Electron Cyclotron power management for control of Neoclassical Tearing Modes in the ITER baseline scenario

Poli, Francesca M.; Fredrickson, Eric; Henderson, Mark A.; Kim, Sun-Hee; Bertelli, Nicola; Poli, Emanuele; Farina, Daniela; Figini, Lorenzo

doi:10.1088/1741-4326/aa8e0b

Title: Electron Cyclotron power management for control of Neoclassical Tearing Modes in the ITER baseline scenario

Journal Article · Thu Sep 21 00:00:00 EDT 2017 · Nuclear Fusion

DOI:https://doi.org/10.1088/1741-4326/aa8e0b· OSTI ID:1395336

^[1]; Fredrickson, Eric ^[1]; Henderson, Mark A. ^[2]; Kim, Sun-Hee ^[2]; Bertelli, Nicola ^[1]; Poli, Emanuele ^[3]; Farina, Daniela ^[4]; Figini, Lorenzo ^[5]

Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
ITER Organization, St. Paul Lez Durance (France)
Max Planck Inst. for Plasma Physics, Munich (Germany)
Consiglio Nazionale delle Ricerche (CNR), Roma (Italy). Inst. of Plasma Physics
National Research Council (CNR), Milan (Italy). Inst. of Plasma Physics (IFP)

Time-dependent simulations are used to evolve plasma discharges in combination with a Modified Rutherford equation (MRE) for calculation of Neoclassical Tearing Mode (NTM) stability in response to Electron Cyclotron (EC) feedback control in ITER. The main application of this integrated approach is to support the development of control algorithms by analyzing the plasma response with physics-based models and to assess how uncertainties in the detection of the magnetic island and in the EC alignment affect the ability of the ITER EC system to fulfill its purpose. These simulations indicate that it is critical to detect the island as soon as possible, before its size exceeds the EC deposition width, and that maintaining alignment with the rational surface within half of the EC deposition width is needed for stabilization and suppression of the modes, especially in the case of modes with helicity (2,1). A broadening of the deposition profile, for example due to wave scattering by turbulence fluctuations or not well aligned beams, could even be favorable in the case of the (2,1)-NTM, by relaxing an over-focussing of the EC beam and improving the stabilization at the mode onset. Pre-emptive control reduces the power needed for suppression and stabilization in the ITER baseline discharge to a maximum of 5 MW, which should be reserved and available to the Upper Launcher during the entire flattop phase. By assuming continuous triggering of NTMs, with pre-emptive control ITER would be still able to demonstrate a fusion gain of Q=10.

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Research Organization:: Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)

Sponsoring Organization:: USDOE

Grant/Contract Number:: AC02- 09CH11466

OSTI ID:: 1395336

Journal Information:: Nuclear Fusion, Vol. 58, Issue 1; ISSN 0029-5515

Publisher:: IOP ScienceCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 22 works

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