Plasma and Fusion Research

Volume 11, 2405034 (2016)

Regular Articles


NITA Coil — Innovation for Enlarging the Blanket Space in the Helical Fusion Reactor
Nagato YANAGI, Takuya GOTO, Hitoshi TAMURA, Junichi MIYAZAWA and Akio SAGARA
National Institute for Fusion Science, 322-6 Oroshi-cho, Toki 509-5292, Japan
(Received 30 November 2015 / Accepted 2 February 2016 / Published 15 April 2016)

Abstract

An innovative idea is proposed for enlarging the blanket space on the inboard side of the torus for the helical fusion reactor FFHR-d1. A set of sub-helical coils, named NITA coils, with opposite-directed current outside the main helical coils, effectively reduces the helical pitch parameter and enlarges the blanket space. Dependence of the blanket space and plasma volume on the effective helical pitch parameter is examined. The obtained magnetic surfaces and their properties are compared with that of the original configuration.


Keywords

helical fusion reactor, FFHR-d1, optimization of heliotron magnetic configuration, blanket space, NITA coil

DOI: 10.1585/pfr.11.2405034


References

  • [1] A. Sagara, H. Tamura, T. Tanaka et al., Fusion Eng. Des. 89, 2114 (2014).
  • [2] A. Komori et al., Nucl. Fusion 49, 104015 (2009).
  • [3] H. Tamura, T. Goto, T. Tanaka et al., Fusion Eng. Des. 89, 2336 (2014).
  • [4] H. Tamura, T. Goto, N. Yanagi et al., Fusion Eng. Des. 88, 2033 (2013).
  • [5] A. Sagara, O. Mitarai, S. Imagawa et al., Fusion Eng. Des. 81, 2703 (2006).
  • [6] T. Morisaki, S. Imagawa, A. Sagara and O. Motojima, Fusion Eng. Des. 81, 2749 (2006).
  • [7] N. Yanagi, K. Nishimura, T. Goto et al., Contrib. Plasma Phys. 50, 661 (2010).
  • [8] T.Watanabe, N. Yanagi and A. Sagara, Plasma Fusion Res. 9, 3403089 (2014).
  • [9] T. Watanabe, private communication (presentation at NIFS Fusion Engineering Research Project meeting, July 2014).