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Featured researches published by T. Watari.


Review of Scientific Instruments | 1999

Liquid stub tuner for ion cyclotron heating

R. Kumazawa; T. Mutoh; T. Seki; F. Sinpo; G. Nomura; T. Ido; T. Watari; Jean-Marie Noterdaeme; Yangping Zhao

Ion cyclotron range of frequency (ICRF) heating on the large helical device (LHD) is characterized by high power (up to 12 MW) and steady state operation (30 min). The LHD is a helical device (with a major radius of 3.9 m and a minor radius of 0.6 m) with superconducting coil windings (l=2, m=10). The main purpose of physical research is to investigate currentless and disruption-free plasma. Research and development for steady state ICRF heating has been carried out in recent years: A high rf power transmission system consisting of stub tuners, a ceramic feedthrough, and an ion cyclotron heating loop antenna has been developed. In addition, steady state operation of a rf oscillator has been achieved at a power higher than 1 MW. A liquid stub tuner has been proposed as an innovation. The liquid stub tuner makes use of the difference between the rf wavelengths in liquid and in gas due to the different relative dielectric constants. The liquid stub tuner has been experimentally proved to be a reliable rf com...


Fusion Science and Technology | 2006

Overview of progress in LHD experiments

A. Komori; T. Morisaki; T. Mutoh; Satoru Sakakibara; Yasuhiko Takeiri; R. Kumazawa; S. Kubo; K. Ida; Shigeru Morita; K. Narihara; T. Shimozuma; K. Tanaka; K.Y. Watanabe; H. Yamada; Mikiro Yoshinuma; T. Akiyama; N. Ashikawa; M. Emoto; H. Funaba; M. Goto; T. Ido; K. Ikeda; S. Inagaki; M. Isobe; H. Igami; K. Itoh; O. Kaneko; K. Kawahata; T. Kobuchi; S. Masuzaki

Abstract Remarkable progress to access the reactor-relevant regime has been made in a recent experiment in the Large Helical Device. Optimizing the rotational transform, the average beta value of 4.3%, which is the highest record among helical devices, was achieved. The high-performance plasma with a fusion triple product up to ~2.2 × 1019 m−3·keV·s was sustained for >7 s by repetitive hydrogen pellet injection. With regard to steady-state operation, which is one of the key issues to realize a fusion reactor, discharges for >30 min were successfully sustained by ion cyclotron range of frequency heating with the aid of the magnetic axis swing technique to reduce the heat load to the plasma-facing component. In the discharge, the total input energy to the plasma reached 1.3 GJ, which also established a new record.


Nuclear Fusion | 2001

The performance of ICRF heated plasmas in LHD

T. Watari; T. Mutoh; R. Kumazawa; T. Seki; K. Saito; Y. Torii; Y. Zhao; D. Hartmann; H. Idei; S. Kubo; K. Ohkubo; M. Sato; T. Shimozuma; Y. Yoshimura; K. Ikeda; O. Kaneko; Y. Oka; M. Osakabe; Yasuhiko Takeiri; K. Tsumori; N. Ashikawa; P. de Vries; M. Emoto; A. Fukuyama; H. Funaba; M. Goto; K. Ida; S. Inagaki; N. Inoue; M. Isobe

An ion cyclotron range of frequency (ICRF) heating experiment was conducted in the third campaign of LHD in 1999. 1.35 MW of ICRF power were injected into the plasma and 200 kJ of stored energy were obtained, which was maintained for 5 s by ICRF power only after the termination of ECH. The impurity problem was so completely overcome that the pulse length was easily extended to 68 s at a power level of 0.7 MW. The utility of a liquid stub tuner in steady state plasma heating was demonstrated in this discharge. The energy confinement time of the ICRF heated plasma has the same dependences on plasma parameters as those of the ISS95 stellarator scaling with a multiplication factor of 1.5, which is a high efficiency comparable to that of NBI. Such an improvement in performance was obtained by various means, including: (a) scanning of the magnetic field intensity and minority concentration, (b) improvement of particle orbits due to a shift of magnetic axis and (c) reduction of the number of impurity ions by means of titanium gettering and the use of carbon divertor plates. In the optimized heating regime, ion heating turned out to be the dominant heating mechanism, unlike in CHS and W7-AS. Owing to the high quality of the heating and the parameter range being extended far beyond that of previous experiments, the experiment can be regarded as the first complete demonstration of ICRF heating in stellarators.


Review of Scientific Instruments | 2001

Liquid impedance matching system for ion cyclotron heating

K. Saito; Y. Torii; R. Kumazawa; T. Mutoh; T. Seki; F. Shimpo; G. Nomura; M. Yokota; T. Watari; G. Cattanei; Yangping Zhao

Ion cyclotron heating has been established as one of the heating schemes in nuclear fusion research and its use in steady state plasma heating in various devices is being considered. The optimal technology for steady state ion cyclotron range of frequency heating has not been firmly established. This article reports on the liquid stub tuner which was newly developed in research and development activities on the large helical device. It demonstrated high performance in real use in experiments. Two different impedance-matching systems based on the liquid stub tuner are studied: one is a triple liquid stub tuner system and the other is a single stub tuner system with a liquid phase shifter. The characteristics of the two systems are compared from the points of view of how wide a frequency range is covered, and how great the reduction of the voltage in the transmission line is.


Plasma Science & Technology | 2006

Review of Divertor Studies in LHD

T. Morisaki; S. Masuzaki; A. Komori; N. Ohyabu; M. Kobayashi; J. Miyazawa; M. Shoji; Gao Xiang; K. Ida; K. Ikeda; O. Kaneko; K. Kawahata; S. Kubo; S. Morita; K. Nagaoka; H. Nakanishi; K. Narihara; Y. Oka; M. Osakabe; B.J. Peterson; S. Sakakibara; R. Sakamoto; T. Shimozuma; Y. Takeiri; K. Tanaka; K. Toi; K. Tsumori; K.Y. Watababe; T. Watari; H. Yamada

In the Large Helical Device (LHD), two different divertor configurations, i.e. helical divertor (HD) and local island divertor (LID), are utilized to control the edge plasma. The HD with two X-points is an intrinsic divertor for heliotron devices, accompanied with a relatively thick ergodic layer outside the confinement region. Edge and divertor plasma behavior from low density to high density regimes is presented, referring to the divertor detachment. The effect of the ergodic layer on the edge transport is also discussed. On the other hand, the LID is an advanced divertor concept which realizes a high pumping efficiency by the combination of an externally induced magnetic island and a closed pumping system. Experimental results to confirm the fundamental divertor performance of the LID are presented.


The thirteenth topical conference on radio frequency power in plasmas | 1999

Liquid impedance matching system for Ion Cyclotron heating

R. Kumazawa; T. Mutoh; T. Seki; K. Saito; F. Shimpo; G. Nomura; T. Ido; T. Watari; G. Cattanei; Yanping Zhao

Ion Cyclotron Range of Frequency (ICRF) heating on the Large Helical Device (LHD) is characterized by high power (up to 12MW) and by steady-state operation (30 minutes). Research and development for ICRF heating have been carried out in recent years. A newly developed liquid stub tuner has demonstrated highly reliable performance as a stub tuner; it has withstood 63kV for 10 seconds and 50kV for 30 minutes. The liquid surface level could be shifted under high RF voltage without breakdown. A liquid impedance matching system has been designed and fabricated for ICRF heating on the LHD. This system consists of a liquid stub tuner and a liquid phase shifter. The liquid phase shifter was constructed by connecting two liquid stub tuners in a U-shaped configuration. An impedance matching can be acquired in a wide frequency range, i.e., 25–95MHz by selecting the length of 4m for the liquid stub tuner. At some frequencies, it was a problem that the RF voltage at the phase shifter became higher than that between th...


international symposium on fusion engineering | 1995

Development of steady state ICRF heating for Large Helical Device

T. Mutoh; R. Kumazawa; T. Seki; F. Simpo; G. Nomura; S. Masuda; T. Ido; Z. Wang; T. Watari

The high power and steady state ICRF system for the LHD has been being developed and tested. The wide band transmitter having a double coaxial output cavity is constructed and tested. 1.2 MW CW operation was achieved. The water cooled transmission line and tuners have been tested successfully. The fast wave ICRF antenna of the LHD has been designed and the steady state test on the R&D antenna has been carried out.


The thirteenth topical conference on radio frequency power in plasmas | 1999

Initial ICRF heating experiments on the LHD

R. Kumazawa; T. Mutoh; T. Seki; K. Saito; F. Shimpo; G. Nomura; T. Ido; T. Watari; G. Cattanei; Xie Jikang; Hiroyuki Okada; K. Ohkubo; M. Sato; S. Kubo; T. Shimozuma; H. Idei; Y. Yoshimura; O. Kaneko; Y. Takeiri; Y. Oka; K. Tsumori; M. Osakabe; N. Ohyabu; K. Kawahata; A. Komori; H. Yamada; Kenya Akaishi; M. Emoto; H. Funaba; M. Goto

The final goal of Ion Cyclotron Range of Frequency (ICRF) heating on the Large Helical Device (LHD) is characterized by its high power (up to 12MW) and by steady state operation (30 minutes). Initial ICRF heating experiments were carried out using a pair of loop antemas in the 2nd experimental campaign in 1998. The ICRF heating power was applied to an ECH-produced plasma at an RF power level of 300 kW for 0.2 seconds. An applied frequency of f=25.6 MHz was selected. A cyclotron resonance layer of hydrogen ions was located at the half minor radius during operation at B=1.5 T. A mode conversion layer of a He plasma with a minority of hydrogen ions was located between the magnetic axis and the last closed magnetic flux. The plasma stored energy was observed to increase to twice that of the ECH plasma (PECH=300 kW). The plasma stored energy of the ECH target plasma was 11-13 kJ at an average electron density of ne=8–9×1018 m−3 and a central electron temperature of Te0=400 eV. The plasma stored energy increase...


19th Fusion Energy Conference | 2003

A demonstration of magnetic field optimization in LHD

S. Murakami; H. Yamada; A. Wakasa; M. Sasao; M. Isobe; T. Ozaki; P. Goncharov; T. Saida; J. F. Lyon; M. Osakabe; K. Narihara; K. Tanaka; H. Inagaki; Shigeru Morita; K. Ida; J. Miyazawa; H. Idei; K. Ikeda; S. Kubo; R. Kumazawa; T. Mutoh; Y. Oka; K. Saito; T. Seki; Yasuhiko Takeiri; Y. Torii; K. Tumori; T. Watari; K.Y. Watanabe; H. Funaba


Research Report NIFS-Series | 1998

Steady State Heating Technology Development for LHD

T. Watari; T. Shimozuma; Y. Takeiri; R. Kumazawa; T. Mutoh; M. Sato; O. Kaneko; K. Ohkubo; S. Kubo; H. Idei; Y. Oka; M. Osakabe; T. Seki; K. Tsumori; Y. Yoshimura; R. Akiyama; T. Kawamoto; S. Kobayashi; F. Shimpo; Y. Takita; E. Asano; S. Itoh; G. Nomura; T. Ido; M. Hamabe; M. Fujiwara; A. Iiyoshi; S. Morimoto; T. Bigelow; Yanping Zhao

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T. Mutoh

Graduate University for Advanced Studies

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R. Kumazawa

Graduate University for Advanced Studies

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