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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.
F. Warmer, C. D. Beidler, A. Dinklage, Y. Turkin, R. Wolf
Fusion Science and Technology | Volume 68 | Number 4 | November 2015 | Pages 727-740
Technical Paper | doi.org/10.13182/FST15-131
Articles are hosted by Taylor and Francis Online.
In fusion power plant studies, a high confinement improvement with respect to empirical scaling is often assumed in the design of compact machines. In this work, the limits of such a confinement enhancement are studied for a helical-axis advanced stellarator (HELIAS).
As a first exercise, the well-established power balance approach is used to investigate the impact of confinement enhancement (in terms of the ISS04 renormalization factor) on the required size of HELIAS power plants. It is found that both a lower (0.5) and an upper limit (1.5 to 1.7) exist for which, respectively, ignition is no longer possible or further confinement enhancement irrelevant due to physics limits.
In the second part of the work, a predictive neoclassical transport model is introduced and employed to determine a self-consistent confinement time based on transport modelling. It is found that the confinement enhancement with respect to the ISS04 scaling decreases in comparison to Wendelstein 7-X as the device is scaled to reactor size, dropping from ~2.5 to a range of 1.2 to 1.3. This behavior is explained with underlying scaling relations and transport effects. The results from both models are consistent and important for future HELIAS systems studies.