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icc2011_asai_mod.pdf2011-08-18 18:54:47Tomohiko Asai

New control methods for stabilization and equilibrium of a field-reversed configuration

Author: Tomohiko Asai
Requested Type: Consider for Invited
Submitted: 2011-06-10 09:54:32

Co-authors: H. Matsunaga, Y. Fujikawa, Y. Matsuzawa, Ts. Takahashi, H. Itagaki, M. Inomoto, To. Takahashi, L.C. Steinhauer

Contact Info:
Nihon University
1-8 Kanda-Surugadai
Tokyo, Tokyo   101-830

Abstract Text:
Control methods for a field-reversed configuration (FRC) have been proposed and investigated on the NUCTE series theta-pinch based FRC devices. The FRC has been investigated as a candidate for a highly efficient fusion reactor core with several unique advantages such as simply-connected magnetic geometry, all the equilibrium current maintained by classical diamagnetism, open field region as a natural diverter and high mobility along the geometrical axis. However, these nature of FRC make it difficult to apply additional control methods such as inductive current drive. Therefore, several new control methods have been proposed and developed on NUCTEs. In the translation process, “equivalent neutral beam injection” has been tried. The neutral particles injected into the FRC with relative velocity could fuel and heat the FRC plasma. Improvement of the particle and poloidal flux confinements and delay of onset of n = 2 rotational instability were observed in the translation process [1]. Also the coaxial helicity injection has been tried into the elongated theta-pinch FRC [2]. Injected modest amount of helicity stabilize rotational mode deformation with toroidal mode number n = 2. Moreover, newly built FRC facility named FAT (FRC amplification via translation/transformer) will be presented. This device has “fat” translation chamber with 800mm in diameter and 1000mm in length. Therefore, high-beta, high-density elongated theta-pinch FRC is transited into oblate shape in the translation process. Topological transition from simply-connected to torus has also been tried to install a center solenoid for ohmic current drive and poloidal flux build-up.

[1] Y. Matsuzawa et al., Phys. Plasmas 15, 082504 (2008).
[2] T. Asai et al., in 23rd IAEA Fusion Energy Conference, ICC/P5-01 (2010).

Characterization: A2,D3


University of Washington

Workshop on Innovation in Fusion Science (ICC2011) and
US-Japan Workshop on Compact Torus Plasma
August 16-19, 2011
Seattle, Washington

ICC 2011