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

    Research output: Contribution to journalArticleScientificpeer-review

    19 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 βN on extended duration.
    Original languageEnglish
    Pages (from-to)B179 - B194
    Number of pages16
    JournalPlasma Physics and Controlled Fusion
    Volume47
    Issue number12B
    DOIs
    Publication statusPublished - 2005
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Linear stability analysis
    Electric current control
    profiles
    heat
    Physics
    Degradation
    temperature profiles
    projection
    degradation
    scaling
    physics
    Temperature
    Hot Temperature

    Keywords

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

    Cite this

    Imbeaux, F., Artaud, J. F., Kinsey, J. E., Tala, T., Bourdelle, C., Fujita, T., ... 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
    Imbeaux, F. ; Artaud, J.F. ; Kinsey, J.E. ; Tala, Tuomas ; 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. / Multi-machine transport analysis of hybrid discharges from the ITPA profile database. In: Plasma Physics and Controlled Fusion. 2005 ; Vol. 47, No. 12B. pp. B179 - B194.
    @article{240b494f21d44bc286bfd5a884fd1173,
    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}",
    year = "2005",
    doi = "10.1088/0741-3335/47/12B/S14",
    language = "English",
    volume = "47",
    pages = "B179 -- B194",
    journal = "Plasma Physics and Controlled Fusion",
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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

    Multi-machine transport analysis of hybrid discharges from the ITPA profile database. / Imbeaux, F.; Artaud, J.F.; Kinsey, J.E.; Tala, Tuomas; 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.

    In: Plasma Physics and Controlled Fusion, Vol. 47, No. 12B, 2005, p. B179 - B194.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    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

    VL - 47

    SP - B179 - B194

    JO - Plasma Physics and Controlled Fusion

    JF - Plasma Physics and Controlled Fusion

    SN - 0741-3335

    IS - 12B

    ER -