S. Ohdachi1, J. Varela1, K. Y. Watanabe1, H. Nakano1, 2, H. Takahashi1, 2, Y. Suzuki1, 2, Y. Narushima1, 21, T. Bando2, X. D. Du3, T. Morisaki1, 2, and the LHD Experiment Group1
1National Institute for Fusion Science, 322-6, Oroshi-cho, Toki, Japan
2The Graduate University for Advanced Studies, 322-6, Oroshi-cho, Toki, Japan
3General Atomics, PO Box 85608, San Diego, CA 92186-5608, USA
The suppression of the energetic particle (EP) driven mode is essential for the realization of the fusion reactor. Modification of the local plasma parameters, based on the stability analysis using FAR3D, successfully suppresses the EP driven interchange mode observed in the Large Helical Device (LHD). The achieved temperature is thereby improved significantly. Control of the EP driven interchange mode by the RMP application is demonstrated as well.
To be appeared in the IAEA site.