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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.
Weston M. Stacey
Fusion Science and Technology | Volume 36 | Number 1 | July 1999 | Pages 38-46
Technical Paper | doi.org/10.13182/FST99-A89
Articles are hosted by Taylor and Francis Online.
A linear analysis of thermal instabilities along the magnetic field lines in the plasma edge is used to derive predictive algorithms for the edge density limit for the onset of multifaceted asymmetric radiation from the edge (MARFE) within the last closed flux surface in tokamaks. Calculated MARFE onset density limits for representative impurity and recycling neutral concentrations and representative edge plasma parameters in a model problem exhibit the expected strong dependence on impurity type and concentration at low recycling neutral concentrations. At recycling neutral concentrations greater than ~1 × 10-5, the MARFE onset density limit is found to depend strongly on the recycling neutral concentration and to be relatively independent of impurity type or concentration. Predicted MARFE onset density limits for two DIII-D shots agree reasonably well with experimental data.
