Recent Progress towards a Quantitative Description of Filamentary SOL Transport
Creators
- 1. Max-Planck-Institut für Plasmaphysik, Garching (Germany)
- 2. University of Vienna, 1010 Vienna (Austria)
- 3. Aalto University, Espoo (Finland)
Description
Full text: Heat and particle transport onto plasma-facing components is a key issue for next generation tokamaks, as it will determine the erosion levels and the heat loads at the main chamber first wall. In the scrape-off layer (SOL), this transport is thought to be dominated by the perpendicular convection of filaments. In this work, we present recent experiments which have led to an improved picture of filamentary transport, and its role on the onset of a density profile flattening, known in the literature as the density "shoulder". First, L-mode experiments carried out in the three tokamaks of the ITER stepladder (COMPASS, AUG and JET) showed how normalized divertor collisionality can be used to scale both filament size and the density e-folding length in the far SOL. Furthermore, a transition in the filament regime is found to be the reason for the formation of the density shoulder, as it coincided with a change in the scaling of filament size with propagation velocity from Sheath Limited regime to Inertial regime r3s. This result was later confirmed in AUG by independent experiments which showed how the polarization term in the charge conservation equation became dominant after the onset of the shoulder and how the transition was reversed as filaments propagate radially across regions of decreasing collisionality. Besides, measurements carried out in AUG with a Retarding Field Analyzer in equivalent discharges have led to the discovery of a strong reduction of Ti in the far SOL after the onset of the shoulder, both in filaments and background plasmas, which can not be explained by the minor reduction of Ti at the separatrix. Finally, equivalent experiments in H-mode carried out in AUG have shown howinter-ELM filaments followthe same general behaviour as L-mode filaments, and howa density profile flattening reminiscent of the density shoulder is observed when collisionality is increased over a similar threshold. Besides, Thomson Scattering data indicate the same sharp increase on the e-folding length of density and electron temperature in the near SOL above a critical collisionality. (author)
Additional details
Identifiers
Publishing Information
- Imprint Title
- 26. IAEA Fusion Energy Conference. Programme, Abstracts and Conference Material
- Imprint Pagination
- 935 p.
- Journal Page Range
- p. 173
- Report number
- IAEA-CN--234
Conference
- Title
- 26. IAEA Fusion Energy Conference
- Acronym
- FEC 2016
- Dates
- 17-22 Oct 2016
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49071830
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CHARGE CONSERVATION; COMPASS-D TOKAMAK; CONVECTION; DIVERTORS; EDGE LOCALIZED MODES; ELECTRON TEMPERATURE; EROSION; FILAMENTS; FIRST WALL; HEATING LOAD; H-MODE PLASMA CONFINEMENT; ITER TOKAMAK; JET TOKAMAK; L-MODE PLASMA CONFINEMENT; NEUTRAL-PARTICLE TRANSPORT; PLASMA SCRAPE-OFF LAYER; PLASMA SHEATH; POLARIZATION; THOMSON SCATTERING
- Descriptors DEC
- BOUNDARY LAYERS; CLOSED PLASMA DEVICES; CONFINEMENT; ENERGY TRANSFER; HEAT TRANSFER; INELASTIC SCATTERING; INSTABILITY; LAYERS; MAGNETIC CONFINEMENT; MASS TRANSFER; PLASMA CONFINEMENT; PLASMA INSTABILITY; PLASMA MACROINSTABILITIES; RADIATION TRANSPORT; SCATTERING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Notes
- Abstract only; 3 refs.
- Secondary number(s)
- IAEA-CN--234-0748