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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.
O. Gastaldi, P. Aizes, F. Gabriel, J. F. Salavy, L. Giancarli
Fusion Science and Technology | Volume 54 | Number 1 | July 2008 | Pages 101-106
Technical Paper | Blanket Design | dx.doi.org/10.13182/FST08-A1774
Articles are hosted by Taylor and Francis Online.
Within the framework of the development of technology for a fusion reactor, the need of tritium breeding in order to reach fuel self-sufficiency is a major issue.The systems allowing this tritium production (breeding blanket) have to deal with a main difficulty that comes from the tendency for tritium to diffuse through hot metallic walls. Because of the double function of the blanket: i) breeding the necessary Tritium and ii) efficiently extracting the deposited heat, the coolantcontaining metallic surfaces used to promote the heat transfer lead also to a non negligible mass transfer of tritium from the breeder material towards the coolant.In order to improve the management of tritium, different studies have been launched in this field with applications to DEMO breeding blankets and to the corresponding Test Blanket Module (TBM) to be tested in ITER. The present paper is focused on the case of the helium cooled lithium lead (HCLL) blanket which is one of the two TBMs proposed by EU for testing in ITER.The study determines, for different scenarios of ITER operation (short pulse, long pulse and trains of back-to-back pulses), the flux of tritium between each circuit (mainly PbLi breeder and He coolant), and the inventories of tritium in each circuit. The establishment of mass balance equations for tritium in each circuit leads to a set of non linear differential equations solved in transient conditions since ITER pulses are too short to reach steady state. These equations rely mainly on Fick's law with a link to the tritium Sievert's constant in each metal.