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

T. Eich; B. Sieglin; A. Scarabosio; A. Herrmann; A. Kallenbach; G. F. Matthews; S. Jachmich; S. Brezinsek; M. Rack; Robert James Goldston

doi:10.1016/j.jnucmat.2013.01.011

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

T. Eich, B. Sieglin, A. Scarabosio, A. Herrmann, A. Kallenbach, G. F. Matthews, S. Jachmich, S. Brezinsek, M. Rack, Robert James Goldston

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76 Scopus citations

Abstract

The SOL power decay length (λ_q) 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 λ_q 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 λ_int is approximately given by λ_int ≈ 1_q +1:64 × S. An empirical scaling reveals parametric dependency λ_q/mm ≃ 0:9 · B_T ^-0.7q_cy^1.2_lP⁰ _SOLR⁰_geo for type-I ELMy H-modes. Extrapolation to ITER gives λ_q ≃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.

Original language	English (US)
Pages (from-to)	S72-S77
Journal	Journal of Nuclear Materials
Volume	438
Issue number	SUPPL
DOIs	https://doi.org/10.1016/j.jnucmat.2013.01.011
State	Published - 2013

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
General Materials Science
Nuclear Energy and Engineering

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10.1016/j.jnucmat.2013.01.011

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@article{d938d31a97884a12976e42a05d5fbe57,

title = "Empiricial scaling of inter-ELM power widths in ASDEX Upgrade and JET",

abstract = "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.",

author = "T. Eich and B. Sieglin and A. Scarabosio and A. Herrmann and A. Kallenbach and Matthews, {G. F.} and S. Jachmich and S. Brezinsek and M. Rack and Goldston, {Robert James}",

note = "Funding Information: The authors want to thank O. Kardaun, T. P{\"u}tterich 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. ",

year = "2013",

doi = "10.1016/j.jnucmat.2013.01.011",

language = "English (US)",

volume = "438",

pages = "S72--S77",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier B.V.",

number = "SUPPL",

}

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 -

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

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