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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.
Suk-Kwon Kim, Bong Guen Hong, Dong Won Lee, Do Heon Kim, Young-Ouk Lee
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 746-750
Nuclear Analysis | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | dx.doi.org/10.13182/FST09-A8998
Articles are hosted by Taylor and Francis Online.
A system analysis has been performed to develop the concepts for a fusion reactor and to identify the design parameters by using the tokamak system analysis code at KAERI (Korea Atomic Energy Research Institute). The system code elucidates the device parameters which satisfy the plasma physics and engineering constraints by taking into account a wide range of plasma physics and technology effects, simultaneously. The calculation of 1-D neutronic system code was coupled with this tokamak system code to optimize the reactor parameters. The numerical simulation for blanket neutronics was performed with MCNP5 code to calculate the tritium breeding ratios and neutron multiplications, which were the input parameter of system code. With the coupled system analysis and one-dimensional neutronic calculation, we assessed various types of DEMO blanket concepts with the requirements for the DEMO selected as to demonstrate the tritium self-sufficiency, to generate a net electricity amount, and for a steady-state operation.