Recent accomplishments and future plans of ASDEX Upgrade

V. Mertens; R. Dux; G. Gantenbein; O. Gruber; S. Günter; J. Hobirk; L. Horton; V. Igochine; A. Kallenbach; P. T. Lang; F. Leuterer; C. F. Maggi; A. Manini; M. Maraschek; A. Mück; R. Neu; J. M. Noterdaeme; G. Pautasso; A. C.C. Sips; A. Stäbler; J. Stober; D. Wagner; H. Zohm

doi:10.1109/FUSION.2005.252853

Recent accomplishments and future plans of ASDEX Upgrade

V. Mertens, R. Dux, G. Gantenbein, O. Gruber, S. Günter, J. Hobirk, L. Horton, V. Igochine, A. Kallenbach, P. T. Lang, F. Leuterer, C. F. Maggi, A. Manini, M. Maraschek, A. Mück, R. Neu, J. M. Noterdaeme, G. Pautasso, A. C.C. Sips, A. StäblerJ. Stober, D. Wagner, H. Zohm

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

Abstract

ASDEX Upgrade has demonstrated clear progress in ITER relevant plasma operation scenarios. Successful operation with about 70% Tungsten clad first wall is shown. The operation space of the improved H-mode (advanced tokamak scenario) is enlarged in safety factor 3≤q95≥5 and density 0.4≤n _e/nGw≥0.9. The performance can clearly exceed the ITER reference value. At high densities type-II ELMs mitigate the peak power load in the divertor. A similar effect is achieved by increasing the type-I ELM frequency by shallow pellet injection or cyclic vertical plasma motion. Off-axis neutral beam current drive leads at low powers to a clear current density profile modification. Sawtooth tailoring by electron cyclotron current drive (ECCD) can prevent the growth of neoclassical tearing modes (NTM). (3,2) and (2,1) NTMs excited at high plasma pressure can be stabilized by ECCD at moderate power levels. Narrow ECCD absorption profiles are more effective than broad ones.

Original language	English
Title of host publication	21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05
DOIs	https://doi.org/10.1109/FUSION.2005.252853
State	Published - 2006
Externally published	Yes
Event	21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05 - Knoxville, TN, United States Duration: 26 Sep 2005 → 29 Sep 2005

Publication series

Name	Proceedings - Symposium on Fusion Engineering

Conference

Conference	21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05
Country/Territory	United States
City	Knoxville, TN
Period	26/09/05 → 29/09/05

Keywords

Core MHD control by ECCD
Current density profile modification by NBCD
ELM triggering
Improved H-mode
Tokamak divertor operation
Tungsten clad first wall

Access to Document

10.1109/FUSION.2005.252853

Cite this

Mertens, V., Dux, R., Gantenbein, G., Gruber, O., Günter, S., Hobirk, J., Horton, L., Igochine, V., Kallenbach, A., Lang, P. T., Leuterer, F., Maggi, C. F., Manini, A., Maraschek, M., Mück, A., Neu, R., Noterdaeme, J. M., Pautasso, G., Sips, A. C. C., ... Zohm, H. (2006). Recent accomplishments and future plans of ASDEX Upgrade. In 21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05 Article 4018887 (Proceedings - Symposium on Fusion Engineering). https://doi.org/10.1109/FUSION.2005.252853

@inproceedings{50233061b26d4f41865f4dbe7cc20068,

title = "Recent accomplishments and future plans of ASDEX Upgrade",

abstract = "ASDEX Upgrade has demonstrated clear progress in ITER relevant plasma operation scenarios. Successful operation with about 70% Tungsten clad first wall is shown. The operation space of the improved H-mode (advanced tokamak scenario) is enlarged in safety factor 3≤q95≥5 and density 0.4≤n e/nGw≥0.9. The performance can clearly exceed the ITER reference value. At high densities type-II ELMs mitigate the peak power load in the divertor. A similar effect is achieved by increasing the type-I ELM frequency by shallow pellet injection or cyclic vertical plasma motion. Off-axis neutral beam current drive leads at low powers to a clear current density profile modification. Sawtooth tailoring by electron cyclotron current drive (ECCD) can prevent the growth of neoclassical tearing modes (NTM). (3,2) and (2,1) NTMs excited at high plasma pressure can be stabilized by ECCD at moderate power levels. Narrow ECCD absorption profiles are more effective than broad ones.",

keywords = "Core MHD control by ECCD, Current density profile modification by NBCD, ELM triggering, Improved H-mode, Tokamak divertor operation, Tungsten clad first wall",

author = "V. Mertens and R. Dux and G. Gantenbein and O. Gruber and S. G{\"u}nter and J. Hobirk and L. Horton and V. Igochine and A. Kallenbach and Lang, {P. T.} and F. Leuterer and Maggi, {C. F.} and A. Manini and M. Maraschek and A. M{\"u}ck and R. Neu and Noterdaeme, {J. M.} and G. Pautasso and Sips, {A. C.C.} and A. St{\"a}bler and J. Stober and D. Wagner and H. Zohm",

year = "2006",

doi = "10.1109/FUSION.2005.252853",

language = "English",

isbn = "142440150X",

series = "Proceedings - Symposium on Fusion Engineering",

booktitle = "21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05",

note = "21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05 ; Conference date: 26-09-2005 Through 29-09-2005",

}

Mertens, V, Dux, R, Gantenbein, G, Gruber, O, Günter, S, Hobirk, J, Horton, L, Igochine, V, Kallenbach, A, Lang, PT, Leuterer, F, Maggi, CF, Manini, A, Maraschek, M, Mück, A, Neu, R, Noterdaeme, JM, Pautasso, G, Sips, ACC, Stäbler, A, Stober, J, Wagner, D & Zohm, H 2006, Recent accomplishments and future plans of ASDEX Upgrade. in 21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05., 4018887, Proceedings - Symposium on Fusion Engineering, 21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05, Knoxville, TN, United States, 26/09/05. https://doi.org/10.1109/FUSION.2005.252853

TY - GEN

T1 - Recent accomplishments and future plans of ASDEX Upgrade

AU - Mertens, V.

AU - Dux, R.

AU - Gantenbein, G.

AU - Gruber, O.

AU - Günter, S.

AU - Hobirk, J.

AU - Horton, L.

AU - Igochine, V.

AU - Kallenbach, A.

AU - Lang, P. T.

AU - Leuterer, F.

AU - Maggi, C. F.

AU - Manini, A.

AU - Maraschek, M.

AU - Mück, A.

AU - Neu, R.

AU - Noterdaeme, J. M.

AU - Pautasso, G.

AU - Sips, A. C.C.

AU - Stäbler, A.

AU - Stober, J.

AU - Wagner, D.

AU - Zohm, H.

PY - 2006

Y1 - 2006

N2 - ASDEX Upgrade has demonstrated clear progress in ITER relevant plasma operation scenarios. Successful operation with about 70% Tungsten clad first wall is shown. The operation space of the improved H-mode (advanced tokamak scenario) is enlarged in safety factor 3≤q95≥5 and density 0.4≤n e/nGw≥0.9. The performance can clearly exceed the ITER reference value. At high densities type-II ELMs mitigate the peak power load in the divertor. A similar effect is achieved by increasing the type-I ELM frequency by shallow pellet injection or cyclic vertical plasma motion. Off-axis neutral beam current drive leads at low powers to a clear current density profile modification. Sawtooth tailoring by electron cyclotron current drive (ECCD) can prevent the growth of neoclassical tearing modes (NTM). (3,2) and (2,1) NTMs excited at high plasma pressure can be stabilized by ECCD at moderate power levels. Narrow ECCD absorption profiles are more effective than broad ones.

AB - ASDEX Upgrade has demonstrated clear progress in ITER relevant plasma operation scenarios. Successful operation with about 70% Tungsten clad first wall is shown. The operation space of the improved H-mode (advanced tokamak scenario) is enlarged in safety factor 3≤q95≥5 and density 0.4≤n e/nGw≥0.9. The performance can clearly exceed the ITER reference value. At high densities type-II ELMs mitigate the peak power load in the divertor. A similar effect is achieved by increasing the type-I ELM frequency by shallow pellet injection or cyclic vertical plasma motion. Off-axis neutral beam current drive leads at low powers to a clear current density profile modification. Sawtooth tailoring by electron cyclotron current drive (ECCD) can prevent the growth of neoclassical tearing modes (NTM). (3,2) and (2,1) NTMs excited at high plasma pressure can be stabilized by ECCD at moderate power levels. Narrow ECCD absorption profiles are more effective than broad ones.

KW - Core MHD control by ECCD

KW - Current density profile modification by NBCD

KW - ELM triggering

KW - Improved H-mode

KW - Tokamak divertor operation

KW - Tungsten clad first wall

UR - http://www.scopus.com/inward/record.url?scp=34547804335&partnerID=8YFLogxK

U2 - 10.1109/FUSION.2005.252853

DO - 10.1109/FUSION.2005.252853

M3 - Conference contribution

AN - SCOPUS:34547804335

SN - 142440150X

SN - 9781424401505

T3 - Proceedings - Symposium on Fusion Engineering

BT - 21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05

T2 - 21st IEEE/NPS Symposium on Fusion Engineering, SOFE'05

Y2 - 26 September 2005 through 29 September 2005

ER -

Recent accomplishments and future plans of ASDEX Upgrade

Abstract

Publication series

Conference

Keywords

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