A. Fujisawa
Current Organizations / Institutes
The organizations/institutes from the scholar's latest article
Previous Organizations / Institutes
The organizations / institutes from the scholar's other articles in the past ten years
Research Subjects
A. Fujisawa has a total of 156 co-authors. Here are the top co-authors by number of shared publications:
- Katsumi Ida
National Institute for Fusion Science, National Institutes of Natural Sciences 1 , Toki 509-5292
10 shared publications - Shoichi Okamura
National Institute for Fusion Science, National Institutes of Natural Sciences
9 shared publications - K. Toi
National Institute for Fusion Science, Toki, Japan
7 shared publications H. Iguchi
RIAM, Kyushu University, Kasuga, JAPAN
6 shared publicationsK. Matsuoka
RIAM, Kyushu University, Fukuoka 816-8580, Japan
6 shared publicationsK Matsuoka
5 shared publications
Latest Publications
- 19 March 2014
- Published by Physical Society of Japan
Scrape Off Layer Flow Characteristics in the Spherical Tokamak QUEST
- 19 March 2014
- Published by Physical Society of Japan
Scrape Off Layer Flow Characteristics in the Spherical Tokamak QUEST
- 1 February 2014
- Published by IOP Publishing in Nuclear Fusion
- Vol. 54 (2) , 23010
Role of energetic electrons during current ramp-up and production of high poloidal beta plasma in non-inductive current drive on QUEST
- 1 February 2014
- Published by IOP Publishing in Nuclear Fusion
- Vol. 54 (2) , 23010
Role of energetic electrons during current ramp-up and production of high poloidal beta plasma in non-inductive current drive on QUEST
- 28 December 2011
- Published by AIP Publishing in AIP Conference Proceedings
- Vol. 1406 (1) , 473
Electron Cyclotron ∕ Bernstein Wave Heating and Current Drive Experiments using Phased-array Antenna in QUEST
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 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 was attained in the 17 s plasma sustainment.- 28 December 2011
- Published by AIP Publishing in AIP Conference Proceedings
- Vol. 1406 (1) , 473
Electron Cyclotron ∕ Bernstein Wave Heating and Current Drive Experiments using Phased-array Antenna in QUEST
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 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 was attained in the 17 s plasma sustainment.- 24 October 2006
- Published by IOP Publishing in Plasma Physics and Controlled Fusion
- Vol. 48 (11) , 1683-1692
Scaling of power threshold for edge transport barrier formation in CHS with density, magnetic field and magnetic configuration
- 24 October 2006
- Published by IOP Publishing in Plasma Physics and Controlled Fusion
- Vol. 48 (11) , 1683-1692
Scaling of power threshold for edge transport barrier formation in CHS with density, magnetic field and magnetic configuration
- 6 April 2004
- Published by IOP Publishing in Plasma Physics and Controlled Fusion
- Vol. 46 (5A) , A113-A119
Edge transport barrier formation in compact helical system
- 6 April 2004
- Published by IOP Publishing in Plasma Physics and Controlled Fusion
- Vol. 46 (5A) , A113-A119
Edge transport barrier formation in compact helical system
- 6 April 2004
- Published by IOP Publishing in Plasma Physics and Controlled Fusion
- Vol. 46 (5A) , A45-A50
Comparison of electron internal transport barriers in the large helical device and JT-60U plasmas
- 6 April 2004
- Published by IOP Publishing in Plasma Physics and Controlled Fusion
- Vol. 46 (5A) , A45-A50
Comparison of electron internal transport barriers in the large helical device and JT-60U plasmas
- 6 April 2004
- Published by IOP Publishing in Plasma Physics and Controlled Fusion
- Vol. 46 (5A) , A35-A43
Formation conditions for electron internal transport barriers in JT-60U plasmas
- 6 April 2004
- Published by IOP Publishing in Plasma Physics and Controlled Fusion
- Vol. 46 (5A) , A35-A43
Formation conditions for electron internal transport barriers in JT-60U plasmas
- 26 April 2002
- Published by IOP Publishing in Plasma Physics and Controlled Fusion
- Vol. 44 (5A) , A225-A230
Magnetic field structure preferable to E×B shear flow generation in a quasi-axisymmetric stellarator CHS-qa
Viscous damping and effective helical ripple have been quantitatively estimated for a proposed quasi-axisymmetric stellarator CHS-qa configuration. It is predicted that viscous damping against plasma flow in CHS-qa is low enough to sustain large E × B shear as observed in the H-modes and internal transport barriers in many tokamaks. Effective helical ripple in CHS-qa is adjusted to be on the order of 10-2 or lower, which is suitable to trigger transport barriers due to non-ambipolar neoclassical fluxes peculiar to conventional helical devices. For experimental flexibility, viscous damping and effective helical ripple in CHS-qa can be extensively controlled over a range of about one order by modifying modular coil currents.
- 26 April 2002
- Published by IOP Publishing in Plasma Physics and Controlled Fusion
- Vol. 44 (5A) , A225-A230
Magnetic field structure preferable to E×B shear flow generation in a quasi-axisymmetric stellarator CHS-qa
Viscous damping and effective helical ripple have been quantitatively estimated for a proposed quasi-axisymmetric stellarator CHS-qa configuration. It is predicted that viscous damping against plasma flow in CHS-qa is low enough to sustain large E × B shear as observed in the H-modes and internal transport barriers in many tokamaks. Effective helical ripple in CHS-qa is adjusted to be on the order of 10-2 or lower, which is suitable to trigger transport barriers due to non-ambipolar neoclassical fluxes peculiar to conventional helical devices. For experimental flexibility, viscous damping and effective helical ripple in CHS-qa can be extensively controlled over a range of about one order by modifying modular coil currents.
- 26 April 2002
- Published by IOP Publishing in Plasma Physics and Controlled Fusion
- Vol. 44 (5A) , A189-A195
Bootstrap current analysis for neoclassical internal transport barrier discharge of CHS
The bootstrap current analyses have been carried out for two different kinds of discharges of compact helical system (CHS) heliotron/torsatron. One is the electron cyclotron resonance heating (ECRH) discharge with moderate density and without internal transport barrier (ITB) (ne(0)>0.5×1019 m-3, Te(0)ne19 m-3) with ECRH and co-NBI. The NC ITB mode is characterized by steeply peaked electron temperature profile (Te(0)>2.0 keV) in the core domain and large positive radial electric field (Er~ + 10 kV m-1). The dependence of toroidal net current on magnetic axis position Rax was investigated for ECRH discharges without ITB. There is good agreement in the tendency of Rax dependence of the net toroidal current between experiment and neoclassical calculation. In the NC ITB discharges, the experimental net current including both bootstrap and beam-driven current is largely reduced compared with that in the L-mode and it drops to almost zero. It seems as if the reversal of bootstrap current takes place in the NC ITB phase but such a view is inconsistent with neoclassical prediction. The observed reduction of the plasma current in the ITB phase is not explained by the neoclassical theory.
- 26 April 2002
- Published by IOP Publishing in Plasma Physics and Controlled Fusion
- Vol. 44 (5A) , A189-A195
Bootstrap current analysis for neoclassical internal transport barrier discharge of CHS
The bootstrap current analyses have been carried out for two different kinds of discharges of compact helical system (CHS) heliotron/torsatron. One is the electron cyclotron resonance heating (ECRH) discharge with moderate density and without internal transport barrier (ITB) (ne(0)>0.5×1019 m-3, Te(0)ne19 m-3) with ECRH and co-NBI. The NC ITB mode is characterized by steeply peaked electron temperature profile (Te(0)>2.0 keV) in the core domain and large positive radial electric field (Er~ + 10 kV m-1). The dependence of toroidal net current on magnetic axis position Rax was investigated for ECRH discharges without ITB. There is good agreement in the tendency of Rax dependence of the net toroidal current between experiment and neoclassical calculation. In the NC ITB discharges, the experimental net current including both bootstrap and beam-driven current is largely reduced compared with that in the L-mode and it drops to almost zero. It seems as if the reversal of bootstrap current takes place in the NC ITB phase but such a view is inconsistent with neoclassical prediction. The observed reduction of the plasma current in the ITB phase is not explained by the neoclassical theory.
- 1 May 2001
- Published by IOP Publishing in Nuclear Fusion
- Vol. 41 (5) , 575-584
Observation of bifurcation properties of radial electric fields using a heavy ion beam probe
The bifurcated nature of the potential profile of a toroidal helical plasma is investigated in CHS using a heavy ion beam probe. The measurements reveal that three main branches of potential profile exist in ECR heated plasmas with a low density of e ≈ 0.5 × 1019m-3. The branches with higher central potential exhibit a rather strong radial electric field shear that should result in fluctuation reduction and formation of a transport barrier. An analysis of the pulsating behaviour in the potential suggests the existence of a fine structure in the potential profiles between the main branches. Lissajous and histogram expressions are useful in extracting the bifurcation characteristics of the potential structure.
- 1 May 2001
- Published by IOP Publishing in Nuclear Fusion
- Vol. 41 (5) , 575-584
Observation of bifurcation properties of radial electric fields using a heavy ion beam probe
The bifurcated nature of the potential profile of a toroidal helical plasma is investigated in CHS using a heavy ion beam probe. The measurements reveal that three main branches of potential profile exist in ECR heated plasmas with a low density of e ≈ 0.5 × 1019m-3. The branches with higher central potential exhibit a rather strong radial electric field shear that should result in fluctuation reduction and formation of a transport barrier. An analysis of the pulsating behaviour in the potential suggests the existence of a fine structure in the potential profiles between the main branches. Lissajous and histogram expressions are useful in extracting the bifurcation characteristics of the potential structure.