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Title: SOL effects on the pedestal structure in DIII-D discharges

Journal Article · · Nuclear Fusion

SOLPS analysis explains the differences in pedestal structure associated with different ion ∇B drift directions in DIII-D. Core transport models predict that fusion power scales roughly as the square of the pressure at the top of the pedestal, so understanding the effects that determine pedestal structure in steady-state operational scenarios is important to projecting scenarios developed in DIII-D to ITER and other devices. Both experiments and modeling indicate that scrape off layer (SOL) conditions are important in optimizing the pedestal structure for high-beta steady-state scenarios. The SOLPS code is used to provide interpretive analysis of the pedestal and SOL to examine the nature of flows and fueling on the pedestal structure including the effects of drifts in the fluid model. This analysis shows that flows driven by the ion ∇B drift are outward when this drift is toward the x-point in a single-null divertor configuration (favorable ∇B direction for reduced H-mode power threshold), and inward when the drift is away from the x-point (unfavorable ∇B direction). It is hypothesized that these flows decrease the density gradient in the pedestal in the favorable direction, thereby stabilizing the kinetic ballooning mode (KBM) and increasing the pedestal width. Comparisons of pedestal structures in similarly shaped DIII-D steady-state plasmas confirm this change, showing increased density pedestal width and lower peak density and lower separatrix density with the favorable drift direction. The pedestal temperature is higher in the lower density case, resulting in an increased pedestal pressure, which indicates that the increased particle flux does not significantly degrade energy confinement. Modeling of cases with constant ∇B drift direction but changing between the more open lower divertor and more closed upper divertor show that there is increased fueling inside the pedestal with the more open geometry. As a result, the pedestal fueling rate for both attached and detached cases is always lower with more closed divertor geometry than in any cases with more open geometry.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); General Atomics, San Diego, CA (United States)
Sponsoring Organization:
USDOE
Grant/Contract Number:
AC05-00OR22725; FC02-04ER54698
OSTI ID:
1394293
Alternate ID(s):
OSTI ID: 1373410
Journal Information:
Nuclear Fusion, Vol. 57, Issue 7; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 17 works
Citation information provided by
Web of Science

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Cited By (6)

DIII-D research towards establishing the scientific basis for future fusion reactors journal June 2019
Effect of carbon and tungsten plasma-facing materials on the divertor and pedestal plasma in EAST journal October 2019
Effects of divertor geometry on H-mode pedestal structure in attached and detached plasmas in the DIII-D tokamak journal July 2018
Predicting the rotation profile in ITER journal January 2020
Progress of physics understanding for long pulse high-performance plasmas on EAST towards the steady-state operation of ITER and CFETR journal December 2019
Integrated operation of steady-state long-pulse H-mode in Experimental Advanced Superconducting Tokamak journal July 2019