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Nuclear Science and Engineering
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.
M. F. Graswinckel, M. A. Van den Berg, W. A. Bongers, A. J. H. Donné, A. P. H. Goede, N. Lopes Cardozo, D. M. S. Ronden, A. G. A. Verhoeven
Fusion Science and Technology | Volume 53 | Number 1 | January 2008 | Pages 208-219
Technical Paper | Special Issue on Electron Cyclotron Wave Physics, Technology, and Applications - Part 2 | dx.doi.org/10.13182/FST08-A1666
Articles are hosted by Taylor and Francis Online.
A design is presented for the electron cyclotron (EC) heating and current drive system of the ITER upper port launchers based on the remote steering (RS) concept. In this concept the millimeter-wave beam is steered by a mirror that is located at the back end of the launcher waveguide. The RS concept has the advantage that the mirror steering mechanism can be situated in the secondary vacuum of the ITER machine where neutron flux and beryllium and tritium contamination is reduced. This allows simpler maintenance relative to a system with a plasma-facing steering mechanism. The optimization is carried out on the quasi-optical elements of the system, including the mirror shapes and positions. The design is assessed for its effectiveness in stabilizing the neoclassical tearing mode (NTM) over a wide range of ITER reference scenarios. The stabilization performance is quantified in terms of the parameter ntm, expressing the ratio between the peak EC wave-driven current density and the bootstrap current density, which parameter should exceed 1.2. The performance is also evaluated in terms of beam-focusing properties and power loading on the mirrors, and an empirical relation between beam size and ntm has been established. The performance achieved meets the requirements for NTM stabilization in all but one of the ITER reference scenarios.