Analysis of the H-mode density limit in the ASDEX upgrade tokamak using bolometry
Description
The high confinement mode (H-mode) is the operational scenario foreseen for ITER, DEMO and future fusion power plants. At high densities, which are favourable in order to maximize the fusion power, a back transition from the H-mode to the low confinement mode (L-mode) is observed. This H-mode density limit (HDL) occurs at densities on the order of, but below, the Greenwald density. In this thesis, the HDL is revisited in the fully tungsten walled ASDEX Upgrade tokamak (AUG). In AUG discharges, four distinct operational phases were identified in the approach towards the HDL. First, there is a stable H-mode, where the plasma density increases at steady confinement, followed by a degrading H-mode, where the core electron density is fixed and the confinement, expressed as the energy confinement time, reduces. In the third phase, the breakdown of the H-mode and transition to the L-mode, the overall electron density is fixed and the confinement decreases further, leading, finally, to an L-mode, where the density increases again at a steady confinement at typical L-mode values until the disruptive Greenwald limit is reached. These four phases are reproducible, quasi-stable plasma regimes and provide a framework in which the HDL can be further analysed. Radiation losses and several other mechanisms, that were proposed as explanations for the HDL, are ruled out for the current set of AUG experiments with tungsten walls. In addition, a threshold of the radial electric field or of the power flux into the divertor appears to be responsible for the final transition back to L-mode, however, it does not determine the onset of the HDL. The observation of the four phases is explained by the combination of two mechanisms: a fueling limit due to an outward shift of the ionization profile and an additional energy loss channel, which decreases the confinement. The latter is most likely created by an increased radial convective transport at the edge of the plasma. It is shown that the four phases occur due to a coupling of these two mechanisms. These observations are in line with studies made at AUG with carbon walls, although in those discharges the energy loss was most likely caused by the full detachment of the divertor. The density of the HDL depends only weakly on the plasma current, unlike the Greenwald limit, and can be increased by high heating power, again unlike the Greenwald limit. The triangularity of the plasma has no influence on the density of the HDL, though improves the performance of the plasma, since the onset of the degrading H-mode phase occurs at higher densities. It is explicitly shown that the HDL and also the L-mode density limit are determined by edge parameters. Using pellet fueling, centrally elevated density profiles above the Greenwald limit can be achieved in stable H-modes at a moderate confinement. Future tokamaks will have intrinsic density peaking. Consequently, they will most likely operate in H-modes above the Greenwald limit.
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45052019.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 131 p.
- Report number
- INIS-DE--1577
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 45052019
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- ASDEX TOKAMAK; CHARGE EXCHANGE; COLLISIONAL PLASMA; COLLISIONS; CONVECTION; ELECTRIC DISCHARGES; ELECTRON DENSITY; ENERGY LOSSES; H-MODE PLASMA CONFINEMENT; L-MODE PLASMA CONFINEMENT; MARFE; PLASMA DENSITY; SCALING LAWS; TUNGSTEN
- Descriptors DEC
- CLOSED PLASMA DEVICES; CONFINEMENT; ELEMENTS; ENERGY TRANSFER; HEAT TRANSFER; LOSSES; MAGNETIC CONFINEMENT; MASS TRANSFER; METALS; PLASMA; PLASMA CONFINEMENT; REFRACTORY METALS; THERMONUCLEAR DEVICES; TOKAMAK DEVICES; TRANSITION ELEMENTS