Hiroshi Yamada
Current Organizations / Institutes
The organizations/institutes from the scholar's latest article
Research Subjects
Hiroshi Yamada has a total of 102 co-authors. Here are the top co-authors by number of shared publications:
H. Funaba
National Institute for Fusion Science, 322‐6 Oroshi‐cho, Toki 509‐5292, Japan
3 shared publicationsS. Ohdachi
National Institute for Fusion Science, 322‐6 Oroshi‐cho, Toki 509‐5292, Japan
3 shared publicationsS. Sakakibara
National Institute for Fusion Science, 322‐6 Oroshi‐cho, Toki 509‐5292, Japan
3 shared publicationsA. Komori
National Institute for Fusion Science, Toki, Gifu 509-5292, Japan
2 shared publicationsA. Sagara
National Institute for Fusion Science, Toki, Gifu 509-5292, Japan
2 shared publicationsB.J. Peterson
National Institute for Fusion Science, Toki, Gifu 509-5292, Japan
2 shared publications
Latest Publications
- 1 January 2012
- Published by Springer Nature
- p. 1183-1215
Fusion Energy
- 23 July 2010
- Published by Wiley in Contributions to Plasma Physics
- Vol. 50 (6-7) , 480-486
Study of High‐Beta Plasmas in a Helical System
- 23 July 2010
- Published by Wiley in Contributions to Plasma Physics
- Vol. 50 (6-7) , 480-486
Study of High‐Beta Plasmas in a Helical System
- 1 August 2003
- Published by IOP Publishing in Nuclear Fusion
- Vol. 43 (8) , 749-755
Impact of heat deposition profile on global confinement of NBI heated plasmas in the LHD
Energy confinement and heat transport of net-current-free NBI heated plasmas in the large helical device (LHD) are discussed with emphasis on density and power deposition profile dependences. Although the apparent density dependence of the energy confinement time has been demonstrated in a wide parameter range in LHD, the loss of this dependence has been observed in the high density regime under specific conditions. Broad heat deposition due to off-axis alignment and shallow penetration of neutral beams degrades the global energy confinement while the local heat transport maintains a clear temperature dependence, lying between Bohm and gyro-Bohm characteristics. The central heat deposition tends towards an intrinsic density dependence like τE∝(n̄e/P)0.6 from the state where density dependence is lost. The broadening of the temperature profile due to the broad heat deposition profile contrasts with the invariant property that has been observed widely as profile resilience or stiffness in tokamak experiments. The confinement improvement as a result of the inward shift of the magnetic axis is obvious in the core region, which emphasizes the improvement of transport because of the geometry being unfavourable for the central heating of NBI in this configuration. The edge pressure, clearly, does not depend on the magnetic axis position. Unlike a tokamak H-mode, the edge pressure is determined by transport and can be increased by increasing the heating power.
- 1 August 2003
- Published by IOP Publishing in Nuclear Fusion
- Vol. 43 (8) , 749-755
Impact of heat deposition profile on global confinement of NBI heated plasmas in the LHD
Energy confinement and heat transport of net-current-free NBI heated plasmas in the large helical device (LHD) are discussed with emphasis on density and power deposition profile dependences. Although the apparent density dependence of the energy confinement time has been demonstrated in a wide parameter range in LHD, the loss of this dependence has been observed in the high density regime under specific conditions. Broad heat deposition due to off-axis alignment and shallow penetration of neutral beams degrades the global energy confinement while the local heat transport maintains a clear temperature dependence, lying between Bohm and gyro-Bohm characteristics. The central heat deposition tends towards an intrinsic density dependence like τE∝(n̄e/P)0.6 from the state where density dependence is lost. The broadening of the temperature profile due to the broad heat deposition profile contrasts with the invariant property that has been observed widely as profile resilience or stiffness in tokamak experiments. The confinement improvement as a result of the inward shift of the magnetic axis is obvious in the core region, which emphasizes the improvement of transport because of the geometry being unfavourable for the central heating of NBI in this configuration. The edge pressure, clearly, does not depend on the magnetic axis position. Unlike a tokamak H-mode, the edge pressure is determined by transport and can be increased by increasing the heating power.
- 1 July 2001
- Published by IOP Publishing in Nuclear Fusion
- Vol. 41 (7) , 901-908
Energy confinement and thermal transport characteristics of net current free plasmas in the Large Helical Device
The energy confinement and thermal transport characteristics of net current free plasmas in regimes with much smaller gyroradii and collisionality than previously studied have been investigated in the Large Helical Device (LHD). The inward shifted configuration, which is superior from the point of view of neoclassical transport theory, has revealed a systematic confinement improvement over the standard configuration. Energy confinement times are improved over the International Stellarator Scaling 95 by a factor of 1.6 ±0.2 for an inward shifted configuration. This enhancement is primarily due to the broad temperature profile with a high edge value. A simple dimensional analysis involving LHD and other medium sized heliotrons yields a strongly gyro-Bohm dependence (τEΩ ∝ ρ*-3.8) of energy confinement times. It should be noted that this result is attributed to a comprehensive treatment of LHD for systematic confinement enhancement and that the medium sized heliotrons have narrow temperature profiles. The core stored energy still indicates a dependence of τEΩ ∝ ρ*-2.6 when data only from LHD are processed. The local heat transport analysis of discharges dimensionally similar except for ρ* suggests that the heat conduction coefficient lies between Bohm and gyro-Bohm in the core and changes towards strong gyro-Bohm in the peripheral region. Since the inward shifted configuration has a geometrical feature suppressing neoclassical transport, confinement improvement can be maintained in the collisionless regime where ripple transport is important. The stiffness of the pressure profile coincides with enhanced transport in the peaked density profile obtained by pellet injection.
- 1 July 2001
- Published by IOP Publishing in Nuclear Fusion
- Vol. 41 (7) , 901-908
Energy confinement and thermal transport characteristics of net current free plasmas in the Large Helical Device
The energy confinement and thermal transport characteristics of net current free plasmas in regimes with much smaller gyroradii and collisionality than previously studied have been investigated in the Large Helical Device (LHD). The inward shifted configuration, which is superior from the point of view of neoclassical transport theory, has revealed a systematic confinement improvement over the standard configuration. Energy confinement times are improved over the International Stellarator Scaling 95 by a factor of 1.6 ±0.2 for an inward shifted configuration. This enhancement is primarily due to the broad temperature profile with a high edge value. A simple dimensional analysis involving LHD and other medium sized heliotrons yields a strongly gyro-Bohm dependence (τEΩ ∝ ρ*-3.8) of energy confinement times. It should be noted that this result is attributed to a comprehensive treatment of LHD for systematic confinement enhancement and that the medium sized heliotrons have narrow temperature profiles. The core stored energy still indicates a dependence of τEΩ ∝ ρ*-2.6 when data only from LHD are processed. The local heat transport analysis of discharges dimensionally similar except for ρ* suggests that the heat conduction coefficient lies between Bohm and gyro-Bohm in the core and changes towards strong gyro-Bohm in the peripheral region. Since the inward shifted configuration has a geometrical feature suppressing neoclassical transport, confinement improvement can be maintained in the collisionless regime where ripple transport is important. The stiffness of the pressure profile coincides with enhanced transport in the peaked density profile obtained by pellet injection.