EU developments of the ITER ECRH system

Henderson, M.; Alberti, S.; Benin, P.; Bonicelli, T.; Chavan, R.; Campbell, D.J.; Cirant, S.; Dammertz, G.; Dormicchi, O.; Dumbrājs, O.; Fasel, D.; Goodman, T. P.; Heidinger, R.; Hogge, J.‐P.; Kasparek, W.; Lievin, C.; Piosczyk, B.; Poli, E.; Ramponi, G.; Saibene, G.; Sauter, O.; Serikov, A.; Taddia, Giuseppe; Thumm, M.; Tran, M.Q.; Verhoeven, A.G.A.; Zohm, H.

doi:10.1016/j.fusengdes.2007.01.029

Cited by 34 publications

(12 citation statements)

References 25 publications

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“…which is in quite good agreement with Sauter's stabilization criterion (2), derived in Ref. [11] and confirmed in Ref.…”

Section: Derivation Of the Stabilization Criteriasupporting

confidence: 91%

“…The nominal power reaching the plasma on account of transmission losses is 20 MW, to be divided between the two launchers. This paper focuses on the criteria guiding the design of the UL, which is being developed in the frame of a European collaboration [2] and has reached recently the preliminary design level, i. e. the last major step before design finalization [3]. The UL comprises four ports, each housing eight beam lines, arrayed in an upper and a lower row of four waveguides each.…”

Section: Introductionmentioning

confidence: 99%

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On recent results in the modelling of neoclassical-tearing-mode stabilization via electron cyclotron current drive and their impact on the design of the upper EC launcher for ITER

et al. 2015

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Electron cyclotron wave beams injected from a launcher placed in the upper part of the vessel will be used in ITER to control MHD instabilities, in particular neoclassical tearing modes (NTMs). Simplified NTM stabilization criteria have been used in the past to guide the optimization of the launcher. Their derivation is reviewed in this paper and their range of applicability clarified. Moreover, possible effects leading to a deterioration of the predicted performance are discussed. Particularly critical in this context is the broadening of the EC deposition profiles. It is argued that the most detrimental effect for ITER is likely to be the scattering of the EC beams from density fluctuations due to plasma turbulence, resulting in a beam broadening by about a factor of two. The combined impact of these effects with that of beam misalignment (with respect to the targeted surface) is investigated by solving the Rutherford equation in a form that retains the most relevant terms. The perspectives for NTM stabilization in the Q = 10 ITER scenario are discussed.

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“…which is in quite good agreement with Sauter's stabilization criterion (2), derived in Ref. [11] and confirmed in Ref.…”

Section: Derivation Of the Stabilization Criteriasupporting

confidence: 91%

Section: Introductionmentioning

confidence: 99%

On recent results in the modelling of neoclassical-tearing-mode stabilization via electron cyclotron current drive and their impact on the design of the upper EC launcher for ITER

et al. 2015

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“…Control of the sawtooth period with ECCD has been demonstrated on a number of tokamaks [16][17][18][19][20][21][22], and consequently has been included in the design of the sawtooth control system for ITER [23,24]. The history of sawtooth control using current drive is reviewed in [25].…”

Section: Introductionmentioning

confidence: 99%

Sawtooth control using electron cyclotron current drive in the presence of energetic particles in high performance ASDEX Upgrade plasmas

Chapman

Igochine

Maraschek

et al. 2013

Plasma Phys. Control. Fusion

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Abstract.Sawtooth control using steerable electron cyclotron current drive (ECCD) has been demonstrated in ASDEX Upgrade plasmas with a significant population of energetic ions in the plasma core and long uncontrolled sawtooth periods. The sawtooth period is found to be minimised when the ECCD resonance is swept to just inside the q = 1 surface. Sawtooth control using ECCD inside q = 1 avoids the triggering of performance-degrading neoclassical tearing modes, even at much higher pressure than required in the ITER baseline scenario. Operation at 25% higher normalised pressure has been achieved when only modest ECCD power is used for sawtooth control compared to identical discharges without sawtooth control when neo-classical tearing modes are triggered by the sawteeth. Numerical modelling suggests that the achieved driven current changes the local magnetic shear sufficiently to compensate for the stabilising influence of the energetic particles in the plasma core. Sawtooth control using ECCD in ASDEX Upgrade2

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“…An in-line switch installed in the transmission line (TL) is used to divert the power to either launcher depending on the physics requirements. For example, if the EC system is to be used for controlling magneto-hydrodynamic (MHD) instabilities the power is directed to the four UL [1,2] providing access to the outer half of the plasma. If central central heating and current drive is required the power is directed to the EL [3,4] providing access to the inner half of the plasma.…”

Section: Introductionmentioning

confidence: 99%

Overview of the ITER EC upper launcher

et al. 2008

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Abstract. The ITER electron cyclotron (EC) upper port antenna (or launcher) is nearing completion of the detailed design stage and will soon be starting the final build to print design. The main objective of this launcher is to drive current locally to stabilise the NTMs (depositing ECCD inside of the island that forms on either the q=3/2 or 2 rational magnetic flux surfaces) and control the sawtooth instability (deposit ECCD near the q=1 surface). The launcher should be capable of steering the focused beam deposition location to the resonant flux surface over the range in which the q=1, 3/2 and 2 surfaces are expected to be found, for the various plasma equilibria susceptible to the onset of NTMs and sawteeth. The aim of this paper is to provide the design status of the principle components that make up the launcher: port plug, mm-wave system and shield block components. The port plug represents the chamber that provides a rigid support structure that houses the mm-wave and shield blocks. The mm-wave system is comprised of the components used to guide the RF beams through the port plug structure and refocus the beams far into the plasma. The shield block components are used to attenuate the nuclear radiation from the burning plasma, protecting the fragile in-port components and reducing the neutron streaming through the port assembly. The design of these three subsystems is described, in addition, the relevant thermo-mechanical and electro-magnetic analysis are reviewed for the critical design issues.

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EU developments of the ITER ECRH system

Cited by 34 publications

References 25 publications

On recent results in the modelling of neoclassical-tearing-mode stabilization via electron cyclotron current drive and their impact on the design of the upper EC launcher for ITER

On recent results in the modelling of neoclassical-tearing-mode stabilization via electron cyclotron current drive and their impact on the design of the upper EC launcher for ITER

Sawtooth control using electron cyclotron current drive in the presence of energetic particles in high performance ASDEX Upgrade plasmas

Overview of the ITER EC upper launcher

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