Modelling one-third field operation in the ITER pre-fusion power operation phase

Research output: Contribution to journalArticleScientificpeer-review

Standard

Modelling one-third field operation in the ITER pre-fusion power operation phase. / ITPA Topical Grp Energetic Particl; Kim, S. H.; Kurki-Suonio, T.; Sarkimaki, K.; Snicker, A.

In: Nuclear Fusion, Vol. 59, No. 12, 126014, 12.2019.

Research output: Contribution to journalArticleScientificpeer-review

Harvard

APA

Vancouver

Author

Bibtex - Download

@article{4416b0ba990b4b6e80381365eb89a8bb,
title = "Modelling one-third field operation in the ITER pre-fusion power operation phase",
abstract = "In the four-stage approach of the new ITER Research Plan, the first pre-fusion power operation (PFPO) phase will only have limited power available from external heating and current drive (H&CD) systems: 20-30 MW provided by the electron cyclotron resonance heating (ECRH) system. Accessing the H-mode confinement regime at such low auxiliary power requires operating at low magnetic field, plasma current and density, i.e. 1.8 T and 5 MA for a density between 40{\%} and 50{\%} of the Greenwald density. II-mode plasmas at 5 MA/1.8 T will also be investigated in the second PFPO phase when ITER will have its full complement of H&CD capabilities installed, i.e. 20-30 MW of ECRH, 20 MW of ion cyclotron resonance heating and 33 MW of neutral beam injection. This paper describes the operational constraints and the II&CD capabilities for such scenarios in hydrogen and helium plasmas, to assess their viability and the issues it will be possible to address with them. The modelling results show that 5 MA/1.8 T scenarios are viable and will allow the exploration of the H-mode physics and control issues foreseen in the ITER Research Programme in the PFPO phases.",
keywords = "heating and current drive, ITER, one-third field operation, NBI, ICRH, ECRH, tokamak, CURRENT DRIVE, TRANSPORT, TOKAMAK, ABSORPTION, CODE",
author = "{ITPA Topical Grp Energetic Particl} and M. Schneider and Polevoi, {A. R.} and Kim, {S. H.} and A. Loarte and Pinches, {S. D.} and J-F Artaud and E. Militello-Asp and B. Beaumont and R. Bilato and D. Boilson and Campbell, {D. J.} and P. Dumortier and D. Farina and L. Figini and Y. Gribov and M. Henderson and Khayrutdinov, {R. R.} and Kavin, {A. A.} and F. Kochl and T. Kurki-Suonio and A. Kuyanov and P. Lamalle and E. Lerche and Lukash, {V. E.} and A. Messiaen and V Parail and K. Sarkimaki and A. Snicker and {Van Eester}, D.",
year = "2019",
month = "12",
doi = "10.1088/1741-4326/ab3de0",
language = "English",
volume = "59",
journal = "Nuclear Fusion",
issn = "0029-5515",
number = "12",

}

RIS - Download

TY - JOUR

T1 - Modelling one-third field operation in the ITER pre-fusion power operation phase

AU - ITPA Topical Grp Energetic Particl

AU - Schneider, M.

AU - Polevoi, A. R.

AU - Kim, S. H.

AU - Loarte, A.

AU - Pinches, S. D.

AU - Artaud, J-F

AU - Militello-Asp, E.

AU - Beaumont, B.

AU - Bilato, R.

AU - Boilson, D.

AU - Campbell, D. J.

AU - Dumortier, P.

AU - Farina, D.

AU - Figini, L.

AU - Gribov, Y.

AU - Henderson, M.

AU - Khayrutdinov, R. R.

AU - Kavin, A. A.

AU - Kochl, F.

AU - Kurki-Suonio, T.

AU - Kuyanov, A.

AU - Lamalle, P.

AU - Lerche, E.

AU - Lukash, V. E.

AU - Messiaen, A.

AU - Parail, V

AU - Sarkimaki, K.

AU - Snicker, A.

AU - Van Eester, D.

PY - 2019/12

Y1 - 2019/12

N2 - In the four-stage approach of the new ITER Research Plan, the first pre-fusion power operation (PFPO) phase will only have limited power available from external heating and current drive (H&CD) systems: 20-30 MW provided by the electron cyclotron resonance heating (ECRH) system. Accessing the H-mode confinement regime at such low auxiliary power requires operating at low magnetic field, plasma current and density, i.e. 1.8 T and 5 MA for a density between 40% and 50% of the Greenwald density. II-mode plasmas at 5 MA/1.8 T will also be investigated in the second PFPO phase when ITER will have its full complement of H&CD capabilities installed, i.e. 20-30 MW of ECRH, 20 MW of ion cyclotron resonance heating and 33 MW of neutral beam injection. This paper describes the operational constraints and the II&CD capabilities for such scenarios in hydrogen and helium plasmas, to assess their viability and the issues it will be possible to address with them. The modelling results show that 5 MA/1.8 T scenarios are viable and will allow the exploration of the H-mode physics and control issues foreseen in the ITER Research Programme in the PFPO phases.

AB - In the four-stage approach of the new ITER Research Plan, the first pre-fusion power operation (PFPO) phase will only have limited power available from external heating and current drive (H&CD) systems: 20-30 MW provided by the electron cyclotron resonance heating (ECRH) system. Accessing the H-mode confinement regime at such low auxiliary power requires operating at low magnetic field, plasma current and density, i.e. 1.8 T and 5 MA for a density between 40% and 50% of the Greenwald density. II-mode plasmas at 5 MA/1.8 T will also be investigated in the second PFPO phase when ITER will have its full complement of H&CD capabilities installed, i.e. 20-30 MW of ECRH, 20 MW of ion cyclotron resonance heating and 33 MW of neutral beam injection. This paper describes the operational constraints and the II&CD capabilities for such scenarios in hydrogen and helium plasmas, to assess their viability and the issues it will be possible to address with them. The modelling results show that 5 MA/1.8 T scenarios are viable and will allow the exploration of the H-mode physics and control issues foreseen in the ITER Research Programme in the PFPO phases.

KW - heating and current drive

KW - ITER

KW - one-third field operation

KW - NBI

KW - ICRH

KW - ECRH

KW - tokamak

KW - CURRENT DRIVE

KW - TRANSPORT

KW - TOKAMAK

KW - ABSORPTION

KW - CODE

U2 - 10.1088/1741-4326/ab3de0

DO - 10.1088/1741-4326/ab3de0

M3 - Article

VL - 59

JO - Nuclear Fusion

JF - Nuclear Fusion

SN - 0029-5515

IS - 12

M1 - 126014

ER -

ID: 37833758