High performance power handling in the absence of an H-mode edge in negative triangularity DIII-D plasmas

Journal Article · 16 July 2024 · Nuclear Fusion

DOI: https://doi.org/10.1088/1741-4326/ad5f41 · OSTI ID:2403613

Scotti, F. ; Marinoni, A.; McLean, A. G.; Paz-Soldan, C. ; Thome, K. E. ; Zhao, M. ; Allen, S.; Austin, M.; Burke, M. G.; Eldon, D. ; Fenstermacher, M. ; Hyatt, A.; Lasnier, C. J. ; Leonard, A. ; Lore, J. ; Nelson, A. O. ; Osborne, T.; Sauter, O. ; Truong, D.; Van Zeeland, M. A. ; Wang, H. Q. ; Wilcox, R.

Abstract Experiments performed during strongly-shaped high-power diverted negative triangularity (NT) experiments in DIII-D achieved detached divertor conditions and a transient-free edge, showcasing the potential for application of NT to a core-edge integrated reactor-like scenario and providing the first characterization of the parametric dependencies for detachment onset. Detached divertor conditions will be required in future devices to mitigate divertor heat fluxes. Access to dissipative divertor conditions was investigated via an increase in upstream density. Detachment onset at the outer strike point was achieved with H-mode level confinement $H_{98-y2}\sim 1$ and reactor-relevant normalized pressures ${\beta }_{\mathrm{N}}\sim 2$ . Confinement degradation was observed with deeper detachment, associated with the loss of an electron temperature pedestal. Differences in geometry, radial transport, impact of cross field drifts are discussed to explain differences in access to detachment in NT discharges. Higher normalized densities, with respect to equivalent discharges in positive triangularity, were necessary to achieve detachment, partially explained by the shorter parallel connection length to the targets. The effect of cross-field particle drifts ( E × B , B $\times \mathrm{\nabla }$ B ) on access to detachment was demonstrated by the lower upstream density needed to access detachment with ion B $\times \mathrm{\nabla }$ B drift directed outside of the active divertor (Greenwald fraction $f_{\mathrm{Gw}}\sim$ 0.9–1.0 vs $f_{\mathrm{Gw}}\sim$ 1.3). The upstream density at detachment onset was observed to increase linearly with plasma current with ion B $\times \mathrm{\nabla }$ B drift into the divertor, consistent with the observed narrowing of the scrape-off layer heat flux width λ _q . Edge fluid simulations capture separatrix densities needed to achieve detachment in NT plasma and their dependence on drift direction. The ability to reproduce detachment dynamics in NT plasma increases the confidence in future design studies for NT divertors.

• Sponsoring Organization: USDOE Office of Science (SC), Fusion Energy Sciences (FES)
• Grant/Contract Number: AC05-00OR22725
• OSTI ID: 2403613
• Alternate ID(s): OSTI ID: 2438830; OSTI ID: 2446967; OSTI ID: 2478918
• Journal Information: Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 9 Vol. 64; ISSN 0029-5515
• Publisher: IOP PublishingCopyright Statement
• Country of Publication: IAEA
• Language: English