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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.F. Yang, G.S. Luan,† L. Bromberg, D.R. Cohn, B.J. Braams
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 857-863
Advanced Reactor | doi.org/10.13182/FST91-A29452
Articles are hosted by Taylor and Francis Online.
A novel gaseous divertor concept is proposed consisting of gas chamber and pumping at high pressure or by reionizing the neutrals. The concept results in substantial reductions of the plasma temperature and heat flux at the target and the pumping requirement. Fluid model simulations of the scrape-off region of the Aries Reactor design by feeding the gas at the target at a flux of 1 × 1023m−2/s at 0.5 eV has shown that the electron and ion temperatures can be cooled to 20 eV. The heat flux to the target can be reduced from 80 MW/m2 to 6 MW/m2. The plasma temperature and heat flux at the divertor target are monotonically decreasing functions of the neutral incident flux. Interestingly the temperature and the heat flux also decrease with decreasing neutral gas initial flowing speed removing the need of gas jets. The backflow problem can be minimized by including a baffle plate to form a gaseous chamber. Monte-Carlo simulations using test particles have showed that the throat of the gaseous chamber can be practically plugged by the incident plasma to prevent backflow of neutrals into plasma core. The pumping can be facilitated by either operating the divertor chamber at high pressure on the order of 30 torr or reionizing the neutrals traveling to a weak toroidal field region.