Predictive transport simulations of real-time profile control in JET advanced tokamak plasmas

Tuomas Tala (Corresponding Author), L. Laborde, D. Mazon, D. Moreau, G. Corrigan, F. Crisanti, X. Garbet, D. Heading, E. Joffrin, X. Litaudon, V. Parail, Antti Salmi, JET-EFDA Contributors

    Research output: Contribution to journalArticleScientificpeer-review

    18 Citations (Scopus)

    Abstract

    Predictive, time-dependent transport simulations with a semi-empirical plasma model have been used in closed-loop simulations to control the q-profile and the strength and location of the internal transport barrier (ITB). Five transport equations (Te, Ti, q, ne, vΦ) are solved, and the power levels of lower hybrid current drive, NBI and ICRH are calculated in a feedback loop determined by the feedback controller matrix. The real-time control (RTC) technique and algorithms used in the transport simulations are identical to those implemented and used in JET experiments (Laborde L. et al 2005 Plasma Phys. Control. Fusion 47 155 and Moreau D. et al 2003 Nucl. Fusion 43 870). The closed-loop simulations with RTC demonstrate that varieties of q-profiles and pressure profiles in the ITB can be achieved and controlled simultaneously. The simulations also showed that with the same RTC technique as used in JET experiments, it is possible to sustain the q-profiles and pressure profiles close to their set-point profiles for longer than the current diffusion time. In addition, the importance of being able to handle the multiple time scales to control the location and strength of the ITB is pointed out. Several future improvements and perspectives of the RTC scheme are presented.
    Original languageEnglish
    Pages (from-to)1027 - 1038
    Number of pages12
    JournalNuclear Fusion
    Volume45
    Issue number9
    DOIs
    Publication statusPublished - 2005
    MoE publication typeA1 Journal article-refereed

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    profiles
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    Keywords

    • JET
    • plasma
    • fusion energy
    • fusion reactors
    • ITER
    • Tokamak
    • internal transport barriers

    Cite this

    Tala, T., Laborde, L., Mazon, D., Moreau, D., Corrigan, G., Crisanti, F., ... JET-EFDA Contributors (2005). Predictive transport simulations of real-time profile control in JET advanced tokamak plasmas. Nuclear Fusion, 45(9), 1027 - 1038. https://doi.org/10.1088/0029-5515/45/9/001
    Tala, Tuomas ; Laborde, L. ; Mazon, D. ; Moreau, D. ; Corrigan, G. ; Crisanti, F. ; Garbet, X. ; Heading, D. ; Joffrin, E. ; Litaudon, X. ; Parail, V. ; Salmi, Antti ; JET-EFDA Contributors. / Predictive transport simulations of real-time profile control in JET advanced tokamak plasmas. In: Nuclear Fusion. 2005 ; Vol. 45, No. 9. pp. 1027 - 1038.
    @article{acbb5984d5814642a82b7f73c1335dde,
    title = "Predictive transport simulations of real-time profile control in JET advanced tokamak plasmas",
    abstract = "Predictive, time-dependent transport simulations with a semi-empirical plasma model have been used in closed-loop simulations to control the q-profile and the strength and location of the internal transport barrier (ITB). Five transport equations (Te, Ti, q, ne, vΦ) are solved, and the power levels of lower hybrid current drive, NBI and ICRH are calculated in a feedback loop determined by the feedback controller matrix. The real-time control (RTC) technique and algorithms used in the transport simulations are identical to those implemented and used in JET experiments (Laborde L. et al 2005 Plasma Phys. Control. Fusion 47 155 and Moreau D. et al 2003 Nucl. Fusion 43 870). The closed-loop simulations with RTC demonstrate that varieties of q-profiles and pressure profiles in the ITB can be achieved and controlled simultaneously. The simulations also showed that with the same RTC technique as used in JET experiments, it is possible to sustain the q-profiles and pressure profiles close to their set-point profiles for longer than the current diffusion time. In addition, the importance of being able to handle the multiple time scales to control the location and strength of the ITB is pointed out. Several future improvements and perspectives of the RTC scheme are presented.",
    keywords = "JET, plasma, fusion energy, fusion reactors, ITER, Tokamak, internal transport barriers",
    author = "Tuomas Tala and L. Laborde and D. Mazon and D. Moreau and G. Corrigan and F. Crisanti and X. Garbet and D. Heading and E. Joffrin and X. Litaudon and V. Parail and Antti Salmi and {JET-EFDA Contributors}",
    year = "2005",
    doi = "10.1088/0029-5515/45/9/001",
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    Tala, T, Laborde, L, Mazon, D, Moreau, D, Corrigan, G, Crisanti, F, Garbet, X, Heading, D, Joffrin, E, Litaudon, X, Parail, V, Salmi, A & JET-EFDA Contributors 2005, 'Predictive transport simulations of real-time profile control in JET advanced tokamak plasmas', Nuclear Fusion, vol. 45, no. 9, pp. 1027 - 1038. https://doi.org/10.1088/0029-5515/45/9/001

    Predictive transport simulations of real-time profile control in JET advanced tokamak plasmas. / Tala, Tuomas (Corresponding Author); Laborde, L.; Mazon, D.; Moreau, D.; Corrigan, G.; Crisanti, F.; Garbet, X.; Heading, D.; Joffrin, E.; Litaudon, X.; Parail, V.; Salmi, Antti; JET-EFDA Contributors.

    In: Nuclear Fusion, Vol. 45, No. 9, 2005, p. 1027 - 1038.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Predictive transport simulations of real-time profile control in JET advanced tokamak plasmas

    AU - Tala, Tuomas

    AU - Laborde, L.

    AU - Mazon, D.

    AU - Moreau, D.

    AU - Corrigan, G.

    AU - Crisanti, F.

    AU - Garbet, X.

    AU - Heading, D.

    AU - Joffrin, E.

    AU - Litaudon, X.

    AU - Parail, V.

    AU - Salmi, Antti

    AU - JET-EFDA Contributors, null

    PY - 2005

    Y1 - 2005

    N2 - Predictive, time-dependent transport simulations with a semi-empirical plasma model have been used in closed-loop simulations to control the q-profile and the strength and location of the internal transport barrier (ITB). Five transport equations (Te, Ti, q, ne, vΦ) are solved, and the power levels of lower hybrid current drive, NBI and ICRH are calculated in a feedback loop determined by the feedback controller matrix. The real-time control (RTC) technique and algorithms used in the transport simulations are identical to those implemented and used in JET experiments (Laborde L. et al 2005 Plasma Phys. Control. Fusion 47 155 and Moreau D. et al 2003 Nucl. Fusion 43 870). The closed-loop simulations with RTC demonstrate that varieties of q-profiles and pressure profiles in the ITB can be achieved and controlled simultaneously. The simulations also showed that with the same RTC technique as used in JET experiments, it is possible to sustain the q-profiles and pressure profiles close to their set-point profiles for longer than the current diffusion time. In addition, the importance of being able to handle the multiple time scales to control the location and strength of the ITB is pointed out. Several future improvements and perspectives of the RTC scheme are presented.

    AB - Predictive, time-dependent transport simulations with a semi-empirical plasma model have been used in closed-loop simulations to control the q-profile and the strength and location of the internal transport barrier (ITB). Five transport equations (Te, Ti, q, ne, vΦ) are solved, and the power levels of lower hybrid current drive, NBI and ICRH are calculated in a feedback loop determined by the feedback controller matrix. The real-time control (RTC) technique and algorithms used in the transport simulations are identical to those implemented and used in JET experiments (Laborde L. et al 2005 Plasma Phys. Control. Fusion 47 155 and Moreau D. et al 2003 Nucl. Fusion 43 870). The closed-loop simulations with RTC demonstrate that varieties of q-profiles and pressure profiles in the ITB can be achieved and controlled simultaneously. The simulations also showed that with the same RTC technique as used in JET experiments, it is possible to sustain the q-profiles and pressure profiles close to their set-point profiles for longer than the current diffusion time. In addition, the importance of being able to handle the multiple time scales to control the location and strength of the ITB is pointed out. Several future improvements and perspectives of the RTC scheme are presented.

    KW - JET

    KW - plasma

    KW - fusion energy

    KW - fusion reactors

    KW - ITER

    KW - Tokamak

    KW - internal transport barriers

    U2 - 10.1088/0029-5515/45/9/001

    DO - 10.1088/0029-5515/45/9/001

    M3 - Article

    VL - 45

    SP - 1027

    EP - 1038

    JO - Nuclear Fusion

    JF - Nuclear Fusion

    SN - 0029-5515

    IS - 9

    ER -