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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.
Fusion Science and Technology | Volume 53 | Number 4 | May 2008 | Pages 1023-1063
Technical Paper | Special Issue on Joint European Torus (jet) | dx.doi.org/10.13182/FST08-A1746
Articles are hosted by Taylor and Francis Online.
The tokamak plasma boundary, which is typically identified with the area of open field lines known as the scrape-off layer (SOL), determines the degree of plasma-wall interaction. SOL physics, much of which is concerned with the exhaust (removal) of particles and energy from the plasma, has been one of the major topics investigated on JET during the past two decades. In this chapter, SOL transport/exhaust studies on JET are reviewed. The discussion proceeds chronologically, beginning with the limiter SOL and treating in turn the successive divertors (Mk0, MkI, MkIIA, and MkIIGB) with which JET was equipped in subsequent years. When appropriate, old results are reinterpreted in the light of recent improvements in our understanding of edge/SOL turbulence and edge-localized modes (ELMs). Although emphasis is placed on deuterium transport in the SOL, impurity transport is briefly considered. In particular, the effect of divertor closure, of L-mode versus H-mode, and of inter-ELM versus ELM erosion on plasma purity (Zeff), radiation (frad), and confinement (E) is briefly discussed. The chapter concludes with a summary of empirical scaling expressions for SOL profile widths (radial e-folding lengths) in both limiter and divertor configurations.