Stationary high-performance discharges in the DIII-D tokamak

Luce, T. C.; Wade, M. R.; Ferron, J. R.; Hyatt, A.W.; Kellman, A.G.; Kinsey, J. E.; Haye, R.J. La; Lasnier, C.J.; Murakami, M.; Politzer, Peter; Scoville, J.T.

doi:10.1088/0029-5515/43/5/304

Cited by 96 publications

(113 citation statements)

References 24 publications

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“…At pressures lower than the maximum achieved, there appear to be systematic trends in the type of MHD observed [9,10,13,16]. Small sawteeth are generally seen for In AUG and DIII-D, the fishbones tend to appear at higher density, while at lower density,…”

Section: Existence Domainsmentioning

confidence: 88%

Development of advanced inductive scenarios for ITER

et al. 2013

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Regression analysis on the multi-tokamak database has been performed, but it appears that the database is not conditioned sufficiently well to yield a new scaling for this type of plasma.Coordinated experiments on size scaling using the dimensionless parameter scaling approach find a weaker scaling with normalized gyroradius than the standard H-mode scaling. Preliminary studies on scaling with collision frequency show a favorable scaling stronger than the standard H-mode scaling. Coordinated modeling activity has resulted in successful benchmarking of modeling codes in the ITER regime. Validation of transport models using these codes on present-day expeirments is in progress, but no single model has been shown to capture the variations seen in the experiments. However, projection to ITER using these models is in general agreement with the favorable projections found with the empirical scalings.

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Section: Existence Domainsmentioning

confidence: 88%

Development of advanced inductive scenarios for ITER

et al. 2013

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“…The more deleterious 2/1 and 3/2 NTMs are not present during the hybrid type III ELM case or in the reference type I case. The residual MHD island (4/3 NTM) is about 3 cm wide and explains only partially the confinement degradation observed during the type III ELM regime (compared with the type I ELM case in which the 4/3 NTM is not present): the loss of confinement associated with the 4/3 NTM is estimated to be δH = 4 · (width/a) · (ρ 4/3 /a) 3 ≈ 5%, where a is the minor plasma radius and ρ 4/3 is the radial position of the q = 4/3 magnetic surface [16]. …”

Section: Mhd and Plasma Stabilitymentioning

confidence: 92%

Hybrid H-mode scenario with nitrogen seeding and type III ELMs in JET

Corre

Joffrin

Monier‐Garbet

et al. 2008

Plasma Phys. Control. Fusion

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The performance of the 'hybrid' H-mode regime (long pulse operation with high neutron fluency) has been extensively investigated in JET during the [2005][2006][2007] experimental campaign up to normalized pressure β N = 3, toroidal magnetic field B t = 1.7 T, with type I ELMs plasma edge conditions. The optimized external current drive sources, self-generated non-inductive bootstrap current and plasma core stability properties provide a good prospect of achieving a high fusion gain at reduced plasma current for long durations in ITER.One of the remaining issues is the erosion of the divertor target plates associated with the type I ELM regime. regime with a normalized pressure β N = 2.6 (P NBI ∼ 20-22 MW) and a thermal confinement factor of H * 98 (y, 2) ∼ 0.83 has been recently successfully developed on JET with nitrogen seeding. This scenario shows good plasma edge condition (compatible with the future ITER-like wall on JET) and moderate MHD activity. In this paper, we report on the experimental development of the scenario (with plasma current I p = 1.7 MA and magnetic field B t = 1.7 T) and the trade-off between heat load reduction at the target plates and global confinement due to nitrogen seeding and type III ELM working conditions.

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“…Secondly, coupling of ICRH on D or minority H ions, mainly heats the electrons, while the aim of this experiment is to study ion ITBs which may be governed by different physics than those in the electron channel. At JET an ITB scenario has been developed that uses ICRH coupling to 3 He minority and predominantly heats the ions, as long as the 3 He minority concentration, which is controlled in real-time, is kept below 8% [14]. At a magnetic field of B=3.45T (I p =2.5MA, q 95 =4.5), 37MHz ICRH provides central ion heating without coupling to other resonances.…”

Section: Experiments With Dominant Icrhmentioning

confidence: 99%

Internal transport barrier dynamics with plasma rotation in JET

et al. 2009

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Abstract. At JET the dynamics of Internal Transport Barriers (ITBs) has been explored by trying to decouple the effects of heating on one hand and torque on the other with the ultimate objective of identifying the minimum torque required for the formation of transport barriers. The experiments shed light on the physics behind the initial trigger for ITBs, which often shows to be linked to the shape of the q profile and magnetic shear, while the further development was influenced by the strength of the rotational shear. In discharges with a small amount of rotational shear ITBs were triggered, which suggest that the rotational shear is not the dominant factor in the triggering process. However, the subsequent growth of the barrier was limited if the rotational shear was too low at the time of triggering. This growth phase may be highly non-linear, with several possible positive feedback loops, such as the increases of the toroidal and poloidal component of the rotational shear caused by the ITB itself.

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Stationary high-performance discharges in the DIII-D tokamak

Cited by 96 publications

References 24 publications

Development of advanced inductive scenarios for ITER

Development of advanced inductive scenarios for ITER

Hybrid H-mode scenario with nitrogen seeding and type III ELMs in JET

Internal transport barrier dynamics with plasma rotation in JET

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