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April 8–10, 2021
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Fusion Science and Technology
NC State celebrates 70 years of nuclear engineering education
An early picture of the research reactor building on the North Carolina State University campus. The Department of Nuclear Engineering is celebrating the 70th anniversary of its nuclear engineering curriculum in 2020–2021. Photo: North Carolina State University
The Department of Nuclear Engineering at North Carolina State University has spent the 2020–2021 academic year celebrating the 70th anniversary of its becoming the first U.S. university to establish a nuclear engineering curriculum. It started in 1950, when Clifford Beck, then of Oak Ridge, Tenn., obtained support from NC State’s dean of engineering, Harold Lampe, to build the nation’s first university nuclear reactor and, in conjunction, establish an educational curriculum dedicated to nuclear engineering.
The department, host to the 2021 ANS Virtual Student Conference, scheduled for April 8–10, now features 23 tenure/tenure-track faculty and three research faculty members. “What a journey for the first nuclear engineering curriculum in the nation,” said Kostadin Ivanov, professor and department head.
D. A. Humphreys, R. D. Deranian, J. R. Ferron, A. W. Hyatt, R. D. Johnson, R. R. Khayrutdinov, R. J. La Haye, J. A. Leuer, B. G. Penaflor, J. T. Scoville, M. L. Walker, A. S. Welander
Fusion Science and Technology | Volume 48 | Number 2 | October 2005 | Pages 1249-1263
Technical Paper | DIII-D Tokamak - Technologies for Next-Step Devices | dx.doi.org/10.13182/FST05-A1075
Articles are hosted by Taylor and Francis Online.
The integrated plasma control approach provides a systematic method for designing plasma control algorithms with high reliability and for confirming their performance off-line prior to experimental implementation. This approach includes construction of plasma and system response models, validation of models against operating experiments, design of integrated controllers that operate in concert with one another as well as with supervisory modules, simulation of control action against off-line and actual machine control platforms, and iteration of the design-test loop to optimize performance. Using this approach, required levels of robustness to model uncertainties and off-normal events can be quantified and incorporated in the design process. The DIII-D digital plasma control system (PCS) enables application of this method by providing a flexible programming environment and an architecture for real-time parallel operation of a set of computers that executes the large set of control algorithms needed for exploration of the advanced tokamak regime. The present work describes the DIII-D PCS and the approach, benefits, and progress made in integrated plasma control as applied to the DIII-D tokamak, with implications for the International Thermonuclear Experimental Reactor design and other next-generation tokamaks.