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Journal Articles

Reduced heat transport between edge-localized-mode bursts at low collisionality and small poloidal larmor radius

Urano, Hajime; Takizuka, Tomonori; Kamada, Yutaka; Oyama, Naoyuki; Takenaga, Hidenobu; Miura, Yukitoshi

Physical Review Letters, 95(3), p.035003_1 - 035003_4, 2005/07

 Times Cited Count:15 Percentile:62.67(Physics, Multidisciplinary)

Non-dimensional parameter dependence of heat transport between ELMs is examined for H mode plasmas. At lower edge collisionality, the heat flux assigned to the heat transport between ELMs is reduced and the ELM loss power is enhanced. During the inter-ELM phase, the energy confinement time becomes larger with decreasing the edge collisionality and poloidal Larmar radius. The electron heat diffusivity between ELMs is reduced to the level of ion neoclassical transport in the plasma edge region which is affected by ELM burst.

Journal Articles

A Linear gyrokinetic model in magnetic coordinates

Jolliet, S.*; Angelino, P.*; Bottino, A.*; Idomura, Yasuhiro; Villard, L.*

Theory of Fusion Plasmas, ISPP21, p.345 - 351, 2004/00

Global particle-in-cell (PIC) simulations are a very useful tool for studying the time evolution of turbulence induced by ion-temperature-gradient (ITG) instabilities. Unfortunately, the linear code LORB5 and its non-linear version ORB5 require high computational power. In order to study more sophisticated models, we need to optimize these codes. We will focus on LORB5, which uses a cylindrical grid (r,z) for solving the Vlasov equation and a (s,$$theta$$) grid for the Poisson equation. The approach presented in this work consists of implementing the gyrokinetic model using a single (s,$$theta_*$$) grid. Here $$theta_*$$ is the straight-field-line poloidal coordinate. A method to avoid the singularity at the magnetic axis is presented, and a benchmark with the CYCLONE case is shown.

Journal Articles

Progress of electron cyclotron heating/current drive technology in JT-60U

Moriyama, Shinichi; Ikeda, Yoshitaka; Seki, Masami; Sakamoto, Keishi; Kasugai, Atsushi; Takahashi, Koji; Kajiwara, Ken*; Isayama, Akihiko; Suzuki, Takahiro; Fukuda, Takeshi*; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 79(9), p.935 - 944, 2003/09

An optimization of current profile is a key issue for attaining higher plasma performance in Tokamak, such as stabilization of neo-classical tearing mode (NTM) and control of internal transport barrier (ITB). In JT-60U, a high power electron cyclotron heating (ECH) system at 110 GHz has been developed for local plasma heating and current drive. We have demonstrated the technical feasibility of the antenna which can scan EC beam in both toroidal and poloidal directions. The toroidal scan enabled co- and counter- current drive and also pure plasma heating. An automatic stabilization of the NTM was demonstrated by means of current drive at the location of magnetic island using a feedback control of poloidal beam angle. The total injected power has been extended to 2.8 MW for 3.6 sec and each gyrotron delivers ~ 1 MW for 5 sec. This world record of the injection energy was attained by an upgrade of the gyrotron using RF absorber in the beam tunnel to suppress the parasitic oscillation and improvement of the transmission efficiency of the waveguide system.

Journal Articles

Electromagnetic phenomenon in superconducting magnet for fusion facility; Forced flow superconducting magnet

Hamada, Kazuya; Koizumi, Norikiyo

Purazuma, Kaku Yugo Gakkai-Shi, 78(7), p.616 - 624, 2002/07

In the Tokamak type fusion reactor design, a forced flow superconducting coil is applied from the viewpoint to high magnetic field, high withstand voltage performance and large electromagnetic force. In the forced flow magnets, it is well known that various electromagnetic phenomena are occurred by zero resistance and diamagnetic effect of superconductor and complicated structure of cable in conduit conductor (CICC). In the R&D of CICC, the study of hysteresis losses and coupling losses CICC have a lot of progress. For example, using the optimization of filament arrangement in superconducting strand and control of contact resistance of strand, ITER model coil project have a large achievement.

Journal Articles

Overview of JT-60U results toward high integrated performance in reactor-relevant regime

Hatae, Takaki; JT-60 Team

Proceedings of 6th Japan-Australia Workshop on Plasma Diagnostics (CD-ROM), 13 Pages, 2002/00

The main purpose of JT-60U project is to make contribution to establishment of scientific basis of ITER and the demo tokamak reactor. Our ultimate goal is to achieve and sustain high integrated performance, namely high beta, high confinement, high bootstrap current fraction, full non-inductive current drive and heat/particle control, in a reactor-relevant regime. Toward this goal, we have developed weak magnetic shear ("high $$beta_{p}$$ mode") and reversed magnetic shear plasmas. In both regimes, the internal transport barrier (ITB) and the edge pedestal are obtained simultaneously. As a large-sized tokamak equipped with a variety of devices for heating, current drive and profile control, JT-60U has high ability to approach the conditions required in reactors (ITER or demo): low values of normalized Larmor radius and collisionality, high toroidal field, high temperature with Te$$>sim$$Ti, small central fueling, small ELM activities, etc. This paper reviews recent JT-60U results with the emphasis on the projection to the reactor-relevant regime.

Journal Articles

Neoclassical tearing mode

Ozeki, Takahisa; Isayama, Akihiko

Purazuma, Kaku Yugo Gakkai-Shi, 77(5), p.409 - 419, 2001/05

Neoclassical tearing modes (NTMs) which are induced by lack of the bootstrap current inside the magnetic island are reviewed based on the modified Rutherford equation. Theoretical bases and experimental observations of NTM are described. The beta value scaling of the growth of NTM and the mechanism of the growth are discussed. Influence of NTM on energy confinement is described, and the stabilization of NTM by electron cyclotron current drive (ECCD) is introduced.

Journal Articles

MHD instability induced by the internal transport barrier

Ozeki, Takahisa

Purazuma, Kaku Yugo Gakkai-Shi, 74(9), p.998 - 1005, 1998/09

no abstracts in English

Journal Articles

Coherent magnetic fluctuations ergodized ELMy H-mode in the JFT-2M tokamak

W.Liu*; Miura, Yukitoshi; JFT-2M Group

Purazuma, Kaku Yugo Gakkai-Shi, 74(7), p.753 - 757, 1998/07

no abstracts in English

Journal Articles

Characteristics of edge pedestal width in JT-60U ELM-free H-mode plasmas

Hatae, Takaki; Kamada, Yutaka; Ishida, Shinichi; Fukuda, Takeshi; Takizuka, Tomonori; Shirai, Hiroshi; Koide, Yoshihiko; Kikuchi, Mitsuru; Yoshida, Hidetoshi; Naito, Osamu

Plasma Physics and Controlled Fusion, 40(6), p.1073 - 1083, 1998/00

 Times Cited Count:41 Percentile:76.58(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Production of sheared flow during ion cyclotron resonance heating in tokamak plasmas

C.G.Liu*; Yamagiwa, Mitsuru; S.J.Qian*

Physics of Plasmas, 4(8), p.2788 - 2790, 1997/08

 Times Cited Count:3 Percentile:12.92(Physics, Fluids & Plasmas)

no abstracts in English

JAEA Reports

Production of sheared flow by means of ICRF heating in tokamak plasmas

C.Liu*; Yamagiwa, Mitsuru; S.Qian*

JAERI-Research 96-068, 17 Pages, 1997/01

JAERI-Research-96-068.pdf:0.84MB

no abstracts in English

Journal Articles

Poloidal shear flow effect on toroidal ion temperature gradient mode; A Theory and simulation

J.Y.Kim*; Kishimoto, Yasuaki; Wakatani, Masahiro*; Tajima, Toshiki*

Physics of Plasmas, 3(10), p.3689 - 3695, 1996/10

 Times Cited Count:52 Percentile:82.07(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Internal transport barrier on q=3 surface and poloidal plasma spin up in JT-60U high-$$beta$$$$_{p}$$ discharges

Koide, Yoshihiko; Kikuchi, Mitsuru; Mori, Masahiro; Tsuji, Shunji; Ishida, Shinichi; Asakura, Nobuyuki; Kamada, Yutaka; Nishitani, Takeo; Kawano, Yasunori; Hatae, Takaki; et al.

Physical Review Letters, 72(23), p.3662 - 3665, 1994/06

 Times Cited Count:268 Percentile:98.54(Physics, Multidisciplinary)

no abstracts in English

Journal Articles

The second test results on the Nb$$_{3}$$Sn demo poloidal coil(DPC-EX)

Ando, Toshinari; Nakajima, Hideo; *; Hiyama, Tadao; Takahashi, Yoshikazu; Nishi, Masataka; Yoshida, Kiyoshi; Okuno, Kiyoshi; Kato, Takashi; Sugimoto, Makoto; et al.

Advances in Cryogenic Engineering, Vol.39, 0, p.335 - 341, 1994/00

no abstracts in English

JAEA Reports

An Investigation of A.C.Losses in two sub-size conductors for the ITER

R.J.Nelson*; Takahashi, Yoshikazu; Isono, Takaaki; *; Otsu, K.*; Tajiri, F.*

JAERI-M 93-219, 48 Pages, 1993/11

JAERI-M-93-219.pdf:1.28MB

no abstracts in English

Journal Articles

Development of a high-current superconductor

Takahashi, Yoshikazu

Purazuma, Kaku Yugo Gakkai-Shi, 69(6), p.610 - 614, 1993/06

no abstracts in English

Journal Articles

Experimental results of stability and current sharing of NbTi cable-in-conduit conductors for the poloidal field coils

Takahashi, Yoshikazu; Koizumi, Norikiyo; *; Okuno, Kiyoshi; Nishi, Masataka; Isono, Takaaki; Yoshida, Kiyoshi; Sugimoto, Makoto; Kato, Takashi; *; et al.

IEEE Transactions on Applied Superconductivity, 3(1), p.610 - 613, 1993/03

 Times Cited Count:12 Percentile:69.7(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Enhanced confinement of high bootstrap current discharges in JT-60U

Ishida, Shinichi; Matsuoka, Mamoru; Kikuchi, Mitsuru; Tsuji, Shunji; Nishitani, Takeo; Koide, Yoshihiko; Ozeki, Takahisa; Fujita, Takaaki; Nakamura, Hiroo; Hosogane, Nobuyuki; et al.

Plasma Physics and Controlled Nuclear Fusion Research 1992, Vol.1, p.219 - 233, 1993/00

no abstracts in English

JAEA Reports

Japanese contribution of ITER PF systems design during CDA

Azumi, Masafumi; Hasegawa, Mitsuru*; *; Kurihara, Kenichi; Nakamura, Yukiharu; Nishio, Satoshi; Shimomura, Yasuo; Shinya, K.*; Sugihara, Masayoshi; *; et al.

JAERI-M 92-041, 100 Pages, 1992/03

JAERI-M-92-041.pdf:2.59MB

no abstracts in English

Journal Articles

AC loss results of the Nb$$_{3}$$Sn demo poloidal coil(DPC-EX)

Ando, Toshinari; Takahashi, Yoshikazu; Okuno, Kiyoshi; Tsuji, Hiroshi; Hiyama, Tadao; Nishi, Masataka; Tada, Eisuke; Yoshida, Kiyoshi; Koizumi, Norikiyo; Nakajima, Hideo; et al.

IEEE Transactions on Magnetics, 28(1), p.206 - 209, 1992/01

 Times Cited Count:4 Percentile:47.74(Engineering, Electrical & Electronic)

no abstracts in English

43 (Records 1-20 displayed on this page)