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Argonne: Where AI research meets education and training
Last September, in the Chicago suburb of Lemont, Ill., Argonne National Laboratory hosted its first AI STEM Education Summit. More than 180 educators from high schools, community colleges, and universities; STEM administrators; and experts in various disciplines convened at “One Ecosystem, Many Pathways–Building an AI-Ready STEM Workforce” to discuss how artificial intelligence is reshaping STEM-related industries, including the implications for the nuclear engineering classroom and workforce.
L. H. Rovner, G. R. Hopkins
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 274-302
Technical Paper | Fusion Reactor Material / Material | doi.org/10.13182/NT76-A31593
Articles are hosted by Taylor and Francis Online.
The (low-atomic-number ceramic) materials carbon, SiC, Be2C, B4C, TiC, BN, Si3N4, Al2O3, and BeO provide a range of property values that are useful for evaluating range of applicability of low-atomic-number ceramic materials in fusion reactors. A survey of recent literature provides a base for conceptual design analyses of two first wall concepts: (a) a radiation-cooled simple plate liner and (b) a pressurized helium, forced convection-cooled tubular assembly. The first case is limited in heat load by maximum material temperature, and the second by either temperature or stress. Maximum temperatures are limited by vapor pressure or chemical reaction rates with plasma hydrogen, both resulting in release of impurities to the plasma. Silicon carbide and carbon appear most suitable for first wall materials, with estimated wall loading limits in the range from 1 to >5 MW/m2 of incident 14-MeV neutrons.