Properties of the LHD plasmas with a large island—super dense core plasma and island healing

Ohyabu, N.; Morisaki, T.; Masuzaki, S.; Sakamoto, R.; Kobayashi, M.; Miyazawa, J.; Shoji, M.; Funaba, H.; Harris, J. H.; Hirooka, Y.; Inagaki, S.; Itoh, K.; Narihara, K.; Nakajima, N.; Narushima, Y.; Ohdachi, S.; Peterson, B.J.; Sakakibara, S.; Sánchez, Raúl; Tanaka, K.; Watanabe, Kunihiko; Yokoyama, M.; Ida, K.; Shimozuma, Τ.; Yamada, H.; Nagayama, Y.; Kaneko, O.; Mutoh, T.; Kawahata, K.; Komori, A.; Sudo, S.; Motojima, O.

doi:10.1088/0741-3335/48/12b/s35

Cited by 11 publications

(12 citation statements)

References 28 publications

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“…The absorbed power was superposed with the same weight ignoring the effect of interference. High density plasma with an internal diffusion barrier (IDB) [10] with the following profiles of electron density and temperatures of ions and electrons were supposed, n e = n e0 [0.8 exp{−(ρ/0.35) 2.5 } + 0.1(1 − ρ 6.5 ) + 0.1], (7) T i,e = T i,e0 (1 − ρ 4 ).…”

Section: Ray Tracing Calculation Of Icrf Wave In Helical Reactormentioning

confidence: 99%

ICRF Heating in Helical Reactor

Saito

Seki

Kumazawa

et al. 2010

Plasma and Fusion Research

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ICRF heating is a favorable high-density plasma heating method, since the ICRF wave can propagate in high-density plasma. ICRF heating in a helical reactor was calculated by using an antenna code and a ray tracing code assuming high-density plasma without resonance layers of α-particles in the plasma core. Enough loading resistance and a low electric field inside the ICRF antenna was obtained. Strong heating of plasma is expected in high-density plasma by heating electron and tritium, especially with the configuration of the second harmonic resonance layer of tritium on the magnetic axis shifted onto the saddle point.

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Section: Ray Tracing Calculation Of Icrf Wave In Helical Reactormentioning

confidence: 99%

ICRF Heating in Helical Reactor

Saito

Seki

Kumazawa

et al. 2010

Plasma and Fusion Research

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“…The LHD super dense core discharges with internal diffusion barriers [35] should also be investigated in the future with new tools, because at the moment only the ideal nested surfaces without magnetic islands are considered in our 3D bootstrap codes.…”

Section: Discussionmentioning

confidence: 99%

Bootstrap current calculations with the SPBSC and the VENUS+δf codes for the Large Helical Device

Isaev¹,

Watanabe²,

Cooper³

et al. 2009

Nucl. Fusion

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Total bootstrap current calculations with the updated VENUS+δf code that incorporates energy convolution and the momentum correction technique have been performed for the reference tokamak JT-60U cases and for the experimental Large Helical Device (LHD, NIFS, Japan) configurations with different magnetic axis positions. The VENUS+δf results have been compared with the corresponding tokamak results of the neoclassical bootstrap current models for the general axisymmetric equilibria and arbitrary collisionality regime, as well as with the corresponding 3D SPBSC code numerical predictions and with the LHD experimental tendency.

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“…The NBI has played an important role to obtain the performance of the LHD plasmas [56][57][58][59]. The maximum total power injected with three negative NBIs is more than 16 MW in the LHD experiment.…”

Section: Nbimentioning

confidence: 99%