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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.
J. W. Coenen, B. Bazylev, S. Brezinsek, V. Philipps, T. Hirai, A. Kreter, J. Linke, G. Pintsuk, G. Sergienko, A. Pospieszczyk, T. Tanabe, Y. Ueda, U. Samm, The TEXTOR Team
Fusion Science and Technology | Volume 61 | Number 2 | February 2012 | Pages 129-135
Technical Paper | First Joint ITER-IAEA Technical Meeting on Analysis of ITER Materials and Technologies | doi.org/10.13182/FST12-A13378
Articles are hosted by Taylor and Francis Online.
Behavior and characteristics of tungsten materials under impinging high heat fluxes are investigated. Experiments with inertially - not actively - cooled samples have been carried out in the plasma edge of the TEXTOR tokamak to study the changes of material properties such as grain size and abundance of voids or bubbles. In addition, the effects of electron beam impact regarding subsequent W power handling have been studied in view of future devices.The parallel heat flux at the radial position in TEXTOR impinging on the plasma-facing components (PFCs) ranges around q[parallel] [approximately] 45 MW/m2 allowing samples to be exposed at an impact angle of 35 deg to 20 to 30 MW/m2. Melt layer motion perpendicular to the magnetic field is observed following a Lorentz force originating from thermoelectric emission of the hot W sample. Up to 3 g of molten W are redistributed forming hill-like structures at the plasma-connected edge of the sample. The typical melt layer thickness is 1.0 to 1.5 mm. Those hills are, due to the changes in the local geometry, particularly susceptible to even higher heat fluxes of up to the full q[parallel]; hence, locally the temperature of W can reach up to 6000 K, and thus boiling can occur.In terms of material degradation, several aspects are considered: formation of leading edges by redistributed melt, bubble formation, and recrystallization. Bubbles are occurring in sizes between 1 and 200 m while recrystallization increases the grain size up to 1.5 mm. The power-handling capabilities are severely degraded by all those aspects. Melting of tungsten in future devices is highly unfavorable and needs to be avoided especially in light of uncontrolled transients and possible unshaped PFCs.Predamaged samples from the TEXTOR exposures have also been exposed in the JUDITH 1 facility under transient heat loads (up to [approximately]1 GW/m2, energy impact: 36 MWm-2s1/2). The samples show an unfavorable increase in the ductile-to-brittle transition temperature. In addition, surface cracks lose their directionality recrystallizing toward a more isotropic state from the manufactured monodirectional state. The increased grain size leads to a more brittle behavior under transient thermal loads with respect to crack progression.