Overview of ASDEX Upgrade results

Tutkimustuotos: Lehtiartikkeli

Standard

Overview of ASDEX Upgrade results. / ASDEX Upgrade Team; EUROfusion MST1 Team; Kallenbach, A.; Aguiam, D.; Aho-Mantila, L.; Angioni, C.; Arden, N.; Parra, R. Arredondo; Asunta, O.; de Baar, M.; Balden, M.; Behler, K.; Bergmann, A.; Bernardo, J.; Bernert, M.; Beurskens, M.; Biancalani, A.; Bilato, R.; Birkenmeier, G.; Bobkov, V.; Bock, A.; Bogomolov, A.; Bolzonella, T.; Boswirth, B.; Bottereau, C.; Bottino, A.; van den Brand, H.; Brezinsek, S.; Brida, D.; Brochard, F.; Groth, M.; Hakola, A. H.; Karhunen, J.; Kim, D.; Kurki-Suonio, T.; Li, L.; Li, M.; Liu, Y.; Miettunen, J.; Perez, I. Paradela; Salmi, A.; Santos, J.; Shao, L.; Silva, C.; Simpson, J.; Snicker, A.; Wang, N.; Wang, X.; Yang, Q.; Yang, Z.; Yu, Q.; Zhang, W.

julkaisussa: Nuclear Fusion, Vuosikerta 57, Nro 10, 102015, 10.2017.

Tutkimustuotos: Lehtiartikkeli

Harvard

ASDEX Upgrade Team, EUROfusion MST1 Team, Kallenbach, A, Aguiam, D, Aho-Mantila, L, Angioni, C, Arden, N, Parra, RA, Asunta, O, de Baar, M, Balden, M, Behler, K, Bergmann, A, Bernardo, J, Bernert, M, Beurskens, M, Biancalani, A, Bilato, R, Birkenmeier, G, Bobkov, V, Bock, A, Bogomolov, A, Bolzonella, T, Boswirth, B, Bottereau, C, Bottino, A, van den Brand, H, Brezinsek, S, Brida, D, Brochard, F, Groth, M, Hakola, AH, Karhunen, J, Kim, D, Kurki-Suonio, T, Li, L, Li, M, Liu, Y, Miettunen, J, Perez, IP, Salmi, A, Santos, J, Shao, L, Silva, C, Simpson, J, Snicker, A, Wang, N, Wang, X, Yang, Q, Yang, Z, Yu, Q & Zhang, W 2017, 'Overview of ASDEX Upgrade results', Nuclear Fusion, Vuosikerta. 57, Nro 10, 102015. https://doi.org/10.1088/1741-4326/aa64f6

APA

ASDEX Upgrade Team, EUROfusion MST1 Team, Kallenbach, A., Aguiam, D., Aho-Mantila, L., Angioni, C., ... Zhang, W. (2017). Overview of ASDEX Upgrade results. Nuclear Fusion, 57(10), [102015]. https://doi.org/10.1088/1741-4326/aa64f6

Vancouver

ASDEX Upgrade Team, EUROfusion MST1 Team, Kallenbach A, Aguiam D, Aho-Mantila L, Angioni C et al. Overview of ASDEX Upgrade results. Nuclear Fusion. 2017 loka;57(10). 102015. https://doi.org/10.1088/1741-4326/aa64f6

Author

ASDEX Upgrade Team ; EUROfusion MST1 Team ; Kallenbach, A. ; Aguiam, D. ; Aho-Mantila, L. ; Angioni, C. ; Arden, N. ; Parra, R. Arredondo ; Asunta, O. ; de Baar, M. ; Balden, M. ; Behler, K. ; Bergmann, A. ; Bernardo, J. ; Bernert, M. ; Beurskens, M. ; Biancalani, A. ; Bilato, R. ; Birkenmeier, G. ; Bobkov, V. ; Bock, A. ; Bogomolov, A. ; Bolzonella, T. ; Boswirth, B. ; Bottereau, C. ; Bottino, A. ; van den Brand, H. ; Brezinsek, S. ; Brida, D. ; Brochard, F. ; Groth, M. ; Hakola, A. H. ; Karhunen, J. ; Kim, D. ; Kurki-Suonio, T. ; Li, L. ; Li, M. ; Liu, Y. ; Miettunen, J. ; Perez, I. Paradela ; Salmi, A. ; Santos, J. ; Shao, L. ; Silva, C. ; Simpson, J. ; Snicker, A. ; Wang, N. ; Wang, X. ; Yang, Q. ; Yang, Z. ; Yu, Q. ; Zhang, W. / Overview of ASDEX Upgrade results. Julkaisussa: Nuclear Fusion. 2017 ; Vuosikerta 57, Nro 10.

Bibtex - Lataa

@article{589b2013f32e4f00a5a8562e2704296e,
title = "Overview of ASDEX Upgrade results",
abstract = "The ASDEX Upgrade (AUG) programme is directed towards physics input to critical elements of the ITER design and the preparation of ITER operation, as well as addressing physics issues for a future DEMO design. Since 2015, AUG is equipped with a new pair of 3-strap ICRF antennas, which were designed for a reduction of tungsten release during ICRF operation. As predicted, a factor two reduction on the ICRF-induced W plasma content could be achieved by the reduction of the sheath voltage at the antenna limiters via the compensation of the image currents of the central and side straps in the antenna frame. There are two main operational scenario lines in AUG. Experiments with low collisionality, which comprise current drive, ELM mitigation/suppression and fast ion physics, are mainly done with freshly boronized walls to reduce the tungsten influx at these high edge temperature conditions. Full ELM suppression and non-inductive operation up to a plasma current of I-p = 0.8 MA could be obtained at low plasma density. Plasma exhaust is studied under conditions of high neutral divertor pressure and separatrix electron density, where a fresh boronization is not required. Substantial progress could be achieved for the understanding of the confinement degradation by strong D puffing and the improvement with nitrogen or carbon seeding. Inward/outward shifts of the electron density profile relative to the temperature profile effect the edge stability via the pressure profile changes and lead to improved/decreased pedestal performance. Seeding and D gas puffing are found to effect the core fueling via changes in a region of high density on the high field side (HFSHD).The integration of all above mentioned operational scenarios will be feasible and naturally obtained in a large device where the edge is more opaque for neutrals and higher plasma temperatures provide a lower collisionality. The combination of exhaust control with pellet fueling has been successfully demonstrated. High divertor enrichment values of nitrogen E-N >= 10 have been obtained during pellet injection, which is a prerequisite for the simultaneous achievement of good core plasma purity and high divertor radiation levels. Impurity accumulation observed in the all-metal AUG device caused by the strong neoclassical inward transport of tungsten in the pedestal is expected to be relieved by the higher neoclassical temperature screening in larger devices.",
keywords = "nuclear fusion, tokamak physics, ITER, DEMO",
author = "{ASDEX Upgrade Team} and {EUROfusion MST1 Team} and A. Kallenbach and D. Aguiam and L. Aho-Mantila and C. Angioni and N. Arden and Parra, {R. Arredondo} and O. Asunta and {de Baar}, M. and M. Balden and K. Behler and A. Bergmann and J. Bernardo and M. Bernert and M. Beurskens and A. Biancalani and R. Bilato and G. Birkenmeier and V. Bobkov and A. Bock and A. Bogomolov and T. Bolzonella and B. Boswirth and C. Bottereau and A. Bottino and {van den Brand}, H. and S. Brezinsek and D. Brida and F. Brochard and M. Groth and Hakola, {A. H.} and J. Karhunen and D. Kim and T. Kurki-Suonio and L. Li and M. Li and Y. Liu and J. Miettunen and Perez, {I. Paradela} and A. Salmi and J. Santos and L. Shao and C. Silva and J. Simpson and A. Snicker and N. Wang and X. Wang and Q. Yang and Z. Yang and Q. Yu and W. Zhang",
year = "2017",
month = "10",
doi = "10.1088/1741-4326/aa64f6",
language = "English",
volume = "57",
journal = "Nuclear Fusion",
issn = "0029-5515",
number = "10",

}

RIS - Lataa

TY - JOUR

T1 - Overview of ASDEX Upgrade results

AU - ASDEX Upgrade Team

AU - EUROfusion MST1 Team

AU - Kallenbach, A.

AU - Aguiam, D.

AU - Aho-Mantila, L.

AU - Angioni, C.

AU - Arden, N.

AU - Parra, R. Arredondo

AU - Asunta, O.

AU - de Baar, M.

AU - Balden, M.

AU - Behler, K.

AU - Bergmann, A.

AU - Bernardo, J.

AU - Bernert, M.

AU - Beurskens, M.

AU - Biancalani, A.

AU - Bilato, R.

AU - Birkenmeier, G.

AU - Bobkov, V.

AU - Bock, A.

AU - Bogomolov, A.

AU - Bolzonella, T.

AU - Boswirth, B.

AU - Bottereau, C.

AU - Bottino, A.

AU - van den Brand, H.

AU - Brezinsek, S.

AU - Brida, D.

AU - Brochard, F.

AU - Groth, M.

AU - Hakola, A. H.

AU - Karhunen, J.

AU - Kim, D.

AU - Kurki-Suonio, T.

AU - Li, L.

AU - Li, M.

AU - Liu, Y.

AU - Miettunen, J.

AU - Perez, I. Paradela

AU - Salmi, A.

AU - Santos, J.

AU - Shao, L.

AU - Silva, C.

AU - Simpson, J.

AU - Snicker, A.

AU - Wang, N.

AU - Wang, X.

AU - Yang, Q.

AU - Yang, Z.

AU - Yu, Q.

AU - Zhang, W.

PY - 2017/10

Y1 - 2017/10

N2 - The ASDEX Upgrade (AUG) programme is directed towards physics input to critical elements of the ITER design and the preparation of ITER operation, as well as addressing physics issues for a future DEMO design. Since 2015, AUG is equipped with a new pair of 3-strap ICRF antennas, which were designed for a reduction of tungsten release during ICRF operation. As predicted, a factor two reduction on the ICRF-induced W plasma content could be achieved by the reduction of the sheath voltage at the antenna limiters via the compensation of the image currents of the central and side straps in the antenna frame. There are two main operational scenario lines in AUG. Experiments with low collisionality, which comprise current drive, ELM mitigation/suppression and fast ion physics, are mainly done with freshly boronized walls to reduce the tungsten influx at these high edge temperature conditions. Full ELM suppression and non-inductive operation up to a plasma current of I-p = 0.8 MA could be obtained at low plasma density. Plasma exhaust is studied under conditions of high neutral divertor pressure and separatrix electron density, where a fresh boronization is not required. Substantial progress could be achieved for the understanding of the confinement degradation by strong D puffing and the improvement with nitrogen or carbon seeding. Inward/outward shifts of the electron density profile relative to the temperature profile effect the edge stability via the pressure profile changes and lead to improved/decreased pedestal performance. Seeding and D gas puffing are found to effect the core fueling via changes in a region of high density on the high field side (HFSHD).The integration of all above mentioned operational scenarios will be feasible and naturally obtained in a large device where the edge is more opaque for neutrals and higher plasma temperatures provide a lower collisionality. The combination of exhaust control with pellet fueling has been successfully demonstrated. High divertor enrichment values of nitrogen E-N >= 10 have been obtained during pellet injection, which is a prerequisite for the simultaneous achievement of good core plasma purity and high divertor radiation levels. Impurity accumulation observed in the all-metal AUG device caused by the strong neoclassical inward transport of tungsten in the pedestal is expected to be relieved by the higher neoclassical temperature screening in larger devices.

AB - The ASDEX Upgrade (AUG) programme is directed towards physics input to critical elements of the ITER design and the preparation of ITER operation, as well as addressing physics issues for a future DEMO design. Since 2015, AUG is equipped with a new pair of 3-strap ICRF antennas, which were designed for a reduction of tungsten release during ICRF operation. As predicted, a factor two reduction on the ICRF-induced W plasma content could be achieved by the reduction of the sheath voltage at the antenna limiters via the compensation of the image currents of the central and side straps in the antenna frame. There are two main operational scenario lines in AUG. Experiments with low collisionality, which comprise current drive, ELM mitigation/suppression and fast ion physics, are mainly done with freshly boronized walls to reduce the tungsten influx at these high edge temperature conditions. Full ELM suppression and non-inductive operation up to a plasma current of I-p = 0.8 MA could be obtained at low plasma density. Plasma exhaust is studied under conditions of high neutral divertor pressure and separatrix electron density, where a fresh boronization is not required. Substantial progress could be achieved for the understanding of the confinement degradation by strong D puffing and the improvement with nitrogen or carbon seeding. Inward/outward shifts of the electron density profile relative to the temperature profile effect the edge stability via the pressure profile changes and lead to improved/decreased pedestal performance. Seeding and D gas puffing are found to effect the core fueling via changes in a region of high density on the high field side (HFSHD).The integration of all above mentioned operational scenarios will be feasible and naturally obtained in a large device where the edge is more opaque for neutrals and higher plasma temperatures provide a lower collisionality. The combination of exhaust control with pellet fueling has been successfully demonstrated. High divertor enrichment values of nitrogen E-N >= 10 have been obtained during pellet injection, which is a prerequisite for the simultaneous achievement of good core plasma purity and high divertor radiation levels. Impurity accumulation observed in the all-metal AUG device caused by the strong neoclassical inward transport of tungsten in the pedestal is expected to be relieved by the higher neoclassical temperature screening in larger devices.

KW - nuclear fusion

KW - tokamak physics

KW - ITER

KW - DEMO

U2 - 10.1088/1741-4326/aa64f6

DO - 10.1088/1741-4326/aa64f6

M3 - Article

VL - 57

JO - Nuclear Fusion

JF - Nuclear Fusion

SN - 0029-5515

IS - 10

M1 - 102015

ER -

ID: 31400269