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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.
J. D. Galambos, D. J. Strickler, Y-K. M. Peng, R. L. Reid
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 483-488
Plasma Engineering | doi.org/10.13182/FST89-A39746
Articles are hosted by Taylor and Francis Online.
Trade studies are performed to determine the optimum plasma elongation for a next-step tokamak such as the International Thermonuclear Experimental Reactor. Degradations of the plasma beta limit for high elongations and poloidal field coil scaling with elongation are included in the analysis. When plasma ignition is required using confinement scalings that include direct plasma current or power degradation terms, the optimum elongation is between 2.5 and 2.9, but generally the minimum-cost curve is relatively flat for elongations over 2.3. When confinement scalings that depend only on size are used or when only current drive performance is required, the optimum elongation is near 2.3. Also, when only a plasma current and neutron wall load are used as plasma performance limits, the optimum elongation is between 2.6 and 2.8, but with small cost benefits above elongations of 2.3.