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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.
Theron Marshall, Robert Pawelko, Robert A. Anderl, Galen R. Smolik, Richard L. Moore, Brad Merrill
Fusion Science and Technology | Volume 45 | Number 4 | June 2004 | Pages 592-596
Technical Paper | doi.org/10.13182/FST04-A534
Articles are hosted by Taylor and Francis Online.
Carbon fiber composites (CFCs) are often suggested as armor material for the first wall of a fusion plasma chamber because of carbon's low atomic number, high thermal conductivity, and high melting point. However, carbon is chemically reactive in air and readily absorbs tritium. Accordingly, it is believed that during a loss-of-vacuum accident (LOVA), the CFC armor will react with the air ingress and release its absorbed tritium. The mobilization of this tritium and the carbon monoxide produced by the CFC-air chemical reaction are both safety concerns. This paper discusses the MELCOR thermal-hydraulic analysis of a simulated LOVA for the SOMBRERO fusion design. The MELCOR analysis is important because it included data from recent oxidation experiments that studied the advanced CFC NB31. A previous MELCOR analysis of a simulated SOMBRERO LOVA event suggested that the ingress of air would aggressively oxidize the CFC. While the current analysis revealed initial first-wall temperatures that exceed those of the prior analyses, the trend reversed 10 h after the onset of the LOVA. The calculated wall temperatures at the back of the blanket for the current analysis were consistently lower than those previously calculated using the older data. Accordingly, the conclusion is that a LOVA event for a fusion design similar to SOMBRERO may not be as grave as once predicted.