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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.
M. Kobayashi, N. Ohyabu, T. Mutoh, R. Kumazawa, Y. Feng, M. Shoji, T. Morisaki, S. Masuzaki, A. Sagara, R. Sakamoto, T. Seki, J. Miyazawa, T. Watanabe, M. Goto, K. Ideda, H. Kasahara, S. Morita, B. J. Peterson, N. Ashikawa, K. Saito, S. Sakakibara, T. Tokuzawa, Y. Nakamura, K. Narihara, I. Yamada, H. Yamada, A. Komori, O. Motojima, LHD Experimental Group
Fusion Science and Technology | Volume 52 | Number 3 | October 2007 | Pages 566-573
Technical Paper | The Technology of Fusion Energy - High Heat Flux Components | dx.doi.org/10.13182/FST07-A1549
Articles are hosted by Taylor and Francis Online.
The divertor performance of LHD is studied for the two configurations, LID and HD. It is shown that the both divertor configurations play important roles for obtaining high performance plasmas in LHD: the large pumping capability of the LID to keep the low edge density in the IDB-SDC plasma, the large wetted area and the flexibility of strike point sweep of HD to reduce the power load on the divertor plates in long pulse operations. The possible effect of the ergodic layer on impurity retention in divertor is discussed by using the 3D edge transport modelling. It is found that the drag force exerted by the plasma flow can dominate over the thermal force, providing the impurity retention effect. The further changes needed to improve the current divertor configurations are discussed. New divertor designs for the future upgrade of LHD and for a LHD-type reactor are presented.