Scrape-off layer radiation and heat load to the ASDEX Upgrade LYRA divertor
- 1 July 1999
- journal article
- Published by IOP Publishing in Nuclear Fusion
- Vol. 39 (7) , 901-917
- https://doi.org/10.1088/0029-5515/39/7/307
Abstract
In 1997 the new `LYRA' divertor went into operation at ASDEX Upgrade and, in parallel, the neutral beam heating power was increased to 20 MW by installation of a second injector leading to a P/R value of 12 MW/m. Experiments have shown that the ASDEX Upgrade LYRA divertor is capable of handling such high heating powers. There is an overall reduction of the maximum heat flux in the LYRA divertor by about a factor of 2 compared with the previous open divertor Div I. This reduction is mainly due to increased radiative losses inside the divertor region, which are caused by an effective reflection of hydrogen neutrals into the hot separatrix region. The main channel of radiative loss is carbon radiation, which cools the divertor plasma down to a few electronvolts, where hydrogen radiation losses become significant. The radiative losses preferentially reduce the power flux at the separatrix, leading to early detachment around the strike point position. With increasing density, the detached region extends upwards on the vertical target. The power fraction radiated in the LYRA divertor is around 45% and nearly independent of the heating power. This value is a factor of 2 higher than the typical radiation fraction in Div I. B2-EIRENE modelling of the performed experiments supports the experimental finding and refines the understanding of loss processes in the divertor region.Keywords
This publication has 27 references indexed in Scilit:
- ITER overviewNuclear Fusion, 1999
- Spectroscopic investigation of the dynamics of ions and neutrals in the ASDEX Upgrade Divertor IIJournal of Nuclear Materials, 1999
- Noble gas exhaust with a strongly baffled divertor in ASDEX-UpgradeJournal of Nuclear Materials, 1999
- Survey of target plate heat flux in diverted DIII-D tokamak dischargesNuclear Fusion, 1998
- Pressure driven high-n/high-mtearing modes in low shear regions with high pressure gradients and high resistivityNuclear 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
- Partially detached radiative divertor with active divertor pumpingNuclear Fusion, 1997
- H mode power threshold database for ITERNuclear Fusion, 1996
- Observation of Continuous Divertor Detachment in-Mode Discharges in ASDEX UpgradePhysical Review Letters, 1995
- Energy flux to the ASDEX-Upgrade diverter plates determined by thermography and calorimetryPlasma Physics and Controlled Fusion, 1995