Abstract
One of the most severe problems for fusion reactors is the power load on the divertor target plates. Technically only power loads of less than 10 MW m-2 are acceptable. However, strong edge localized mode (ELM) activity can lead to power loads in excess of 800 MW m-2. In order to reduce the steady-state heat flux and the transient heat flux due to ELMs, radiation cooling experiments were performed at JET. Nitrogen was puffed into the divertor up to a radiative power fraction of 90%. This was achieved at a density of 0.85 times the Greenwald density (Greenwald M 1988 Nucl. Fusion 28 2199), while maintaining an H-factor of fH98 = 0.82. The Zeff in all those discharges stayed around 2.0. At approximately 55% radiative power fraction, the ELM characteristic changes from type I to type III, resulting in a loss of confinement of about 25% due to a degradation of the edge pedestal and hence a reduction of the ELM power load to the divertor tiles. By increasing the radiative power fraction to values of about 90%, the heat flux is reduced to 2 MW m-2.
Original language | English |
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Article number | 302 |
Pages (from-to) | 639-652 |
Number of pages | 14 |
Journal | Plasma Physics and Controlled Fusion |
Volume | 44 |
Issue number | 6 |
DOIs | |
State | Published - Jun 2002 |
Externally published | Yes |
Event | IAEA Technical Committee Meeting on Divertor Concepts - Aix-en-Provence, France Duration: Sep 11 2001 → Sep 14 2001 |