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April 8–10, 2021
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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.
J. Konys, W. Krauss, H. Steiner
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 281-288
Fusion Materials | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | dx.doi.org/10.13182/FST09-A8915
Articles are hosted by Taylor and Francis Online.
RAFM steels (e.g. Eurofer) are considered as struc-tural material for blanket components of future fusion power plants. One of the envisaged blanket concepts to be tested in ITER foresees the application of a liquid breed-er, the eutectic lead alloy Pb-17Li. Various corrosion experiments have been made in the past, mostly conducted up to temperatures of ca. 480°C, with respect to deter-mine corrosion rates and mechanisms and comparison of the results with earlier tested RAFM-steels of type F82H-mod., Optifer and Manet. In the mean time the envisaged operational temperature increased to around 550°C and flow rates may also have changed. Thus extrapolations of the RAFM-steel corrosion behavior determined in the past to the higher working conditions may be problematic due to large uncertainties in reliability and, additionally, only low knowledge on transport of dissolved components in the Pb-17Li flow is present.Therefore, the development of modeling tools for de-scribing Pb-17Li corrosion was of absolute necessity. The modular structured code MATLIM is based on physical, chemical and thermo-hydraulic parameters and, in the first stage, the development was focused on the dissolu-tion of Eurofer steel and validation with test results ob-tained at 480 and 550°C in the lead-lithium loop PICOLO of FZK.