Divertor tokamak operation at high densities on ASDEX Upgrade
- 1 December 1997
- journal article
- Published by IOP Publishing in Plasma Physics and Controlled Fusion
- Vol. 39 (12B) , B19-B38
- https://doi.org/10.1088/0741-3335/39/12b/003
Abstract
Densities achievable in ASDEX Upgrade discharges are restricted by a disruptive limit in the L-mode caused by an edge-power imbalance which is linking divertor detachment, Marfe formation and the separatrix density. The attainable average densities depend then on the internal particle sources and the core transport and can exceed the empirical Greenwald density. In H-mode an upper density limit is found which represents a non-disruptive H - L back transition, which is preceded by the occurrence of type-III ELMs. Close to the Greenwald limit this H - L transition cannot be avoided at any power flux across the separatrix and - at high external neutral gas fluxes - confinement compared with ITER H-92P scaling degrades even before the back transition. The H-mode operational window is determined by local edge-barrier parameters and their gradients, respectively. The boundaries are represented by the L - H transition-temperature threshold, the ideal ballooning edge-pressure gradient limit, the upper temperature limit for type-III ELMs and an upper H-mode barrier density limitation. The cause for the last limitation is not yet identified; it may be due to resistive ballooning modes or the separatrix density limit. Despite the limited edge densities the Greenwald density could be surpassed by a factor of three with pellet refuelling from the low magnetic-field side. Pellet injection from the high-field side gains from the strong increase of fuelling efficiency due to the assisting toroidal outward drift of the formed high- ablatant. Higher densities are achievable in H-mode compared with low-field side injection and diminished convective losses avoid confinement degradation up to the Greenwald density. In gas-puffed type-I ELMy H-modes the plasma thermal energy and the edge-pressure gradients, which are limited by ballooning stability, are linked via a robust temperature-profile stiffness and the flat density profiles resulting from dominant edge refuelling at high densities. Their confinement does not improve with increasing density (and neutral gas fluxes) and may even slightly degrade. Therefore, the superior confinement of type-I ELMy H-modes compared with type-III ELMy ones at medium densities is actually offset at densities close to the Greenwald density. In contrast to the temperature-profile resilience density profiles can be changed both by deep refuelling (with pellets) and intrinsic transport improvements connected with density peaking (observed in CDH-modes), which offers the combination of high confinement and high density operation. The possible alliance with radiation cooling, divertor detachment and divertor compatible type-III ELMs could solve the power exhaust problem.Keywords
This publication has 14 references indexed in Scilit:
- Investigation of physical processes limiting plasma density in high confinement mode discharges on DIII-DPhysics of Plasmas, 1997
- Electron temperature fluctuations in drift-resistive ballooning turbulencePhysics of Plasmas, 1997
- A scrape-off layer based model for Hugill-Greenwald type density limitsNuclear Fusion, 1997
- Three-dimensional computation of collisional drift wave turbulence and transport in tokamak geometryPlasma Physics and Controlled Fusion, 1997
- Observation of Continuous Divertor Detachment in-Mode Discharges in ASDEX UpgradePhysical Review Letters, 1995
- The ITER divertor conceptJournal of Nuclear Materials, 1995
- Improved confinement with edge radiative cooling at high densities and high heating power in TEXTORNuclear Fusion, 1994
- The H-Mode of ASDEXNuclear Fusion, 1989
- Disruptions in JETNuclear Fusion, 1989
- Control of particle and energy transport across the boundary of a Tokamak plasmaPlasma Physics and Controlled Fusion, 1984