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Reactor Physics
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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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.
Panos J. Karditsas
Fusion Science and Technology | Volume 47 | Number 3 | April 2005 | Pages 729-733
Technical Paper | Fusion Energy - Divertor and Plasma-Facing Components | dx.doi.org/10.13182/FST05-A772
Articles are hosted by Taylor and Francis Online.
The High Efficiency Thermal Shield (HETS) concept was proposed by ENEA for divertor application in the context of the ITER project and as part of the European Power Plant Conceptual Study. The design is modular, and the unit dimensions are of the order of centimeters for limiting mechanical and thermal stresses. This paper presents results of thermal-fluid and structural analyses, with different heat flux loads, fluid pressures and inlet velocities. The fluid analysis shows that the sharp corner flow passage at the point of flow reversal behaves like an abrupt enlargement, leading to considerable pressure losses as compared to the results obtained by rounding the corner. The combination of rounding the sharp corner and flow cross-sectional area expansion, leads to reduced pressure losses, without any degradation of the thermal performance of the component.