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ANS Student Conference 2025
April 3–5, 2025
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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.
N. A. Uckan, D. E. Post, J. C. Wesley, ITER JCT, ITER Home Teams, ITER Physics Expert Groups
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 371-376
International Thermonuclear Experimental Reactor (ITER) | doi.org/10.13182/FST98-A11963642
Articles are hosted by Taylor and Francis Online.
The physics knowledge relevant to the design of a reactor-scale tokamak—the ITER Physics Basis—has recently been assessed by the ITER JCT, the ITER Home Teams, and the ITER Physics Expert Groups. Physics design guidelines and methodologies for projecting plasma performance in ITER and reactor tokamaks are developed from extrapolations of various characterizations of the database for tokamak operation and of the understanding that its interpretation provides. Both “conventional” and “advanced tokamak” operating modes are considered. The overall device parameters for ITER are found to be consistent with these guidelines. The plasma performance attainable in ITER is affected by many physics issues, including energy confinement, L-to H and H-to-L-mode power transition thresholds, MHD stability/beta limit, density limit, disruptions, helium removal, impurity content, etc. Design basis and guidelines are provided in each of these areas, along with sensitivities and/or uncertainties involved.