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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.
R. Mitteau, Tore Supra Team
Fusion Science and Technology | Volume 56 | Number 3 | October 2009 | Pages 1353-1365
Technical Papers | Tore Supra Special Issue | dx.doi.org/10.13182/FST09-A9182
Articles are hosted by Taylor and Francis Online.
The main key to achieving high-power long-duration discharges on Tore Supra, the actively cooled toroidal pump limiter (TPL) is the main plasma-facing component, handling high heat fluxes. The heat pattern on the TPL presents features of both localized and large-area limiters (mixed influences of parallel and cross-field heat fluxes). The combination of the toroidal field ripple and the flat surface results in a peaked heat flux pattern with large private flux areas on the surface. The apparent heat flux decay length is shorter than 10 mm and varies by less than 10% with the plasma conditions. The conduction/convection is modeled within 5% by the heat flux deposition code TOKAFLUX. The heat pattern is further modified by the contribution of suprathermal particles (ion ripple losses, fast electrons). Altogether, the relation of the peak heat flux to a given injected power is consistent with modeling made during TPL design. The thermal response of the elements is also in line with the design, with a typical thermal time constant of 1 s and steady-state surface temperature during long discharges. An important issue being investigated concerns the growth of material deposits; they accumulate in shadowed areas and especially just along the frontier to plasma-wetted areas. In 2009, the limiter is still in operation and several thematics are still being actively investigated, such as the effect of the material deposits on the operation, the long-time-scale behavior of the tile to heat sink bond, and the deuterium retention.