Simulations of tokamak boundary plasma turbulence transport in setting the divertor heat flux width
- 1. Lawrence Livermore National Laboratory, Livermore, CA 94550 (United States)
- 2. University of Science and Technology of China, Hefei (China)
Description
The BOUT + + code has been used to simulate edge plasma electromagnetic (EM) turbulence and transport, and to study the role of EM turbulence in setting the scrape-off layer (SOL) heat flux width λ q. More than a dozen tokamak discharges from C-Mod, DIII-D, EAST, ITER and CFETR have been simulated with encouraging success. The parallel electron heat fluxes onto the target from the BOUT + + simulations of C-Mod, DIII-D, and EAST follow the experimental heat flux width scaling of the inverse dependence on the poloidal magnetic field. Further turbulence statistics analysis shows that the blobs are generated near the pedestal pressure peak gradient region inside the separatrix and contribute to the transport of the particle and heat in the SOL region. Transport simulations indicate two distinct regimes: drift dominant regime and turbulence dominant regime. Goldston's heuristic drift-based (HD) model yields a consistent divertor heat flux width in the drift dominant regime. For C-Mod enhanced D α H-mode discharges, drifts and turbulence are competing in setting the divertor heat flux width, possibly due to its compact machine size and good pedestal confinement.
The simulations for ITER and CFETR indicate that divertor heat flux width λ q of the future machines may no longer follows the 1/B pol,OMP HD-based empirical (Eich) scalings and the HD model gives a pessimistic limit of divertor heat flux width. The simulation results show a transition from a drift dominant regime to a turbulence dominant regime from current machines to future machines such as ITER and CFETR for two reasons. (1) The magnetic drift-based radial transport decreases due to large CFETR and ITER machine sizes. (2) The SOL turbulence thermal diffusivity increases due to larger turbulent fluxes ejected from the pedestal into the SOL when operating in a different pedestal structure, from an ELM-free H-mode pedestal regime to a small and grassy ELM regime. (paper)
Availability note (English)
Available from http://dx.doi.org/10.1088/1741-4326/ab430dAdditional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Fusion
- Journal Volume
- 59
- Journal Issue
- 12
- Journal Page Range
- [11 p.]
- ISSN
- 0029-5515
- CODEN
- NUFUAU
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51094002
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- DIVERTORS; DOUBLET-3 DEVICE; EDGE LOCALIZED MODES; HEAT FLUX; H-MODE PLASMA CONFINEMENT; ITER TOKAMAK; MAGNETIC FIELDS; PLASMA SCRAPE-OFF LAYER; SIMULATION; SOLS; THERMAL DIFFUSIVITY; TURBULENCE; WIDTH
- Descriptors DEC
- BOUNDARY LAYERS; CLOSED PLASMA DEVICES; COLLOIDS; CONFINEMENT; DIMENSIONS; DISPERSIONS; INSTABILITY; LAYERS; MAGNETIC CONFINEMENT; PHYSICAL PROPERTIES; PLASMA CONFINEMENT; PLASMA INSTABILITY; PLASMA MACROINSTABILITIES; THERMODYNAMIC PROPERTIES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS