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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. Matera, M. Merola
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1873-1879
Plasma-Facing Component | doi.org/10.13182/FST92-A29992
Articles are hosted by Taylor and Francis Online.
The paper presents the conceptual study of an innovative divertor plate for the physical phase of the ITER/NET reactor. The main distinguishing feature of the new concept is the use of a single material, a Carbon Fibre reinforced Carbon (CFC) composite with ultra-high-thermal conductivity carbon fibres, for the whole structure, i.e. for the protective armour, heat sink and cooling channels. The main potential advantages of such a solution are perceived to be: elimination of the severe joint-interface problems inherent to other multimaterial solutions; weak interaction with runaway electrons; low-activation properties; reduction of mechanical stresses induced by electromagnetic transient. Moreover, the use of helium as a coolant leads to the following additional advantages: avoidance of the risk of burn-out; flexibility towards different operating scenarios; ease of baking at high temperature; lower tritium inventory in the CFC material; avoidance of the sharp pressure rise in cooling circuit because of water evaporation due to runaway electron impact. The thermal performance assessment shows that the maximum surface temperature can be kept below the threshold for radiation enhanced sublimation with comparable pumping power with that required by water cooling with turbulence promoters. After this study, which has to be considered as a first step in the iterative process for the development of a new component, the issue of the manufacturing feasibility in close collaboration with the composite industry will be addressed.