Published April 19, 2019 | Version v1
Journal article Open

Progress on in-vessel poloidal field coils optimization design for alternative divertor configuration studies on the EAST tokamak

  • 1. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, 230031, China
  • 2. University of Tuscia
  • 3. ENEA Unità Tecnica Fusione, C.R. Frascati, Via E. Fermi 45, 00044 Frascati, Roma, Italy
  • 4. e CREATE, Università di Napoli Federico II, Università di Cassino and Università di Napoli Parthenope, Via Claudio 19, 80125, Napoli, Italy

Description

This is the accepted manuscript (post-peer reviewed) of the following final paper: "Xiao, B.J., Luo, Z.P., Li, H., Li, G.Q., Wang, L., Wang, Z.L., Xu, G.S., Yao, D.M., Zhou, Z.B., Calabrò, G., Crisanti, F., Castaldo, A., Lombroni, R., Minucci, S., Ramogida, G., Progress on in-vessel poloidal field coils optimization design for alternative divertor configuration studies on the EAST tokamak, (2019) Fusion Engineering and Design, 146, pp. 2149-2152, https://doi.org/10.1016/j.fusengdes.2019.03.126"

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Funding

EUROfusion – Implementation of activities described in the Roadmap to Fusion during Horizon 2020 through a Joint programme of the members of the EUROfusion consortium 633053
European Commission