Technical Paper | doi.org/10.13182/FST14-782
Articles are hosted by Taylor and Francis Online.
The conceptual design of an experiment for demonstrating and developing the efficient sustainment of a spheromak with sufficient confinement is presented. “Sufficient” means that the current drive power can heat the plasma to its stability β limit. Previous transient experiments showing sufficient confinement in the kilo-electron-volt temperature range with no external toroidal field coil, recent results on Helicity Injected Torus with Steady Inductive (HIT-SI) showing sustainment with sufficient confinement, the potential of imposed dynamo current drive (IDCD) of solving other fusion issues, and a very attractive reactor concept justify a proof-of-principle experiment for a high-β spheromak sustained by IDCD. A machine with 1-m minor radius with the required density control, wall loading, and neutral shielding for a 10-s pulse is described. Peak temperatures of 3 keV and toroidal currents of 3.2 MA and 16% wall-normalized plasma β are envisioned.
