Analysis of drift effects on the tokamak power scrape-off width using SOLPS-ITER
- College of William and Mary, Williamsburg, VA (United States)
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Peter the Great St. Petersburg Polytechnic Univ., St. Petersburg (Russia)
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
SOLPS-ITER, a comprehensive 2D scrape-off layer modeling package, is used to examine the physical mechanisms that set the scrape-off width ($${{\lambda}_{q}}$$ ) for inter-ELM power exhaust. Guided by Goldston's heuristic drift (HD) model, which shows remarkable quantitative agreement with experimental data, this research examines drift effects on $${{\lambda}_{q}}$$ in a DIII-D H-mode magnetic equilibrium. As a numerical expedient, a low target recycling coefficient of 0.9 is used in the simulations, resulting in outer target plasma that is sheath limited instead of conduction limited as in the experiment. Scrape-off layer (SOL) particle diffusivity (DSOL) is scanned from 1 to 0.1 m2 s–1. Across this diffusivity range, outer divertor heat flux is dominated by a narrow (~3–4mm when mapped to the outer midplane) electron convection channel associated with thermoelectric current through the SOL from outer to inner divertor. An order-unity up–down ion pressure asymmetry allows net ion drift flux across the separatrix, facilitated by an artificial mechanism that mimics the anomalous electron transport required for overall ambipolarity in the HD model. At $${{D}_{\text{SOL}}}=0.1$$ m2 s–1, the density fall-off length is similar to the electron temperature fall-off length, as predicted by the HD model and as seen experimentally. Furthermore, this research represents a step toward a deeper understanding of the power scrape-off width, and serves as a basis for extending fluid modeling to more experimentally relevant, high-collisionality regimes.
- Research Organization:
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Sponsoring Organization:
- USDOE Office of Science (SC), Fusion Energy Sciences (FES)
- Grant/Contract Number:
- SC0010434
- OSTI ID:
- 1335693
- Alternate ID(s):
- OSTI ID: 1330720
- Journal Information:
- Plasma Physics and Controlled Fusion, Vol. 58, Issue 12; ISSN 0741-3335
- Publisher:
- IOP ScienceCopyright Statement
- Country of Publication:
- United States
- Language:
- English
Web of Science
Similar Records
On the role of finite grid extent in SOLPS-ITER edge plasma simulations for JET H-mode discharges with metallic wall
Simulations of tokamak boundary plasma turbulence transport in setting the divertor heat flux width