Drift-based Model for Power Scrape-off Width in Low-Gas-Puff H-mode Plasmas: Theory and Implications
Description
Full text: A heuristic model for the plasma scrape-off width in low-gas-puff tokamak H-mode plasmas is introduced. ∇B and curvature drifts into the scrape-off layer (SOL) are balanced against near-sonic parallel flows out of the SOL, to the divertor plates. These assumptions result in an estimated SOL width of order the poloidal gyroradius. It is next assumed that anomalous perpendicular electron thermal diffusivity is the dominant source of heat flux across the separatrix, investing the SOL width, derived above, with heat from the main plasma. The separatrix temperature is then calculated based on a two-point model balancing power input to the SOL with Spitzer-Hiarm parallel thermal conduction losses to the divertor. This results in a heuristic closed-form prediction for the power scrape-off width that is in quantitative agreement both in absolute magnitude and in scaling with recent experimental data. The applicability of the Spitzer-Harm model to this regime can be questioned at the lowest densities, where the presence of a sheath can raise the divertor target electron temperature. A more general two-point model including a finite ratio of divertor target to upstream electron temperature shows only a 5% effect on the SOL width with target temperature fT = 75% of upstream, so this effect is likely negligible in experimentally relevant regimes. To achieve the near-sonic flows measured experimentally, and assumed in this model, sets requirements on the ratio of upstream to total SOL particle sources relative to the square-root of the ratio of target to upstream temperature. As a result very high recycling regimes may allow significantly wider power fluxes. The Pfisch-Schluter model for equilibrium flows has been modified to allow near-sonic flows, appropriate for gradient scale lengths of order the poloidal gyroradius. This results in a new quadrupole flow pattern that amplifies the usual P-S flows at the outer midplane, while reducing them at the inner. The strong parallel flows and plasma charging implied by this model suggest a mechanism for H-mode transition, consistent with the observation that LSN divertors have lower power threshold and the JT-60 divertor did not accommodate H-mode. These results suggest that ITER may need to operate at least transiently in the low SOL regime presented here in order to achieve H-mode transition. (author)
Additional details
Publishing Information
- Imprint Title
- 24. IAEA Fusion Energy Conference. Programme and Book of Abstracts
- Imprint Pagination
- 789 p.
- Journal Page Range
- p. 366
- Report number
- IAEA-CN--197
Conference
- Title
- 24. IAEA Fusion Energy Conference
- Acronym
- FEC 2012
- Dates
- 8-13 Oct 2012
- Place
- San Diego, CA (United States)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 44095074
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BALANCES; COMPUTERIZED SIMULATION; DIVERTORS; ELECTRON TEMPERATURE; EQUILIBRIUM; HEAT FLUX; H-MODE PLASMA CONFINEMENT; ITER TOKAMAK; JT-60 TOKAMAK; LOSSES; PLASMA; PLASMA SCRAPE-OFF LAYER; POWER INPUT; RECYCLING; SCALING; THERMAL CONDUCTION; THERMAL DIFFUSIVITY; TRANSIENTS
- Descriptors DEC
- BOUNDARY LAYERS; CLOSED PLASMA DEVICES; CONFINEMENT; ENERGY TRANSFER; HEAT TRANSFER; LAYERS; MAGNETIC CONFINEMENT; MEASURING INSTRUMENTS; PHYSICAL PROPERTIES; PLASMA CONFINEMENT; SIMULATION; THERMODYNAMIC PROPERTIES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; WEIGHT INDICATORS
Optional Information
- Secondary number(s)
- TH/P4--19