Effect of divertor geometry on boundary and core plasma performance in ASDEX Upgrade and JET
- 1 January 1999
- journal article
- Published by IOP Publishing in Plasma Physics and Controlled Fusion
- Vol. 41 (3A) , A401-A408
- https://doi.org/10.1088/0741-3335/41/3a/032
Abstract
A key element in future toroidal magnetic fusion machines like ITER is the design of a divertor, which allows for safe particle and power exhaust in parallel with high bulk plasma performance. Correspondingly, the definition and design of an optimized divertor is a major task within the ongoing international ITER research and development effort. In order to provide a profound physics basis for such a divertor optimization, different divertor geometries are being tested on major tokamaks. This paper describes the effects of these divertor modifications on plasma performance in ASDEX Upgrade and in JET. In conclusion, increasing closure improves divertor performance without limiting the core plasma performance in ELMy H-modes.Keywords
This publication has 8 references indexed in Scilit:
- Plasma detachment in JET Mark I divertor experimentsNuclear Fusion, 1998
- Identification of plasma-edge-related operational regime boundaries and the effect of edge instability on confinement in ASDEX UpgradePlasma Physics and Controlled Fusion, 1997
- High density operation close to Greenwald limit and H mode limit in ASDEX upgradeNuclear Fusion, 1997
- Particle exhaust studies in ASDEX UpgradePlasma Physics and Controlled Fusion, 1997
- Particle exhaust in radiative divertor experimentsJournal of Nuclear Materials, 1997
- The ITER divertor conceptJournal of Nuclear Materials, 1995
- Analysis of cold divertor concepts for ITERJournal of Nuclear Materials, 1995
- Physics of edge plasmas in enhanced confinement modesJournal of Nuclear Materials, 1995