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
simulation
fusion
controllers
matrices

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.
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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.",
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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}",
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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

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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

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