Analysis of MHD stability and active mode control on KSTAR for high confinement, disruption-free plasma
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- Columbia Univ., New York, NY (United States)
- National Fusion Research Institute, Daejeon (Korea, Republic of)
- Fusion Theory and Computation, Inc., Kingston, WA (United States)
- Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Long-pulse plasma operation at high normalized beta, $$β_N$$, above the $$\textit{n}$$= 1 ideal MHD no-wall stability limit in KSTAR is presently limited by tearing instabilities rather than resistive wall modes. H-mode plasma operation during the recent KSTAR device campaign produced discharges having strong $$\textit{m/n}$$= 2/1 tearing instabilities at $$β_N$$ lower than the ideal MHD no-wall beta limit. The unstable tearing mode consequently reduced plasma confinement and toroidal plasma rotation significantly. We report the experiment confirmed that an extended duration of electron cyclotron heating (ECH) at the initial phase of the discharge plays a critical role in mode destabilization. To study destabilizing mechanisms that affect the mode growth, the stability of the observed tearing modes from plasmas with significantly different $$β_N$$ is computed by using the resistive DCON code and the M3D-C1code. Equilibrium reconstructions that include constraints from internal profile diagnostics, and computed fast particle pressure are used as input for reliable computation of stability. The classical tearing stability index, Δ', from resistive DCON is computed to be unstable when the island is fully saturated with large amplitude, while the unstable mode is not computed by M3D-C1. The modified Rutherford equation (MRE) describing the evolution of the island width has been constructed for KSTAR plasmas by using plasma parameters computed by the TRANSP code. The MRE model estimates a saturated island width corresponding to ~10% of the plasma minor radius for equilibrium at high $$β_N$$ 3 having a stable Δ' from the resistive DCON. In preparation for long-pulse plasma operation at higher beta utilizing increased plasma heating power, a resistive wall mode (RWM) active feedback control algorithm has been completed and enabled on KSTAR. To accurately determine the $$\textit{n}$$= 1component produced by RWMs, an algorithm has been developed that includes magnetic sensor compensation of the prompt applied field and the field from the induced current on the passive conductors. Use of multiple toroidal sensor arrays is enabled by modifying the sensor toroidal angles assumed in mode decomposition to include the effect of varied mode helicities in the outboard region where the mode measurement is made. This analysis on stability, transport, and control provides the required foundation for disruption prediction and avoidance research on KSTAR.
- Research Organization:
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Fusion Theory and Computation, Inc., Kingston, WA (United States)
- Sponsoring Organization:
- USDOE
- Grant/Contract Number:
- SC0016614; SC0016201
- OSTI ID:
- 1650665
- Alternate ID(s):
- OSTI ID: 1615129; OSTI ID: 1867819
- Journal Information:
- Nuclear Fusion, Vol. 60, Issue 5; ISSN 0029-5515
- Publisher:
- IOP ScienceCopyright Statement
- Country of Publication:
- United States
- Language:
- English
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