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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.
William D. Langer, Alicia Butcher Ehrhardt
Fusion Science and Technology | Volume 15 | Number 1 | January 1989 | Pages 118-126
Technical Paper | doi.org/10.13182/FST89-A25334
Articles are hosted by Taylor and Francis Online.
The theory of carbon transport in a plasma boundary layer is important for understanding the impurity penetration, and carbon and hydrogen recycling, in tokamaks using carbon compounds as limiters and as wall coatings. Neutral carbon kinetics and transport at the edge of plasma devices where chemical release is a source of carbon are modeled. Plasma reactions with carbon and hydrocarbons are important for such modeling, and these collisional processes are summarized. Combining the reaction schemes and kinetics in the DEGAS code makes it possible to treat the neutral transport at the plasma boundary layer. Results of such modeling of the atomic carbon and methane distribution at the edge are presented for comparison with recent carbon probe experiments performed on the Divertor and Injection Tokamak Experiment (DITE). The density distribution of carbon impurities at the edge is found to vary with edge conditions, with that of each daughter product in the breakdown being much broader and deeper than the parent molecule. Furthermore, the energy of the carbon atoms released from methane is considerably higher, on average, than the energy at which the methane is released from the wall or limiter. At high densities recycling can play an important role in the transport, and as much as 30% of the carbon flux might be due to recycling in the DITE configuration. Recycling can also be important for understanding the erosion and redeposition of carbon on limiters, which, while apparently insignificant in the DITE carbon probe experiments, might be important for limiters on the Tokamak Fusion Test Reactor.