Main design features and challenges of the ITER-like ICRF antenna for JET

Durodié, F.; Chappuis, P.; Fanthome, J.; Goulding, R. H.; Hosea, J. C.; Lamalle, P.; Lorenz, A.; Nightingale, M. P.; Semeraro, L.; Wesner, F.

doi:10.1016/j.fusengdes.2005.08.019

Cited by 32 publications

(29 citation statements)

References 4 publications

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“…Plasma operation with the JET ITER-like Antenna (ILA) [17][18][19][20][21], based on a similar design concept as the ITER ICRH antenna [22] with a closely packed array of short low inductance straps, has demonstrated operation at ITER-relevant power densities (up to 6.2 MW/m 2 on L-mode, 4.1 MW/m 2 on H-mode) and RF voltages (42 kV, also on ELMy H-mode plasmas). Although the achieved power densities were lower than the originally foreseen 8 MW/m 2 due to the lower than expected coupling, see Section 4.2, they were still up to 6 times higher than hitherto available on JET [20].…”

Section: Performance On Jet Plasmamentioning

confidence: 99%

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The role of JET for the preparation of the ITER exploitation

Romanelli

Laxåbäck

Durodié³

et al. 2011

Fusion Engineering and Design

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Section: Performance On Jet Plasmamentioning

confidence: 99%

“…In the ILA, the straps are mounted as four Resonant Double Loops (RDLs) arranged in a 2 toroidal by 2 poloidal array [18]. Each RDL consists of two poloidally adjacent straps fed through matching capacitors from a T-junction.…”

Section: Performance On Jet Plasmamentioning

confidence: 99%

The role of JET for the preparation of the ITER exploitation

Romanelli

Laxåbäck

Durodié³

et al. 2011

Fusion Engineering and Design

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“…In all them, the ICRF power was coupled using the four A2 antennae [13], known as antennas A, B, C, and D. In pulses performed in 2009, additional power was provided by the JET ICRF ITER-Like antenna (ILA) [14]. The antennae layout is illustrated in figure 1.…”

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confidence: 99%

JET intrinsic rotation studies in plasmas with a high normalized beta and varying toroidal field ripple

Nave

Eriksson

Giroud

et al. 2012

Plasma Phys. Control. Fusion

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Understanding the origin of rotation in Ion Cyclotron Resonance Frequency (ICRF) heated plasmas is important for predictions for burning plasmas sustained by alpha particles, being characterized by a large population of fast ions and no external momentum input. The angular velocity of the plasma column has been measured in JET H-mode plasmas with pure ICRF heating for both the standard low toroidal magnetic ripple configuration, of about ~ 0.08% and, for increased ripple values up to 1.5 % [1]. These new JET rotation data were compared with the multi-machine scaling of ref. [2] for the Alfven-Mach number and with the scaling for the velocity change from L-mode into H-mode. The JET data do not fit well any of these scalings that were derived for plasmas that are co-rotating with respect to the plasma-current.With the standard low ripple configuration, JET plasmas with large ICRF heating power and normalized beta, βN ≈1.3, have a very small co-current rotation, with Alfven-Mach numbers significantly below those given by the rotation scaling of ref. [2]. In some cases the plasmas are actually counter-rotating. No significant difference between the H-mode and L-mode rotation is observed. Typically the H-mode velocities near the edge are lower than in Lmodes. With ripple values larger than the standard JET value, between 1% and 1.5%, H-mode plasmas were obtained where both the edge and the core counter rotated. I -IntroductionIntrinsic rotation can play a key role in the performance of future tokamak power plants where the momentum input will be small [3]. In present day tokamak experiments, rotation is mostly driven by the torque coming from the neutral beam injection (NBI). However, in reactors with high NBI power at high beam energy, the torque is expected to be small. The central toroidal rotation velocity for ITER H-mode plasmas with NBI power of 34 MW, was predicted to be in the range of 10-170 km/s [4]. This is lower than currently observed at JET for the same Prandtl number (ratio between momentum and ion heat diffusivity) and with NBI power less than 20 MW [5]. It is important to note that ITER simulations depend on options of momentum transport whose theory is still evolving. For instance, the ITER simulations of ref.[4] do not include any contribution from a momentum pinch which is found to exist in JET NBI discharges [6,7] and other tokamaks [8,9]. This inward pinch will modify the rotation profile in ITER, in particular the peaking of the rotation profile will increase. Understanding of momentum transport is crucial in order to reliably model rotation profiles in ITER and other future devices, however, this is not the scope of this paper. A good overview of momentum transport theory, covering also aspects like residual stress and up-down asymmetry that may affect significantly the rotation profile in ITER, is given in reference [10].As the NBI driven rotation in future machines is presumed to be small, the intrinsic plasma rotation, which occurs in the absence of momentum sources such as NBI, has...

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“…The tolerance to load variations during ELMs of the ITER-like antenna (ILA) [1] is achieved by setting the impedance at the internal conjugate T-points to low impedance (∼3 ). When operated in this configuration, arcing occurring around the T-junctions is not detected by the standard Voltage Standing Wave Ratio (VSWR) protection [2].…”

Section: Introductionmentioning

confidence: 99%