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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.
S. I. Abdel-Khalik, M. Yoda
Fusion Science and Technology | Volume 47 | Number 3 | April 2005 | Pages 601-609
Technical Paper | Fusion Energy - Inertial Fusion Technology | doi.org/10.13182/FST05-A752
Articles are hosted by Taylor and Francis Online.
This paper provides an overview of experimental and numerical studies conducted at Georgia Tech to assess the fluid dynamics aspects of liquid protection schemes for fusion energy reactors. The problems described here include: (1) Dynamics of slab jets for thick liquid protection, including the effect of nozzle design, flow conditioning, and boundary layer cutting on jet surface smoothness; (2) Primary turbulent breakup of turbulent liquid sheets and forced thin liquid films, and quantification of the associated hydrodynamic source term; (3) Dynamics of forced films on downward-facing flat and curved surfaces, including film detachment and flow around beam ports; (4) Free-surface topology and drop detachment from downward-facing porous wetted walls; and (5) Thermocapillary effects and associated design constraints for liquid-film-protected divertors and first walls.The experimental data and validated numerical models developed in these studies allow reactor designers to identify design windows for successful operation of liquid-protected first walls and plasma facing components in inertial and magnetic confinement systems.