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Optimization of currents in ITER correction coils

  • Mathematical Modeling and Computational Physics 2013 Dubna, Russia, July 8–July 12, 2013
  • Computer Technologies in Physics
  • Published:
Physics of Particles and Nuclei Letters Aims and scope Submit manuscript

Abstract

In tokamaks non-axisymmetric magnetic field perturbations (error fields) can induce in plasma locked modes and cause disruption. In ITER the main contributor to error fields is assembly and manufacturing errors of the magnet system of the machine. To suppress intrinsic error fields and guarantee the expected plasma performance ITER is provided with the proper correction coils (CC). The paper is related to optimization of CC currents. The optimization takes into account as constraints both CC current capacities and an allowable level of error fields.

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Authors and Affiliations

  1. D.V. Efremov Scientific Research Institute, St.-Petersburg, 196641, Russia

    V. M. Amoskov, V. A. Belyakov, E. A. Lamzin, N. A. Maximenkova & S. E. Sytchevsky

  2. ITER Organization, Route de Vinon sur Verdon, 13115, Saint Paul Lez Durance, France

    Yu. A. Gribov

Authors
  1. V. M. Amoskov
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  2. V. A. Belyakov
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  3. Yu. A. Gribov
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  4. E. A. Lamzin
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  5. N. A. Maximenkova
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  6. S. E. Sytchevsky
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Corresponding author

Correspondence to V. M. Amoskov.

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Amoskov, V.M., Belyakov, V.A., Gribov, Y.A. et al. Optimization of currents in ITER correction coils. Phys. Part. Nuclei Lett. 12, 375–379 (2015). https://doi.org/10.1134/S1547477115030048

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  • DOI: https://doi.org/10.1134/S1547477115030048

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