TY - JOUR
T1 - Empiricial scaling of inter-ELM power widths in ASDEX Upgrade and JET
AU - Eich, T.
AU - Sieglin, B.
AU - Scarabosio, A.
AU - Herrmann, A.
AU - Kallenbach, A.
AU - Matthews, G. F.
AU - Jachmich, S.
AU - Brezinsek, S.
AU - Rack, M.
AU - Goldston, Robert James
N1 - Funding Information:
The authors want to thank O. Kardaun, T. Pütterich and C. Lowry for support and discussions. In particular we thank A.W. Leonard and M. Makowski from DIII-D and J. Terry from Alcator C-Mod for highly valuable discussion. Further credit is paid to the support of the IR team in JET, i.e. S. Devaux, G. Arnoux and I. Balboa and P. de Marne from ASDEX Upgrade. This work was supported by EURATOM and carried out within the framework of the European Fusion Development Agreement. The views and opinions expressed herein do not necessarily reflect those of the European Commission.
PY - 2013
Y1 - 2013
N2 - The SOL power decay length (λq) deduced from analysis of fully attached divertor heat load profiles from two tokamaks, JET and ASDEX Upgrade with carbon plasma facing components, are presented. Interpretation of the target heat load profiles is performed by using a 1D-fit function which disentangles the upstream λq and an effective diffusion in the divertor (S), the latter essentially acting as a power spreading parameter in the divertor volume. It is shown that the so called integral decay length λint is approximately given by λint ≈ 1q +1:64 × S. An empirical scaling reveals parametric dependency λq/mm ≃ 0:9 · BT -0.7qcy1.2lP0 SOLR0geo for type-I ELMy H-modes. Extrapolation to ITER gives λq ≃1 mm. Recent measurements in JET-ILW and from ASDEX Upgrade full-W confirm the results. It is shown that a regression for the divertor power spreading parameter S is not yet possible due to the large effect of different divertor geometries of JET and ASDEX Upgrade Divertor-I and Divertor-IIb.
AB - The SOL power decay length (λq) deduced from analysis of fully attached divertor heat load profiles from two tokamaks, JET and ASDEX Upgrade with carbon plasma facing components, are presented. Interpretation of the target heat load profiles is performed by using a 1D-fit function which disentangles the upstream λq and an effective diffusion in the divertor (S), the latter essentially acting as a power spreading parameter in the divertor volume. It is shown that the so called integral decay length λint is approximately given by λint ≈ 1q +1:64 × S. An empirical scaling reveals parametric dependency λq/mm ≃ 0:9 · BT -0.7qcy1.2lP0 SOLR0geo for type-I ELMy H-modes. Extrapolation to ITER gives λq ≃1 mm. Recent measurements in JET-ILW and from ASDEX Upgrade full-W confirm the results. It is shown that a regression for the divertor power spreading parameter S is not yet possible due to the large effect of different divertor geometries of JET and ASDEX Upgrade Divertor-I and Divertor-IIb.
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U2 - 10.1016/j.jnucmat.2013.01.011
DO - 10.1016/j.jnucmat.2013.01.011
M3 - Article
AN - SCOPUS:84885473850
SN - 0022-3115
VL - 438
SP - S72-S77
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
IS - SUPPL
ER -