A preliminary conceptual design study for Korean fusion DEMO reactor

Fusion Engineering and Design 88 (2013) 488–491 Contents lists available at ScienceDirect Fusion Engineering and Design journal homepage: www.elsevier.com/locate/fusengdes A preliminary conceptual design study for Korean fusion DEMO reactor Keeman Kim a,*, Hyoung Chan Kim a, Sangjun Oh a, Young Seok Lee a, Jun Ho Yeom a, Kihak Im a, Gyung-Su Lee a, George Neilson b, Charles Kessel b, Thomas Brown b, Peter Titus b a National Fusion Research Institute, 169-148 Gwahak-ro, Daejeon 305-806, Republic of Korea b Princeton Plasma Physics Laboratory, Princeton University, Princeton, NJ 08543, USA Highlights: - Perform a preliminary conceptual study for a steady-state Korean DEMO reactor. - Present design guidelines and requirements of Korean DEMO reactor. - Present a preliminary design of TF (toroidal field) and CS (central solenoid) magnet. - Present a preliminary result of the radial build scheme of Korean DEMO reactor. Article Info: Received 13 September 2012 Received in revised form 8 February 2013 Accepted 20 February 2013 Available online 27 March 2013 Keywords: DEMO, Reactor design, 16-T Nb3Sn TF magnets, Two-stage development plan Abstract: As the ITER is being constructed, there is a growing anticipation for an earlier realization of fusion energy, so called fast-track approach. Korean strategy for fusion energy can be regarded as a fast-track approach and one special concept discussed in this paper is a two-stage development plan. At first, a steady-state Korean DEMO Reactor (K-DEMO) is designed not only to demonstrate a net electricity generation and a self-sustained tritium cycle, but also to be used as a component test facility. Then, at its second stage, a major upgrade is carried out by replacing in-vessel components in order to show a net electric generation on the order of 300 MWe and the competitiveness in cost of electricity (COE). The major radius is designed to be just below 6.5 m, considering practical engineering feasibilities. By using high performance Nb3Sn-based superconducting cable currently available, high magnetic field at the plasma center above 8 T can be achieved. A design concept for TF magnets and radial builds for the K-DEMO considering a vertical maintenance scheme, are presented together with preliminary design parameters. © 2013 Elsevier B.V. All rights reserved.