### Session JI2: Edge and Divertor Physics

2:00 PM–5:00 PM, Tuesday, November 9, 2010
Room: Grand Ballroom CD

Chair: Anthony Leonard, General Atomics

Abstract ID: BAPS.2010.DPP.JI2.2

### Abstract: JI2.00002 : Taming the Plasma Material Interface with the Snowflake'' Divertor in NSTX

2:30 PM–3:00 PM

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#### Author:

Vsevolod Soukhanovskii
(Lawrence Livermore National Laboratory)

Recent results from NSTX provide support to the innovative snowflake'' divertor (SFD) configuration [1] as a promising plasma-material interface (PMI) concept for future magnetic fusion energy devices, through the demonstration of the SFD with significant divertor peak heat flux reduction and impurity control simultaneously with good H-mode confinement. In ITER and future tokamaks, the divertor PMI must be able to exhaust steady-state heat fluxes up to 10 MW/m$^{2}$ with minimal material erosion. In spherical tokamaks, these requirements are aggravated by the inherently compact divertor geometry. The SFD uses a second-order null-point created by bringing in close proximity two first-order X-points of the standard divertor configuration. The SFD configuration was obtained in NSTX with two divertor magnetic coils controlled in real time. Experiments in NSTX conducted in 0.8 MA 4-6 MW NBI-heated discharges qualitatively confirmed the SFD properties predicted by analytic theory and 2D multi-fluid edge transport modeling with the UEDGE code [1, 2]. When compared to the standard divertor geometry, the SFD in NSTX showed an increase in plasma-wetted area by 100-200 {\%} and an increased divertor volume (with X-point connection length increased by 50-100{\%}). Partial detachment of the outer strike point region (first $\sim$2-3 mm of the scrape-off layer width 6-7 mm mapped to midplane) was evident through a significant reduction of the peak divertor heat flux, a 100{\%} increase in divertor plasma radiation, and formation of a zone with $T_{e}$ =0.8-1.2 eV, $n_{e}$ =2-6x10$^{20}$m$^{-3}$, resulting in significant recombination and volumetric momentum losses. Core carbon inventory and radiated power were reduced by up to 70{\%}, apparently as a result of reduced divertor physical and chemical sputtering in the SFD. \\[4pt] [1] D. D. Ryutov, Phys. Plasmas \textbf{14}, 64502 (2007). \\[0pt] [2] M. V. Umansky \textit{et al}., Nucl. Fusion \textbf{49}, 075005 (2009).

To cite this abstract, use the following reference: http://meetings.aps.org/link/BAPS.2010.DPP.JI2.2