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Latest News
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.
Paul B. Parks, Marshall N. Rosenbluth, Sergei V. Putvinski, Todd E. Evans
Fusion Science and Technology | Volume 35 | Number 3 | May 1999 | Pages 267-279
Technical Paper | doi.org/10.13182/FST99-A80
Articles are hosted by Taylor and Francis Online.
Proposed is a new concept for disruption mitigation and fast shutdown in tokamaks: the injection of hydrogen or helium liquid jets. Liquid jets can rapidly cool the plasma to reduce divertor heat loads and large halo current forces while simultaneously raising the density sufficiently to prevent runaway electron generation. Massive ~40- to 100-fold density increases equivalent to ~50 g of deuterium are necessary for this purpose in the International Thermonuclear Experimental Reactor (ITER). It is shown that only two or three simultaneously injected high-velocity (800 to 1200 m/s) jets can easily deliver this amount of fuel within a period of ~20 ms and thus avoid runaway electron buildup during the 50- to 500-ms current quench phase. Optimum jet parameters, such as radius, velocity, driving pressure, and injection time, predicted from a jet ablation/penetration model, lead to an innovative pulsed injector design concept. The design concept is also based on a thermodynamic process path that allows the lowest possible temperature at the nozzle orifice, given the constraint of a high, ~700-atm driving pressure. By having a cold jet exit the nozzle orifice, the potential problem of rapid boiling (flashover) during jet propagation across vacuum space between the nozzle orifice and the tokamak plasma can be overcome. A one-dimensional fluid-dynamic calculation, including finite compressibility, shows that a specially designed liquid Laval nozzle is needed for liquid helium injection because the jet velocity is supersonic (Mach number ~4). This injector concept is being considered for a proposed disruption mitigation experiment on DIII-D.