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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.
Ehud Greenspan, George H. Miley
Fusion Science and Technology | Volume 2 | Number 4 | October 1982 | Pages 590-608
Technical Paper | Plasma Engineering | doi.org/10.13182/FST82-A20800
Articles are hosted by Taylor and Francis Online.
Partially catalyzed deuterium (PCD) fuel cycles and their sensitivity to ash buildup, radiation losses, Ti/Te. and 3He consumed are investigated. The study is machine independent, using a simple zero-dimensional steady-state model. The PCD fuel cycles include semi-catalyzed-deuterium where only a fraction of the 3He fuses and tritium-catalyzed-deuterium where 3He extracted from the plasma is converted into tritium, which is reinjected. Also considered is tritium-assisted operation where a fraction of the fusion neutrons is used to produce tritium, which is added to the PCD plasma. The PCD and tritium-assisted operation is shown to be attractive for certain nonelectrical applications. They avoid 3He recirculation required for catalyzed-deuterium (Cat-D) operation and enable simplified blanket designs. The ignition temperature, neт, and power density of PCD plasmas are very energy-balance sensitive, but under certain conditions these properties can be comparable or superior to those of Cat-D. Cyclotron radiation losses can significantly impair, whereas tritium assistance can strongly improve, PCD performance.