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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.
Gokul Vasudevamurthy, Travis W. Knight, Thad M. Adams, Elwyn Roberts
Nuclear Technology | Volume 173 | Number 2 | February 2011 | Pages 200-209
Technical Paper | Materials for Nuclear Fuels | dx.doi.org/10.13182/NT11-A11549
Articles are hosted by Taylor and Francis Online.
Dispersed fuel composites consisting of uranium carbide particles (microspheres) in a zirconium carbide (inert) matrix were fabricated and characterized. Advanced fuels including refractory inert matrix fuels are being considered for gas fast reactors, which can accommodate a variety of feed materials including recycled transuranics that include minor actinides for incineration and high-level waste reduction. The particles for this effort were fabricated by employing a custom built rotating electrode machine. This process employed a uranium carbide electrode manufactured by combustion synthesis of uranium hydride and graphite powders. Two process parameters, namely, arc intensity and rotational speed, were varied to assess their effects on the size of the particles produced. The particles were characterized for microstructure, density, and composition (homogeneity). These particles were mixed with pure zirconium and graphite powders in different matrix to particle volumetric ratios of 90/10, 80/20, and 70/30 and inductively heated to 1850°C to initiate combustion synthesis to produce composites of zirconium carbide with the embedded uranium carbide particles. The aim was to limit process temperature and in particular process time, bearing in mind the possible future extensions of these processes to minor actinide-bearing fuels and also to avoid any changes in the structural integrity of the particles and large-scale diffusion of uranium into the matrix. The composites were characterized for microstructure, phase composition, density, and porosity distribution. The results are presented.