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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.
R. W. Bussard, N. A. Krall
Fusion Science and Technology | Volume 26 | Number 4 | December 1994 | Pages 1326-1336
Technical Paper | Fusion Reactor | doi.org/10.13182/FST94-A30317
Articles are hosted by Taylor and Francis Online.
Performance scaling of fusion power sources shows that Maxwellian, magnetic, local-thermodynamic-equilibrium (MM/LTE) devices require much larger sizes and B fields than do electron-driven, inertial-electrostatic-confinement (EXL/IEC) systems for the same output. Basic economics analyses show that systems of either type must be small in size to be economically viable. This requires operation at high fusion power density and first-wall thermal fluxes; flux levels needed are well within those of practical power engineering experience. The EXL/IEC systems can satisfy these demands more readily than can MM/LTE systems. They can be operated to avoid particle thermalization, preserve ion core convergence, and yield a large power gain against losses (e.g., bremsstrahlung) for all fuels from deuterium-tritium to p-11B and 3He3He. Direct conversion of charged-particle energy, without arcing, is inherently straightforward in the quasispherical field geometry. If losses prove to be governed by classical physics phenomena rather than turbulent transport, all research and development (R&D) from physics studies to power plants can be done at a single size (≈3-m radius) and B field (≈1.2 T, 12 kG); no scaling growth in size or field is required. Consequent R&D costs and time scales are estimated to be <12 years and $1 billion for development of prototype EXL/IEC fusion power systems. Research investment seems warranted in this small-scale alternative to large-scale MM/LTE systems.