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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.
L. El-Guebaly et al.
Fusion Science and Technology | Volume 47 | Number 3 | April 2005 | Pages 432-439
Technical Paper | Fusion Energy - Experimental Devices and Advanced Designs | doi.org/10.13182/FST05-A725
Articles are hosted by Taylor and Francis Online.
It is widely recognized among stellarator researchers that the minimum distance between the plasma boundary and the middle of the coil (min) is of great importance for stellarators as it impacts the machine parameters considerably. Techniques for minimizing the radial build have made impressive progress during the first year of the ARIES-CS study. A novel approach has been developed for ARIES-CS where the blanket at the critical area surrounding min has been replaced by a highly efficient WC-based shield. As a result, an appreciable 20-90 cm savings in the radial build has been achieved, reducing the major radius by more than 20%, which is significant. The economic benefit of this approach is yet to be determined and the added engineering problems and complexity will be addressed during the remaining period of the study. This paper covers the details of the radial build optimization process that contributed to the compactness of ARIES-CS. Compared with previous designs, the major radius of ARIES-CS has more than halved, dropping from 24 m to less than 10 m, making a step forward toward the feasibility of a compact stellarator power plant.