Plasma and Fusion Research

Volume 6, 2405110 (2011)

Regular Articles

Optimization of the Poloidal Field Coil System by Using an Integrated Design Code for Tokamak Fusion Reactors
Yuya MIYOSHI, Makoto NAKAMURA and Yuichi OGAWA
Department of Advanced Energy, Graduate School of Frontier Sciences, the University of Tokyo, Kashiwanoha 5-1-5, Kashiwa, Chiba 277-8561, Japan
(Received 7 December 2010 / Accepted 11 April 2011 / Published 27 July 2011)

Abstract

A platform for an integrated design code has been developed in which the detailed analysis codes for many components of a nuclear fusion reactor are compiled and incorporated into the system analysis code. Here we have introduced the lasma equilibrium code into the integrated design code in order to optimize the poloidal coil system. This makes it possible to evaluate the capability of the flux supply for ramping up the plasma current and the controllability of an elongated plasma owing to vertical stability. We calculated the margin for vertical stability for various positions of a passive conductor.

Keywords

integrated design code, automatic optimization, plasma equilibrium, vertical instability, passive conductor

DOI: 10.1585/pfr.6.2405110

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References

  • [1] R. Hiwatari et al., Nucl. Fusion 44, 106 (2004).
  • [2] R. Hiwatari et al., Nucl. Fusion 45, 96 (2005).
  • [3] Z. Dragojlovic et al., Fusion Eng. Des. 85, 243 (2010).
  • [4] M. Nakamura et al., J. Plasma Fusion Res. SERIES 9, 186 (2010).
  • [5] H. Fujieda et al., JAERI-M 08-256 (in Japanese) (1996).
  • [6] Summary of the ITER Final Design Report (2001).
  • [7] A. Fukuyama et al., JJAP 14, 871 (1975).
  • [8] S. Seki et al., JAERI-M 83-165 (in Japanese) (1983).
  • [9] G. Kurita et al., Fusion Eng. Des. 38, 417 (1998).

This paper may be cited as follows:

Yuya MIYOSHI, Makoto NAKAMURA and Yuichi OGAWA, Plasma Fusion Res. 6, 2405110 (2011).