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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.
D C Robinson
Fusion Science and Technology | Volume 27 | Number 3 | April 1995 | Pages 144-149
Overview Paper | doi.org/10.13182/FST95-A11947059
Articles are hosted by Taylor and Francis Online.
The small aspect ratio tokamak combines the attractive features of the tokamak, reverse field pinch and spheromak to produce a compact, stable, high-β configuration with low external fields. Experiments on the Small Tight Aspect Ratio Tokamak (START) at Culham have demonstrated the production of stable, high temperature (Te ≤ 1keV), naturally elongated plasmas with good confinement, at aspect ratios down to 1.25. These plasmas are, so far, free from current-terminating disruptions and exhibit a natural divertor action. Theoretical studies have demonstrated robust stability at high β (> 30%) and self-consistent steady-state equilibria using pressure and beam driven currents. Such steady-state solutions exist for devices at the Mega Amp level, compact component test facilities and fusion power plants of modest size (Ro~2–3m).