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Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
2023 ANS Winter Conference and Expo
November 12–15, 2023
Washington, D.C.|Washington Hilton
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Nuclear Science and Engineering
Fusion Science and Technology
NCSU’s advanced research reactor study to be funded by state
North Carolina’s fiscal year 2024 budget for the state has allocated $3 million for North Carolina State University, in Raleigh, to conduct a study to assess the feasibility for the establishment of an advanced nuclear research reactor.
D. B. Weisberg, J. Leuer, J. McClenaghan, J. H. Yu, W. Wehner, K. McLaughlin, T. Abrams, J. Barr, B. Grierson, B. Lyons, J. R. MacDonald, O. Meneghini, C. C. Petty, R. I. Pinsker, G. Sinclair, W. M. Solomon, T. Taylor, K. Thackston, D. Thomas, B. van Compernolle, M. VanZeeland, K. Zeller
Fusion Science and Technology | Volume 79 | Number 3 | April 2023 | Pages 320-344
Technical Paper | doi.org/10.1080/15361055.2022.2149210
Articles are hosted by Taylor and Francis Online.
A high-level design study for a new experimental tokamak shows that advances in fusion science and engineering can be leveraged to narrow the gaps in energy confinement and exhaust power handling that remain between present devices and a future fusion pilot plant (FPP). This potential new U.S. facility, an Exhaust and Confinement Integration Tokamak Experiment (EXCITE), will access an operational space close to the projected FPP performance regime via a compact, high-field, high-power-density approach that utilizes advanced tokamak scenarios and high-temperature superconductor magnets. Full-device optimization via system code calculations, physics-based core-edge modeling, plasma control simulations, and finite element structural and thermal analysis has converged on a T, MA, m, , D-D tokamak with strong plasma shaping, long-legged divertors, and 50 MW of auxiliary power. Such a device will match several absolute FPP parameters: plasma pressure, exhaust heat flux, and toroidal magnetic field. It will also narrow or close the gap in key dimensionless parameters: toroidal beta, bootstrap fraction, collisionality, and edge neutral opacity. Integrated neutron shielding preserves personnel access by limiting nuclear activation and maximizes experimental run time by reducing site radiation. In addition to design study results and optimization details, parameter sensitivities and uncertainties are also discussed.