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The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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.
D. R. Novog, S. T. Yin, J. S. Chang
Fusion Science and Technology | Volume 52 | Number 4 | November 2007 | Pages 880-884
Technical Paper | First Wall, Blanket, and Shield | dx.doi.org/10.13182/FST07-A1604
Articles are hosted by Taylor and Francis Online.
This paper presents the results of an experimental investigation conducted for high heat flux subcooled boiling heat transfer and pressure drop in a tubular channel under both smooth- and swirl-flow of high velocity water. High heat flux flow boiling is of interest to Fusion reactor first wall cooling. Test conditions covered a mass flux range from 5 to 10 Mg/m2 s, inlet temperatures from 100 to 175°C and system pressures from 2.0 to 5.0 MPa. The maximum heat flux tested was 12 MW/m2. The test section diameter used in this study was 5.30 mm (I.D.) with an axial heated length of 356 mm. To ensure accurate results, a significant number of heat balance tests were performed with a minimum and maximum heat balance error of 1.5%. Swirl-flow tests were performed using twisted tape inserts with thickness 0.8 mm with twist ratios between 2 and 4. To measure heat transfer performance, 15 miniature thermocouples were used to measure the tube outside wall temperature at various axial and circumferential positions. Differential pressure transducers were used to measure the axial pressure drop at several locations along the test section under single- and two-phase conditions.