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The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2021 Student Conference
April 8–10, 2021
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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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.
A. Yamawaki, M. Fukumoto, Y. Soga, Y. Ohtsuka, Y. Ueda, K. Ohya
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 1038-1042
Divertors and High Heat Flux Components | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | dx.doi.org/10.13182/FST09-A9048
Articles are hosted by Taylor and Francis Online.
Since carbon deposition layers in tokamak devices will contain significant amount of tritium, it is important to study its formation mechanism. In this study, tungsten and molybdenum samples with a temperature gradient were irradiated by a mixed ion beam to precisely study temperature dependence of the deposition characteristics. For molybdenum, the temperature of the boundary between "deposition" and "nodeposition" is higher than W. This results roughly agree with the results by the material mixing model proposed by Kriegeretal [K. Krieger. J. Roth. J. of Nucl. Mater. 290-293 (2003) 107.]. Erosion yield of C deposition layer in our experimental conditions was almost equal or less than the yield by Rothmodel [J. Roth, C. Garcia-Rosales, Nucl. Fusion 36 (1996) 1647] for graphite.
