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Dive into the research topics where K. Nakamura is active.

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Featured researches published by K. Nakamura.


Plasma Physics and Controlled Fusion | 2004

Edge transport barrier formation in compact helical system

S. Okamura; T. Minami; T. Oishi; C. Suzuki; K. Ida; M. Isobe; Y. Yoshimura; K. Nagaoka; K. Toi; A. Fujisawa; T. Akiyama; Harukazu Iguchi; R. Ikeda; Shinichiro Kado; K. Matsuoka; H Matsushita; K. Nakamura; Haruhisa Nakano; S. Nishimura; M. Nishiura; S. Ohshima; A. Shimizu; S. Takagi; C. Takahashi; Masaki Takeuchi; M. Yoshinuma

The edge transport barrier (ETB) for particle transport is formed in the neutral beam (NB) heated hydrogen discharges in compact helical system (CHS). The transition to the ETB formation and the back transition are controlled by the heating power. The existence of the heating power threshold is confirmed and it is roughly proportional to the density. The Ha emission signal shows a clear drop at the transition (the timescale of signal decrease is ∼1 ms for the high heating power case). The ETB formation continues for the full duration of NB injection (100 ms) with a moderate level of radiation power loss. Local density profile measurement shows increase of the edge density and the movement of the density gradient region towards the edge.


Review of Scientific Instruments | 2005

Two-dimensional diagnostic of edge plasma structure using a lithium beam probe in a compact helical system

K. Nakamura; Harukazu Iguchi; M. Ueda; Z. Narihiro; A. Shimizu; T. Morisaki; M. Isobe; C. Takahashi; S. Nishimura; C. Suzuki; Y. Yoshimura; K. Nagaoka; T. Minami; M. Yoshinuma; K. Ida; S. Okamura; K. Matsuoka

A neutral lithium beam probe for two-dimensional diagnosis of edge plasmas has been designed and installed on the compact helical system. A lithium beam with an energy of 15keV and a current of 0.1mA is used. The spatial resolution is about 10mm, and the time response is about 10ms. The beam penetration depth is expressed in terms of the line integral density ⟨nel⟩, which is about 2×1018m−2. The beam injection angle can be varied and the observation point covers the edge and separatrix region of the helical diverter configuration. Two-dimensional electron density profiles for electron cyclotron heating and neutral beam injection (NBI) heated plasmas are obtained near and outside the last closed flux surface (LCFS). Analysis for two-dimensional density profile reconstruction indicates that significant amounts of surface plasma are confined outside the LCFS for NBI plasmas even though the ergodic layer is cut by the vacuum chamber wall (inboard limiter configuration). The usefullness of this new two-dimensi...


Nuclear Fusion | 2005

Edge and internal transport barrier formations in CHS

S. Okamura; T. Minami; T. Akiyama; T. Oishi; A. Fujisawa; K. Ida; H. Iguchi; M. Isobe; Shinichiro Kado; K. Nagaoka; K. Nakamura; S. Nishimura; K. Matsuoka; H. Matsushita; H. Nakano; M. Nishiura; S. Ohshima; A. Shimizu; C. Suzuki; C. Takahashi; K. Toi; Y. Yoshimura; M. Yoshinuma

Edge transport barrier (ETB) formation was observed in a compact helical system. A sharp decrease in Hα emission indicates the quick transition of edge particle transport. The increase in the density gradient at the edge was measured by using various profile diagnostics. The transition process has a slowly developing pre-phase, and a quick transition for which the fastest case is less than 0.2 ms. There exists a heating power threshold which is roughly proportional to the density and the magnetic field. The transition and back transition is controlled by the heating power. The magnetic configuration effect on ETB formation was also studied. The local density measurement by beam emission spectroscopy shows intermittent bursts of low frequency fluctuations during the ETB formation phase. When the initial density profile is very hollow, ETB formation together with the electron temperature increase (electron internal transport barrier) in the core region, was observed for the NBI discharges without ECH.


Review of Scientific Instruments | 2012

Fast visible imaging and edge turbulence analysis in QUESTa)

Santanu Banerjee; H. Zushi; N. Nishino; Y. Nagashima; K. Hanada; M. Ishiguro; T. Ryoukai; S. Tashima; T. Inoue; K. Nakamura; H. Idei; M. Hasegawa; A. Fujisawa; K. Matsuoka

A fast visible imaging system is installed on the spherical tokamak QUEST to study edge turbulence. The camera uses a complementary metal-oxide semiconductor detector with a maximum resolution of 1024 × 1024 at 7000 frames∕s (fps) and can achieve 775 kfps at a resolution of 128 × 24. In this paper, we present the salient features of the system and its application to study edge turbulence in 8.2 GHz ECRH driven slab plasma, without plasma current. Vertical magnetic field (B(z)) topology is varied with three sets of poloidal field (PF) coils and the variation in the edge turbulence is investigated as a function of the B(z) strength and curvature. Fluctuation amplitude was highest for the shallow PF well. Cross-correlation coefficient shows distinct coherent mode along z direction at the steep density gradient region and it grows with the PF mirror ratio.


Physics of Plasmas | 2014

Role of stochasticity in turbulence and convective intermittent transport at the scrape off layer of Ohmic plasma in QUEST

Santanu Banerjee; H. Zushi; N. Nishino; K. Hanada; M. Ishiguro; S. Tashima; H.Q. Liu; Kishore Mishra; K. Nakamura; H. Idei; M. Hasegawa; A. Fujisawa; Y. Nagashima; K. Matsuoka

Statistical features of fluctuations are investigated using the fast camera imaging technique in the scrape of layer (SOL) of electron cyclotron resonance heated Ohmic plasma. Fluctuations in the SOL towards low field side are dominated by coherent convective structures (blobs). Two dimensional structures of the higher order moments (skewness s and kurtosis k) representing the shape of probability density function (PDF) are studied. s and k are seen to be functions of the magnetic field lines. s and k are consistently higher towards the bottom half of the vessel in the SOL showing the blob trajectory along the field lines from the top towards bottom of the vessel. Parabolic relation ( k=As2+C) is observed between s and k near the plasma boundary, featuring steep density gradient region and at the far SOL. The coefficient A, obtained experimentally, indicates a shift of prominence from pure drift-wave instabilities towards fully developed turbulence. Numerical coefficients characterizing the Pearson system...


Journal of Nuclear Materials | 2003

Two-dimensional diagnostics of edge and divertor region of toroidal helical plasmas using a lithium beam probe

K. Nakamura; H. Iguchi; M. Ueda; T. Morisaki; M. Isobe; K. Ida; C. Takahashi; S. Okamura; K. Matsuoka

Abstract A two-dimensional neutral lithium beam probe has been designed and installed on the Compact Helical System (CHS) to study the edge and separatrix region of l =2 helical divertor configuration. A 10–20 keV beam with equivalent neutral beam current of 0.1 mA is injected. Light emission from the injected beam by electron impact excitation (LiI/670.8 nm) is collected by an eight-channel detector system using optical band-pass filters and Avalanche Photodiodes. The injection beam line is mechanically tilted to cover the area two-dimensionally. The total system has been calibrated by injecting the beam into the helium-gas-filled CHS vacuum chamber. Detailed measurements of two-dimensional structure of edge and divertor region are expected to contribute to studies of helical divertor concept and to improve understanding of the role of edge plasmas on core confinement as well.


Nuclear Fusion | 2007

Two-dimensional plasma structure in the edge region of the compact helical system

K. Nakamura; Harukazu Iguchi; J. Schweinzer; A. Shimizu; M. Isobe; C. Takahashi; S. Nishimura; C. Suzuki; Y. Yoshimura; K. Nagaoka; T. Minami; T. Akiyama; K. Ida; K. Matsuoka; S. Okamura

Two-dimensional edge plasma structures of the l = 2 helical system CHS have been investigated with the use of a neutral lithium beam probe. Two different types of edge magnetic configuration have been compared, namely, an inboard-wall limiter configuration and an ergodic magnetic divertor configuration which is intrinsic to non-axisymmetric helical devices. The scrape-off plasma in the limiter configuration is essentially one-dimensional and the radial scale length is well described by a simple diffusion model with finite connection length of the magnetic field line. While in the ergodic divertor configuration, edge plasma structure shows up?down asymmetry in the steady state near the outer separatrix region regardless of the symmetric magnetic structure. The asymmetry reverses when the magnetic field direction is reversed. Plasma shift is apparently in the direction of ion B ? ?B drift. The result suggests that plasma equilibrium in the ergodic layer is not determined simply by the magnetic field structure. The effect of plasma flow and drift motions would be important. Such asymmetry in plasma structure may induce non-uniform heat deposition on the divertor plates. Modelling of plasma equilibrium in the ergodic layer is necessary for practical helical divertor design.


RADIO FREQUENCY POWER IN PLASMAS: Proceedings of the 19th Topical Conference | 2011

Electron Cyclotron / Bernstein Wave Heating and Current Drive Experiments using Phased‐array Antenna in QUEST

H. Idei; H. Zushi; K. Hanada; K. Nakamura; A. Fujisawa; M. Hasegawa; N. Yoshida; Masanori Sakamoto; H. Watanebe; K. Tokunaga; Y. Nagashima; A. Ejiri; M. Sakaguchi; E. Kalinnikova; M. Ishiguro; S. Tashima; A. Fukuyama; H. Igami; S. Kubo; S.K. Sharma; Tomofumi Ryokai; Haiqing Liu; M. Isobe; K. Nagaoka; H. Nakanishi; N. Nishino; S. Kawasaki; Hiroshi Nakashima; A. Higashijima; Y. Takase

The phased‐array antenna system for Electron Cyclotron/Bernstein Wave Heating and Current Drive experiments has been developed in the QUEST. The antenna was designed to excite a pure O‐mode wave in the oblique injection for the O‐X‐B mode conversion experiments, and its good performances were confirmed at a low power level. The plasma current (<∼15u2009kA) with an aspect ratio of 1.5 was started up and sustained by only RF injection in the low‐density operations. The long pulse discharge of 10 kA was also attained for 37 s. The new density window to sustain the plasma current was observed in the high‐density plasmas. The single‐null divertor configuration with the high plasma current (<∼25u2009kA) was attained in the 17 s plasma sustainment.


Proceedings of the 12th Asia Pacific Physics Conference (APPC12) | 2014

Scrape Off Layer Flow Characteristics in the Spherical Tokamak QUEST

Santanu Banerjee; H. Zushi; N. Nishino; Y. Mahira; K. Nagaoka; S. Tashima; Y. Nagashima; K. Hanada; K. Nakamura; M. Hasegawa; A. Fujisawa; K. Matsuoka; Kasuga Koen

Poloidal component of the plasma flow along the field lines in the scrape off layer (SOL) is measured with fast visible imaging in QUEST. With the injection of electron cyclotron waves (ECW) a distinct mode appears at 0.75-0.8 kHz. Fluctuation structures feature long range correlation and propagate both poloidally and radially. Strong cross-field transport associated with the change in plasma configuration from inboard limiter towards inboard poloidal null-like, are most likely the reasons behind this ECW induced flow.


Fusion Science and Technology | 2007

Improved confinement and related physics study in the compact helical system

S. Okamura; T. Akiyama; A. Fujisawa; K. Ida; H. Iguchi; M. Isobe; Shinichiro Kado; T. Minami; K. Nagaoka; K. Nakamura; S. Nishimura; K. Matsuoka; H. Matsushita; H. Nakano; S. Ohshima; T. Oishi; A. Shimizu; C. Suzuki; C. Takahashi; K. Toi; Y. Yoshimura; M. Yoshinu

Abstract Various types of transport barriers have been studied in the Compact Helical System. In addition to the neoclassical transport barrier, the edge transport barrier (H-mode) was studied using the high-power heating of two coinjection neutral beam injections. A density pedestal is formed after the transition that is indicated by the drop of Hα emission signal. The heating power threshold for the transition was investigated by varying the heating power. Its dependence on the density and the magnetic field is close to the H-mode scaling obtained in tokamaks. The dependence of the power threshold on the magnetic field configuration was also found. Local density fluctuation was measured with beam emission spectroscopy, which observed harmonic oscillations appearing after the density pedestal was formed. For L-mode plasma, long-distance coherence of the potential fluctuations were measured with two sets of heavy ion beam probes (HIBPs). Those coherent modes are supposed to be the geodesic acoustic mode part of zonal flow. Turbulent particle flux was also measured with HIBP, and its change with internal transport barrier formation is demonstrated.

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K. Nagaoka

Graduate University for Advanced Studies

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M. Isobe

Graduate University for Advanced Studies

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