Published December 1997 | Version v1
Journal article

Divertor tokamak operation at high densities on ASDEX Upgrade

  • 1. Max-Planck-Institut fuer Plasmaphysik, EURATOM-IPP Association, Garching and Berlin, POB 1533, D-85740 Garching (Germany)

Description

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. (author)

Additional details

Publishing Information

Journal Title
Plasma Physics and Controlled Fusion (Online)
Journal Volume
39
Journal Issue
12B
Journal Page Range
p. B19-B38
ISSN
1361-6587

Conference

Title
24. European Physical Society conference on controlled fusion and plasma physics
Dates
9-13 Jun 1997
Place
Berchtesgaden (Germany)

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
43113902
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ASDEX TOKAMAK; DIVERTORS; EDGE LOCALIZED MODES; HIGH-BETA PLASMA; H-MODE PLASMA CONFINEMENT; L-MODE PLASMA CONFINEMENT; MARFE; PLASMA DISRUPTION; REVIEWS
Descriptors DEC
CLOSED PLASMA DEVICES; CONFINEMENT; DOCUMENT TYPES; INSTABILITY; MAGNETIC CONFINEMENT; PLASMA; PLASMA CONFINEMENT; PLASMA INSTABILITY; PLASMA MACROINSTABILITIES; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information

Notes
30 refs; This record replaces 31048858