Abstract
A database with attached, partially detached and completely detached divertors has been constructed in ASDEX Upgrade discharges in both H-mode and L-mode plasmas with Thomson Scattering data suitable for the analysis of the upstream SOL electron profiles. By comparing upstream temperature decay width, λTe,u, l with the scaling of the SOL power decay width, λq e,le based on the downstream IR measurements, it is found that a simple relation based on classical electron conduction can relate λTe,u l and λq e le well. The combined dataset can be described by both a single scaling and a separate scaling for H-modes and L-modes. For the single scaling, a strong inverse dependence of, λTe,u l on the separatrix temperature, λTe,u, is found, suggesting the classical parallel SpitzerHarm conductivity as dominant mechanism controlling the SOL width in both L-mode and H-mode over a large set of plasma parameters. This dependence on λTe,u explains why, for the same global plasma parameters, λq e le in L-mode is approximately twice that in H-mode and under detached conditions, the SOL upstream electron profile broadens when the density reaches a critical value. Comparing the derived scaling from experimental data with power balance, gives the cross-field thermal diffusivity as X⊥ ∞e1/2 consistent with earlier studies on Compass-D, JET and Alcator C-Mod. However, the possibility of the separate scalings for different regimes cannot be excluded, which gives results similar to those previously reported for the H-mode, but here the wider SOL width for L-mode plasmas is explained simply by the larger premultiplying coefficient. The relative merits of the two scalings in representing the data and their theoretical implications are discussed.
Original language | English |
---|---|
Article number | 105010 |
Journal | Plasma Physics and Controlled Fusion |
Volume | 59 |
Issue number | 10 |
DOIs | |
State | Published - Aug 22 2017 |
Externally published | Yes |
Funding
This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the European Union’s Horizon 2020 research and innovation programme under grant agreement number 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission.
Funders | Funder number |
---|---|
Horizon 2020 Framework Programme | 633053 |
Horizon 2020 Framework Programme |
Keywords
- attached and detached divertor
- SOL decay width
- tokamak