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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.
Carmen García-Rosales, Sigrid Deschka, Wolfgang Hohenauer, Reiner Duwe, Eric Gauthier, Jochen Linke, Martin Lochter, Werner K. W. M. Malléner, Laurenz Plöchl, Peter Rödhammer, Armando Salito, Asdex-Upgrade Team
Fusion Science and Technology | Volume 32 | Number 2 | September 1997 | Pages 263-276
Technical Paper | First Wall Technology | doi.org/10.13182/FST97-A19896
Articles are hosted by Taylor and Francis Online.
Tiles of fine-grain graphite coated with tungsten layers by different plasma spray techniques (thickness 100 to 550 µm) and by physical vapor deposition (PVD) (thickness 20 to 100 µm) were subjected to heat fluxes, as expected for the divert or of the Axially Symmetric Divertor Experiment (ASDEX)-Upgrade tokamak. By a stepwise increase of the applied heat flux up to 16 MW/m2 and different pulse durations (1 to 5 s), the maximum load for disabling damage of the coating was determined. The fatigue behavior of the coatings was investigated by cyclic loading. The results show that plasma spray coatings are able to withstand heat loads up to 15 MW/m2 for a 2-s pulse without structural changes and cyclic loading with 1000 cycles at 10 MW/m2 and a 2-s pulse. The PVD coatings show damage by crack formation and melting at slightly lower heat loads than most of the plasma spray coatings. Under cyclic loading, the thin PVD coatings fail by extensive crack formation. The results of the tests indicate that the good performance of the plasma spray coatings is related to their higher porosity, which provides a crack-arresting mechanism, and to their mechanical strength.