Empiricial scaling of inter-ELM power widths in ASDEX Upgrade and JET

被引:77
作者
Eich, T. [1 ]
Sieglin, B. [1 ]
Scarabosio, A. [1 ]
Herrmann, A. [1 ]
Kallenbach, A. [1 ]
Matthews, G. F. [2 ]
Jachmich, S. [3 ]
Brezinsek, S. [4 ]
Rack, M. [4 ]
Goldston, R. J. [5 ]
机构
[1] EURATOM, Max Planck Inst Plasmaphys, D-85748 Garching, Germany
[2] EURATOM CCFE Assoc, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[3] EURATOM, ERM KMS, Brussels, Belgium
[4] EURATOM, Forschungszentrum Julich, IEK 4, Julich, Germany
[5] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
基金
英国工程与自然科学研究理事会;
关键词
DIVERTOR; DISCHARGES; PHYSICS; REGIME;
D O I
10.1016/j.jnucmat.2013.01.011
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The SOL power decay length (kq) 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 kq 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 kint is approximately given by lambda(int) approximate to lambda q + 1.64 x S. An empirical scaling reveals parametric dependency lambda q/mm similar or equal to 0: 9 B-T(-0.7) q(cyt)(1.2) R-geo(0) for type-I ELMy H-modes. Extrapolation to ITER gives kq ' 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. (C) 2013 Euratom. Published by Elsevier B. V. All rights reserved.
引用
收藏
页码:S72 / S77
页数:6
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