Multi-machine transport analysis of hybrid discharges from the ITPA profile database

F. Imbeaux; J.F. Artaud; J.E. Kinsey; Tuomas Tala; C. Bourdelle; T. Fujita; C. Greenfield; E. Joffrin; Y.S. Na; V.V. Parail; Y. Sakamoto; A.C.C. Sips; I. Voitsekhovitch; JET-EFDA Contributors

doi:10.1088/0741-3335/47/12B/S14

Multi-machine transport analysis of hybrid discharges from the ITPA profile database

F. Imbeaux
, J.F. Artaud
, J.E. Kinsey
, Tuomas Tala
, C. Bourdelle
, T. Fujita
, C. Greenfield
, E. Joffrin
, Y.S. Na
, V.V. Parail
, Y. Sakamoto
, A.C.C. Sips
, I. Voitsekhovitch
, JET-EFDA Contributors

Commissariat a l'Energie Atomique et aux Energies Alternatives (CEA)
Lehigh University
Japan Atomic Energy Agency
General Atomics
Max-Planck-Institut für Plasmaphysik (IPP)
Korea Basic Science Institute (KBSI)
Culham Science Centre

Research output: Contribution to journal › Article › Scientific › peer-review

20 Citations (Scopus)

Abstract

Current diffusion, heat transport modelling, and linear gyrokinetic stability analysis have been carried out on a set of seven hybrid discharges from AUG, DIII-D, JET and JT-60U, in order to gain better understanding of the physics underlying this promising candidate scenario for ITER. Within this dataset, the GLF23 model has a higher accuracy than the Weiland model in predicting the temperature profiles in the region 0.3 < ρ < 0.8. The core heat transport appears to be similar between hybrid discharges and standard H-modes, and also among hybrid discharges with very different H factors. Projections to ITER show that Q = 10 can be obtained with the hybrid scenario using an alternative scaling without β degradation. However, additional off-axis current drive and current profile control might be needed for the ITER hybrid scenario, in order to achieve its full potential for high β_N on extended duration.

Original language	English
Pages (from-to)	B179 - B194
Number of pages	16
Journal	Plasma Physics and Controlled Fusion
Volume	47
Issue number	12B
DOIs	https://doi.org/10.1088/0741-3335/47/12B/S14
Publication status	Published - 2005
MoE publication type	A1 Journal article-refereed

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

SDG 7 Affordable and Clean Energy

Keywords

JET
plasma
fusion energy
fusion reactors
tokamak
ITER
hybrid discharges
lower hybrid current drive
current drive

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10.1088/0741-3335/47/12B/S14

Cite this

Imbeaux, F., Artaud, J. F., Kinsey, J. E., Tala, T., Bourdelle, C., Fujita, T., Greenfield, C., Joffrin, E., Na, Y. S., Parail, V. V., Sakamoto, Y., Sips, A. C. C., Voitsekhovitch, I., & JET-EFDA Contributors (2005). Multi-machine transport analysis of hybrid discharges from the ITPA profile database. Plasma Physics and Controlled Fusion, 47(12B), B179 - B194. https://doi.org/10.1088/0741-3335/47/12B/S14

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title = "Multi-machine transport analysis of hybrid discharges from the ITPA profile database",

abstract = "Current diffusion, heat transport modelling, and linear gyrokinetic stability analysis have been carried out on a set of seven hybrid discharges from AUG, DIII-D, JET and JT-60U, in order to gain better understanding of the physics underlying this promising candidate scenario for ITER. Within this dataset, the GLF23 model has a higher accuracy than the Weiland model in predicting the temperature profiles in the region 0.3 < ρ < 0.8. The core heat transport appears to be similar between hybrid discharges and standard H-modes, and also among hybrid discharges with very different H factors. Projections to ITER show that Q = 10 can be obtained with the hybrid scenario using an alternative scaling without β degradation. However, additional off-axis current drive and current profile control might be needed for the ITER hybrid scenario, in order to achieve its full potential for high βN on extended duration.",

keywords = "JET, plasma, fusion energy, fusion reactors, tokamak, ITER, hybrid discharges, lower hybrid current drive, current drive",

author = "F. Imbeaux and J.F. Artaud and J.E. Kinsey and Tuomas Tala and C. Bourdelle and T. Fujita and C. Greenfield and E. Joffrin and Y.S. Na and V.V. Parail and Y. Sakamoto and A.C.C. Sips and I. Voitsekhovitch and \{JET-EFDA Contributors\}",

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doi = "10.1088/0741-3335/47/12B/S14",

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Imbeaux, F, Artaud, JF, Kinsey, JE, Tala, T, Bourdelle, C, Fujita, T, Greenfield, C, Joffrin, E, Na, YS, Parail, VV, Sakamoto, Y, Sips, ACC, Voitsekhovitch, I & JET-EFDA Contributors 2005, 'Multi-machine transport analysis of hybrid discharges from the ITPA profile database', Plasma Physics and Controlled Fusion, vol. 47, no. 12B, pp. B179 - B194. https://doi.org/10.1088/0741-3335/47/12B/S14

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T1 - Multi-machine transport analysis of hybrid discharges from the ITPA profile database

AU - Imbeaux, F.

AU - Artaud, J.F.

AU - Kinsey, J.E.

AU - Tala, Tuomas

AU - Bourdelle, C.

AU - Fujita, T.

AU - Greenfield, C.

AU - Joffrin, E.

AU - Na, Y.S.

AU - Parail, V.V.

AU - Sakamoto, Y.

AU - Sips, A.C.C.

AU - Voitsekhovitch, I.

AU - JET-EFDA Contributors, null

PY - 2005

Y1 - 2005

N2 - Current diffusion, heat transport modelling, and linear gyrokinetic stability analysis have been carried out on a set of seven hybrid discharges from AUG, DIII-D, JET and JT-60U, in order to gain better understanding of the physics underlying this promising candidate scenario for ITER. Within this dataset, the GLF23 model has a higher accuracy than the Weiland model in predicting the temperature profiles in the region 0.3 < ρ < 0.8. The core heat transport appears to be similar between hybrid discharges and standard H-modes, and also among hybrid discharges with very different H factors. Projections to ITER show that Q = 10 can be obtained with the hybrid scenario using an alternative scaling without β degradation. However, additional off-axis current drive and current profile control might be needed for the ITER hybrid scenario, in order to achieve its full potential for high βN on extended duration.

AB - Current diffusion, heat transport modelling, and linear gyrokinetic stability analysis have been carried out on a set of seven hybrid discharges from AUG, DIII-D, JET and JT-60U, in order to gain better understanding of the physics underlying this promising candidate scenario for ITER. Within this dataset, the GLF23 model has a higher accuracy than the Weiland model in predicting the temperature profiles in the region 0.3 < ρ < 0.8. The core heat transport appears to be similar between hybrid discharges and standard H-modes, and also among hybrid discharges with very different H factors. Projections to ITER show that Q = 10 can be obtained with the hybrid scenario using an alternative scaling without β degradation. However, additional off-axis current drive and current profile control might be needed for the ITER hybrid scenario, in order to achieve its full potential for high βN on extended duration.

KW - JET

KW - plasma

KW - fusion energy

KW - fusion reactors

KW - tokamak

KW - ITER

KW - hybrid discharges

KW - lower hybrid current drive

KW - current drive

U2 - 10.1088/0741-3335/47/12B/S14

DO - 10.1088/0741-3335/47/12B/S14

M3 - Article

SN - 0741-3335

VL - 47

SP - B179 - B194

JO - Plasma Physics and Controlled Fusion

JF - Plasma Physics and Controlled Fusion

IS - 12B

ER -

Multi-machine transport analysis of hybrid discharges from the ITPA profile database

Abstract

UN SDGs

Keywords

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