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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.
William L. Barr, B. Grant Logan
Fusion Science and Technology | Volume 18 | Number 2 | September 1990 | Pages 251-256
Technical Paper | Divertor System | doi.org/10.13182/FST90-A29297
Articles are hosted by Taylor and Francis Online.
A new divertor configuration is suggested as a possible solution to the problems of high heat flux and erosion at the divertors in large high-power tokamaks. The proposed configuration is a toroidally symmetrical slot in the divertor that allows part of the edge plasma and most of its power to enter a cavity in a thin annular sheet. The large surface area of the sheet is exposed to interaction with gas in the cavity. This results in radiation and a reflux of fast neutral atoms, both of which transport power to the cavity walls. The heat flux is reduced because the power is spread over a much larger area. Erosion due to sputtering is also reduced because the decreased power flux reduces the sheath potential and, therefore, the average ion impact energy. Sputtering by fast neutrals should not be a serious problem because neutrals are not accelerated by a sheath as are ions. Helium ash and impurity atoms that are ionized within the cavity tend to be trapped there by the electric field that must exist throughout the source region in order to make the removal rates for electrons and ions both equal to the production rate.