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Dive into the research topics where Aki Higashijima is active.

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Featured researches published by Aki Higashijima.


Physics of Plasmas | 2012

Non-inductive current start-up assisted by energetic electrons in Q-shu University experiment with steady-state spherical tokamak

M. Ishiguro; K. Hanada; Haiqing Liu; H. Zushi; Kazuo Nakamura; A. Fujisawa; H. Idei; Y. Nagashima; M. Hasegawa; S. Tashima; Y. Takase; Yasuaki Kishimoto; Osamu Mitarai; Shoji Kawasaki; Hisatoshi Nakashima; Aki Higashijima

After intensive discharge cleaning of the chamber wall, non-inductive current start-up experiments have been successfully performed in QUEST in moderate vertical fields of about 1.0–1.5 mT with positive n-index. Simultaneously, with increasing plasma current, an asymmetric toroidal flow of energetic electrons was observed and direct measurements of current driven by this asymmetric flow were taken with a newly developed Langmuir probe technique. A numerical study of the energetic electron orbits indicates that the total current is enough to play a dominant role in the formation of a closed flux surface in QUEST.


Nuclear Fusion | 2007

A study on temperature effects on hydrogen recycling and molybdenum impurity emission from a movable limiter in TRIAM-1M Tokamak

R. Bhattacharyay; H. Zushi; K. Nakashima; Taiichi Shikama; M. Sakamoto; N. Yoshida; Shinichiro Kado; Keiji Sawada; Y. Hirooka; K. Nakamura; K. Hanada; H. Idei; M. Hasegawa; K.N. Sato; M. Ogawa; O. Takaki; K. Sasaki; H. Xu; S. Kawasaki; Hiroshi Nakashima; Aki Higashijima

In order to investigate the surface temperature effects on plasma fuel recycling and impurity release from the plasma facing components, plasma discharges have been performed under selected plasma–wall interaction (PWI) conditions in the high-field superconducting tokamak, TRIAM-1M. By moving a water-cooled molybdenum movable limiter (ML) beyond the last closed flux surface, as defined by poloidal limiters, the surface temperature profile on it is varied. Hot spots have been observed on the ML surface in such conditions. The release behaviour of fuel as well as impurity particles from the ML surface has been studied as a function of hot spot temperature (Thot) by means of wide range spectroscopy (200–1600 nm). A critical Thot is found to be ~2100 K above which the emission of both hydrogen and impurity particles enhances significantly. This is indicative of some thermally activated process playing an important role in PWIs between the limiter and the edge plasma. With the rise in hot spot temperature localized PWI at the ML is found to dominate the global recycling even when external fuelling is stopped.


Nuclear Fusion | 2006

Electron cyclotron current drive experiments in LHCD plasmas using a remote steering antenna on the TRIAM-1M tokamak

H. Idei; K. Hanada; H. Zushi; K. Ohkubo; M. Hasegawa; S. Kubo; S. Nishi; A. Fukuyama; K.N. Sato; Kazuo Nakamura; M. Sakamoto; Atsuhiro Iyomasa; S. Kawasaki; Hiroshi Nakashima; Aki Higashijima; T. Notake; T. Shimozuma; S. Ito; Hiroyuki Hoshika; N. Maezono; K. Nakashima; M. Ogawa

A remote steering antenna was recently developed for electron cyclotron heating and current drive (ECH/ECCD) experiments on the TRIAM-1M tokamak. This is the first application of the remote steering antenna concept for ECH/ECCD experiments, which have conditions relevant to the International Thermonuclear Experimental Reactor (ITER). Fundamental ECH and ECCD experiments were conducted in the ITER frequency from the low field using this antenna system. In addition to the angles near 0°, the launcher was a symmetric direction antenna with an extended steering-angle capability of ±(8°–19°). The output beam from the antenna was a well-defined Gaussian with a proper steering angle. The Gaussian content and the steering-angle accuracy were 0.85 and −0.5°, respectively. The high power tests measured the antenna transmission efficiency at 0.90–0.94. The efficiencies obtained in the low and high power tests were consistent with the calculations using higher-order modes. In order to excite the pure O/X-modes in the oblique injection, two polarizers were used to control the elliptical polarization of the incident beam for the ECCD experiments. The fundamental O/X-mode ECH/ECCD was applied to lower hyrid current drive plasmas at the optimized incident polarization. In the X-mode experiment, at medium density (~1 × 1019 m−3), clear differences in the plasma current and the hard x-ray intensity were observed between the co- and counter-steering injections due to the ECCD effect on the coupling of forward fast electrons.


Review of Scientific Instruments | 2011

Direct measurement of energetic electron flow in Q-shu University experiment with steady-state spherical tokamak

M. Ishiguro; K. Hanada; Haiqing Liu; H. Zushi; Naoaki Yoshida; Tomonori Tokunaga; Kazuo Nakamura; A. Fujisawa; H. Idei; M. Sakamoto; M. Hasegawa; S. Tashima; Y. Takase; T. Maekawa; Yasuaki Kishimoto; Osamu Mitarai; Shoji Kawasaki; Hisatoshi Nakashima; Aki Higashijima

In magnetized plasmas, the presence of a significant number of energetic electrons has been observed but quantitative characteristics of these electrons are proving difficult to investigate. A Langmuir probe offers a means to provide quantitative measurement of these energetic electrons that takes into account electron emissions (secondary electron emission and electron reflection) from the probe tips and sheath expansion around the probe tips caused by a considerable negative potential. In this paper, these effects are experimentally confirmed and an analytical means to measure energetic electron characteristics are proposed. An analysis of plasmas produced by a high frequency wave is then applied leading to the successful detection of an asymmetric flow of energetic electrons. The estimated electron temperature and current density were approximately 4-5 keV and 2-3 kA/m(2).


Physics of Plasmas | 2011

Investigations of the radial propagation of blob-like structure in a non-confined electron cyclotron resonance heated plasma on Q-shu University Experiment with a Steady-State Spherical Tokamak

Ryota Ogata; K. Hanada; N. Nishino; Haiqing Liu; H. Zushi; M. Ishiguro; Teruaki Ikeda; Kazuo Nakamura; A. Fujisawa; H. Idei; M. Hasegawa; Shoji Kawasaki; Hisatoshi Nakashima; Aki Higashijima

A study of radial propagation and electric fields induced by charge separation in blob-like structures has been performed in a non-confined cylindrical electron cyclotron resonance heating plasma on Q-shu University Experiment with a Steady-State Spherical Tokamak using a fast-speed camera and a Langmuir probe. The radial propagation of the blob-like structures is found to be driven by E × B drift. Moreover, these blob-like structures were found to have been accelerated, and the property of the measured radial velocities agrees with the previously proposed model [C. Theiler et al., Phys. Rev. Lett. 103, 065001 (2009)]. Although the dependence of the radial velocity on the connection length of the magnetic field appeared to be different, a plausible explanation based on enhanced short-circuiting of the current path can be proposed.


Physics of Plasmas | 2008

Study of magnetic configuration effects on plasma boundary and measurement of edge electron density in the spherical tokamak compact plasma wall interaction experimental device using Li sheet beam

R. Bhattacharyay; H. Zushi; T. Morisaki; Y. Inada; T. Kikukawa; S. Watanabe; K. Sasaki; T. Ryoukai; M. Hasegawa; K. Hanada; K.N. Sato; K. Nakamura; M. Sakamoto; H. Idei; Tomokazu Yoshinaga; S. Kawasaki; Hiroshi Nakashima; Aki Higashijima

Two-dimensional lithium beam imaging technique has been applied in the spherical tokamak CPD (compact plasma wall interaction experimental device) to study the effects of magnetic field configurations on rf plasma boundary in the absence of any plasma current, and also for the measurement of a two-dimensional edge electron density profile. With the present working condition of the diagnostics, the minimum measured electron density can be ∼1.0×1016m−3; this is considered to be the definition for the plasma boundary. The performance of the lithium sheet beam is absolutely calibrated using a quartz crystal monitor. Experimental results reveal that magnetic field configuration, either mirror or so-called null, critically affects the rf plasma boundary. A sharp lower boundary is found to exist in magnetic null configuration, which is quite different from that in the weak mirror configuration. Theoretical calculations of particle drift orbit and magnetic connection length (wall-to-wall) suggest that only mirror...


15th International Congress on Plasma Physics, ICPP 2010 and 13th Latin American Workshop on Plasma Physics, LAWPP 2010 | 2014

Investigation of Non-inductive Plasma Current Start-up by RF on QUEST

M. Ishiguro; K. Hanada; Hiqing Liu; Ryota Ogata; M. Isobe; S. Tashima; H. Zushi; Khonosuke Sato; A. Fujisawa; Kazuo Nakamura; H. Idei; M. Sakamoto; M. Hasegawa; Y. Takase; T. Maekawa; Yasuaki Kishimoto; Osamu Mitarai; Shoji Kawasaki; Hisatoshi Nakashima; Aki Higashijima

Formations of a closed flux surface (CFS) on QUEST are achieved by fully non-inductive current start-up driven by RF, which is 8.2GHz in frequency and more than 40kW in power. It found that appropriate magnetic configuration with positive n-index and reduction of particle recycling was crucial to achieve the non-inductive plasma current start-up (PCS) successfully. Especially the controllability of particle recycling should be improved by wall conditioning based on successive plasma production and wall cleaning with electron cyclotron resonance heating (ECR) plasmas induced by RF in frequency of 2.45GHz.


ieee symposium on fusion engineering | 2015

Current density calculation from particle orbit in RF-driven divertor plasma on QUEST

Mahbub Alam; Kazuo Nakamura; M. Hasegawa; K. Tokunaga; K. Araki; H. Zushi; K. Hanada; A. Fujisawa; H. Idei; Y. Nagashima; Shoji Kawasaki; Hisatoshi Nakashima; Aki Higashijima; Fan Xia; Osamu Mitarai

We investigate and calculate particle orbits and the effect of particle orbits on plasma current density for nonrelativistic resonance condition in the present RF-driven divertor plasma on QUEST. We surveyed particle orbits for different values of parallel refractive index, particle initial positions and pitch angles on fundamental and second harmonic resonance conditions. We observed that for fundamental harmonic resonance condition when particle orbits are plotted on the poloidal cross-section for positive values of parallel refractive index, these orbits are started from the resonance surface and produced their orbits around the LCFS (Large Closed Flux Surface). These orbits carry positive current. When particle orbits are plotted for negative values of parallel refractive index, these orbits are started from resonance surface, but remained at the inside of the LCFS. These orbits carry negative current that reduced the overall plasma current. For second harmonic resonance condition when particle orbits are plotted on the poloidal cross-section most of the orbits remained in inside the LCFS and carry positive current. When we consider the value of parallel refractive index -0.4 and +0.4 some particle orbits arrived at the limiter and become lost particles. On the other hand, when we consider particle initial positions 0.16 m or more vertically far from the mid plane some banana orbits are produced. These banana orbits make the current density profile maximum at low field side region. From this calculation we got a hollow current density profile with current density peak at the low field side region outside of the LCFS. From this calculation we can infer that parabolic current density profile is possible, if we set the resonance surface outside of the magnetic axis by increasing the toroidal magnetic field coil current and make the plasma position inward by increasing vertical field coil current.


Plasma Science & Technology | 2009

Two Dimensional Density Fluctuation Measurements During the Non-Inductive Current Ramp-up Phase in the Compact Plasma Wall Interaction Experimental Device CPD

H. Zushi; T. Ryoukai; K. Kikukawa; T. Morisaki; R. Bhattacharyay; Tomokazu Yoshinaga; K. Hanada; T. Sakimura; H. Idei; K. Dono; N. Nishino; H. Honma; S. Tashima; T. Mutoh; S. Kubo; K. Nagasaki; M. Sakamoto; Y. Nakashima; Y. Higashizono; K.N. Sato; K. Nakamura; M. Hasegawa; S. Kawasaki; Hiroshi Nakashima; Aki Higashijima

Two-dimensional structure of density fluctuations is examined during the current jump phase, indicating a change from the open magnetic fields to the closed ones. During the smooth current ramp-up phase the two-dimensional contour of the LiI intensity shows vertically alignment, consistent with the magnetic surfaces. At the inflection point in Ip ramp-up the LiI intensity contour becomes flat in the observation regime and then suddenly a steep gradient and higher intensity regime are formed in the vertical direction. This higher intensity corresponds to a burst of LiI waveform. According to these changes in the contour, it is found that, within ±1 ms around the burst of LiI, a low frequency coherent wave with a long wavelength rapidly grows. The relations with other signals (magnetic flux and microwave stray power) are discussed with respect to the topological change in the magnetic configuration and mode conversion of the incident electromagnetic waves.


Nuclear Fusion | 2008

Effects of magnetic field and target plasma on the penetration behaviour of compact toroid plasma by heat load measurements in CPD

R. Bhattacharyay; H. Zushi; N. Fukumoto; M. Nagata; N. Nishino; H. Honma; K. Kawakami; N. Yoshida; S. Kawasaki; Tomokazu Yoshinaga; K. Sasaki; M. Hasegawa; K.N. Sato; M. Sakamoto; K. Nakamura; H. Idei; Hiroshi Nakashima; Aki Higashijima

Compact toroid (CT) injection experiments have recently been carried out in a compact plasma wall interaction experimental device (CPD) in the presence of toroidal as well as poloidal magnetic field and low density RF target plasma. Spectroscopic studies have been carried out using an IR camera, an IR spectrometer and an Hα monitor to estimate the heat load deposition on the target and also to study the magnetic field as well as RF target plasma effects on CT plasma penetration behaviour. Using IR camera imaging of the target plate, heat load deposition on it has been estimated from the observed temperature rise of the plate and has been compared with the energy content of CT plasma. The estimation suggests that nearly 700 J of energy is uniformly deposited on the target plate under vacuum condition without any magnetic field. On the other hand, post exposure analysis of target plate using scanning electron microscopy has indicated local melting of the target plate. It has been observed that radial penetration of CT towards the target plate is reduced with the increase in the external magnetic field, both toroidal and poloidal. Moreover, the presence of RF target plasma in external magnetic fields seems to change the CT penetration behaviour significantly.

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