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Featured researches published by Goro Nomura.


Nuclear Fusion | 2003

Ion cyclotron range of frequencies heating and high-energy particle production in the Large Helical Device

T. Mutoh; R. Kumazawa; T. Seki; K. Saito; T. Watari; Y. Torii; N. Takeuchi; T. Yamamoto; F. Shimpo; Goro Nomura; M. Yokota; M. Osakabe; M. Sasao; S. Murakami; T. Ozaki; T. Saida; Yanping Zhao; Hiroyuki Okada; Y. Takase; A. Fukuyama; N. Ashikawa; M. Emoto; H. Funaba; P. Goncharov; M. Goto; K. Ida; H. Idei; K. Ikeda; S. Inagaki; M. Isobe

Significant progress has been made with ion cyclotron range of frequencies (ICRF) heating in the Large Helical Device. This is mainly due to better confinement of the helically trapped particles and less accumulation of impurities in the region of the plasma core. During the past two years, ICRF heating power has been increased from 1.35 to 2.7 MW. Various wave-mode tests were carried out using minority-ion heating, second-harmonic heating, slow-wave heating and high-density fast-wave heating at the fundamental cyclotron frequency. This fundamental heating mode extended the plasma density range of effective ICRF heating to a value of 1×1020 m−3. This use of the heating mode was its first successful application in large fusion devices. Using the minority-ion mode gave the best performance, and the stored energy reached 240 kJ using ICRF alone. This was obtained for the inward-shifted magnetic axis configuration. The improvement associated with the axis-shift was common for both bulk plasma and highly accelerated particles. For the minority-ion mode, high-energy ions up to 500 keV were observed by concentrating the heating power near the plasma axis. The confinement properties of high-energy particles were studied for different magnetic axis configurations, using the power-modulation technique. It confirmed that with the inward-shifted configuration the confinement of high-energy particles was better than with the normal configuration. By increasing the distance of the plasma to the vessel wall to about 2 cm, the impurity influx was sufficiently reduced to allow sustainment of the plasma with ICRF heating alone for more than 2 min.


Nuclear Fusion | 2001

Ion and electron heating in ICRF heating experiments on LHD

K. Saito; R. Kumazawa; T. Mutoh; T. Seki; T. Watari; Y. Torii; D. Hartmann; Yanping Zhao; A. Fukuyama; F. Shimpo; Goro Nomura; M. Yokota; M. Sasao; M. Isobe; M. Osakabe; T. Ozaki; K. Narihara; Y. Nagayama; S. Inagaki; K. Itoh; S. Morita; A. V. Krasilnikov; K. Ohkubo; M. Sato; S. Kubo; T. Shimozuma; H. Idei; Y. Yoshimura; O. Kaneko; Y. Takeiri

The ICRF heating experiments conducted in 1999 in the third experimental campaign on LHD are reported, with an emphasis on the optimization of the heating regime. Specifically, an exhaustive study of seven different heating regimes was carried out by changing the radiofrequency relative to the magnetic field intensity, and the dependence of the heating efficiency on H minority concentration was investigated. It was found in the experiment that both ion and electron heating are attainable with the same experimental set-up by properly choosing the frequency relative to the magnetic field intensity. In the cases of both electron heating and ion heating, the power absorption efficiency depends on the minority ion concentration. An optimum minority concentration exists in the ion heating case while, in the electron heating case, the efficiency increases with concentration monotonically. A simple model calculation is introduced to provide a heuristic understanding of these experimental results. Among the heating regimes examined in this experiment, one of the ion heating regimes was finally chosen as the optimized heating regime and various high performance discharges were realized with it.


Nuclear Fusion | 2006

Long-pulse plasma discharge on the Large Helical Device

R. Kumazawa; T. Mutoh; K. Saito; T. Seki; Y. Nakamura; S. Kubo; T. Shimozuma; Y. Yoshimura; H. Igami; K. Ohkubo; Y. Takeiri; Y. Oka; K. Tsumori; M. Osakabe; K. Ikeda; K. Nagaoka; O. Kaneko; J. Miyazawa; S. Morita; K. Narihara; M. Shoji; S. Masuzaki; M. Kobayashi; H. Ogawa; M. Goto; T. Morisaki; B.J. Peterson; K. Sato; T. Tokuzawa; N. Ashikawa

A long-pulse plasma discharge of more than 30 min duration was achieved on the Large Helical Device (LHD). A plasma of ne = 0.8 × 1019 m−3 and Ti0 = 2.0 keV was sustained with PICH = 0.52 MW, PECH = 0.1 MW and averaged PNBI = 0.067 MW. The total injected heating energy was 1.3 GJ. One of the keys to the success of the experiment was a dispersion of the local plasma heat load to divertors, accomplished by sweeping the magnetic axis inward and outward. Causes limiting the long pulse plasma discharge are discussed. An ion impurity penetration limited further long-pulse discharge in the 8th experimental campaign (2004).


Plasma Physics and Controlled Fusion | 2002

A study of high-energy ions produced by ICRF heating in LHD

K. Saito; R. Kumazawa; T. Mutoh; T. Seki; T. Watari; T. Yamamoto; Y. Torii; N. Takeuchi; C." Zhang; Yanping Zhao; A. Fukuyama; F. Shimpo; Goro Nomura; M. Yokota; A. Kato; M. Sasao; M. Isobe; A. V. Krasilnikov; T. Ozaki; M. Osakabe; K. Narihara; Y. Nagayama; S. Inagaki; K. Itoh; T. Ido; S. Morita; K. Ohkubo; M. Sato; S. Kubo; T. Shimozuma

This paper reports on the behaviour of high-energy ions created by ion cyclotron range of frequency (ICRF) heating on the Large Helical Device (LHD). In the third experimental campaign conducted in 1999, it was found that minority heating has good heating performance, and high-energy particles were observed. In the fourth campaign in 2000, the temporal behaviour of high-energy ions was investigated in the minority heating regime using turnoff or modulation of ICRF power. The time evolution of the high-energy particle distribution was measured using a natural diamond detector (NDD) and a time-of-flight neutral particle analyser (TOF-NPA). It was found that the count number of higher-energy particles declines faster than that of lower-energy particles after ICRF turnoff. In the modulation experiments, the phase difference of the flux of high-energy particles with respect to the ICRF power modulation increased with energy. These results were explained qualitatively by the Fokker-Planck equation with a simple model. The pitch-angle dependence of the distribution function was also measured in the experiment by changing the line of sight of the TOF-NPA, and an anisotropy of the high-energy tail was found. This anisotropy was reproduced by solving the bounce-averaged Fokker-Planck equation. The second harmonic heating was conducted successfully for the first time in the LHD in high-β plasma, and high-energy particles were also detected in this heating regime.


Physics of Plasmas | 2001

Ion cyclotron range of frequency heating experiments on the large helical device and high energy ion behavior

R. Kumazawa; T. Mutoh; T. Seki; T. Watari; K. Saito; Y. Torii; F. Shimpo; Goro Nomura; M. Yokota; A. Kato; D. Hartmann; Yanping Zhao; A. Fukuyama; Hiroyuki Okada; K. Ohkubo; M. Sato; S. Kubo; T. Shimozuma; H. Idei; Y. Yoshimura; T. Notake; Y. Takita; S. Kobayashi; S.-I. Itoh; Y. Mizuno; O. Kaneko; Y. Takeiri; Y. Oka; K. Tsumori; M. Osakabe

Ion cyclotron range of frequency (ICRF) heating experiments on the Large Helical Device (LHD) [O. Motojima et al. Fus. Eng. Des. 20, 3 (1993)] achieved significant advances during the third experimental campaign carried out in 1999. They showed significant results in two heating modes; these are modes of the ICH-sustained plasma with large plasma stored energy and the neutral beam injection (NBI) plasma under additional heating. A long-pulse operation of more than 1 minute was achieved at a level of 1 MW. The characteristics of the ICRF heated plasma are the same as those of the NBI heated plasma. The energy confinement time is longer than that of International Stellarator Scaling 95. Three keys to successful ICRF heating are as follows: (1) an increase in the magnetic field strength, (2) the employment of an inward shift of the magnetic axis, (3) the installation of actively cooled graphite plates along the divertor legs. Highly energetic protons accelerated by the ICRF electric field were experimentally...


Fusion Science and Technology | 2001

Steady-State Amplifier at Megawatt Level for LHD ICRF Heating

T. Seki; R. Kumazawa; Takashi Mutoh; F. Shimpo; Goro Nomura; T. Watari; K. Saito; Yanping Zhao

Abstract A high-power, wide-band, steady-state amplifier was developed as a part of research and development for ion cyclotron range of frequency (ICRF) heating in the Large Helical Device at the National Institute for Fusion Science. A double coaxial cavity was adopted to cover the wide frequency range of 25 to 100 MHz. An analysis of this cavity is compared with results of static tests, and good agreement is shown. In a high-power test, long-pulse operation of 5000 s at an output power of 1.6 MW, which is a world record for steady-state operation of an ICRF amplifier, has been achieved as a low-impedance-mode operation is adopted. Cooling of various elements of the amplifier is important in the steady-state operation. This paper reports how the steady-state operation is obtained through cooling. An analysis of heat removal in response to the temperature rise of a coaxial cable is also reported.


Plasma Physics and Controlled Fusion | 2003

Confinement characteristics of high-energy ions produced by ICRF heating in the large helical device

R. Kumazawa; K. Saito; Y. Torii; T. Mutoh; T. Seki; T. Watari; M. Osakabe; S. Murakami; M. Sasao; T. Watanabe; T. Yamamoto; T. Notake; N. Takeuchi; T. Saida; F. Shimpo; Goro Nomura; M. Yokota; A. Kato; Y Zao; Hiroyuki Okada; M. Isobe; T. Ozaki; K. Narihara; Y. Nagayama; S. Inagaki; S. Morita; A. V. Krasilnikov; H. Idei; S. Kubo; K. Ohkubo

The behaviour of high-energy ions accelerated by an ion cyclotron range of frequency (ICRF) electric field in the large helical device (LHD) is discussed. A better confinement performance of high-energy ions in the inward-shifted magnetic axis configuration was experimentally verified by measuring their energy spectrum and comparing it with the effective temperature determined by an electron slowing down process. In the standard magnetic axis configuration a saturation of the measured tail temperature was observed as the effective temperature was increased. The ratio between these two quantities is a measure of the quality of transfer efficiency from high-energy ions to a bulk plasma; when this efficiency was compared with Monte Carlo simulations the results agreed fairly well. The ratio of the stored energy of the high-energy ions to that of the bulk plasma was measured using an ICRF heating power modulation method; it was deduced from phase differences between total and bulk plasma stored energies and the modulated ICRF heating power. The measured high energy fraction agreed with that calculated using the injected ICRF heating power, the transfer efficiency determined in the experiment and the confinement scaling of the LHD plasma.


Plasma Physics and Controlled Fusion | 2000

The first ICRF heating experiment in the large helical device

T. Mutoh; R. Kumazawa; T. Seki; K. Saito; F. Shimpo; Goro Nomura; T. Watari; X. Jikang; G. Cattanei; Hiroyuki Okada; K. Ohkubo; M. Sato; S. Kubo; T. Shimozuma; H. Idei; Y. Yoshimura; O. Kaneko; Y. Takeiri; M. Osakabe; Y. Oka; K. Tsumori; A. Komori; H. Yamada; K.Y. Watanabe; S. Sakakibara; M. Shoji; R. Sakamoto; S. Inagaki; J. Miyazawa; S. Morita

The first experiment of the ion cyclotron range of frequencies (ICRF) heating in the Large Helical Device (LHD) was carried out at the end of 1998. The LHD is a large superconducting heliotron device and its first plasma was produced in March 1998. During the ICRF heating experiment, a maximum 300 kW/0.2 s of ICRF power was injected into the LHD plasma by using a pair of loop antennae. This paper reports on the installation of the loop antennae, the results of antenna coupling and the first heating experiments. The antennae are designed to operate in the steady state and to change their distance from the plasma by 0-15 cm. In the experiment, the antenna resistance coupled with the plasma was measured by changing the distance between the last closed flux surface and the launcher front from 9 cm to 5 cm. The resistance was almost doubled by decreasing the distance. The target plasma was produced by the second harmonic electron cyclotron heating (ECH) of 84 GHz gyrotrons at a magnetic field of 1.5 T and a low plasma electron density of less than 1 × 1019 m-3 . Therefore, the low coupling resistance limited the maximum injected power to less than 300 kW. The heating efficiency and heating species were varied by the minority ion gas-puffing rate. The heating characteristics were compared with a one-dimensional full-wave analysis code, and the experimental results were consistent with wave damping analysis. For the optimum condition of the minority hydrogen gas-puff ratio, the plasma internal energy increased from 13 kJ to 26 kJ by almost the same power as the ECH power.


Plasma Science & Technology | 2013

Measurement of Ion Cyclotron Emissions by Using High-Frequency Magnetic Probes in the LHD

K. Saito; R. Kumazawa; T. Seki; H. Kasahara; Goro Nomura

Two pairs of high-frequency magnetic probes were installed in the Large Helical Device (LHD). During the injection of a perpendicular neutral beam, ion cyclotron emissions (ICEs) with the fundamental frequency corresponding to the ion cyclotron frequency at the plasma edge were detected, which are the same type of ICE as measured with the former spare ion cyclotron range of frequencies (ICRF) heating antennas. This type of ICE was further investigated with regard to the phase and intensity of signals. Another type of ICE was found in the LHD, and these ICEs were synchronized with bursts of toroidicity induced Alfven eigenmodes (TAE) and the rise of intensity of lost ion flux. Therefore the source of these ICEs was thought to be the particles transferred from the core to the outer region of plasma by the TAE bursts. The frequency of ICEs induced by the TAE bursts increases linearly with the magnetic field strength, since the ion cyclotron frequency increases with the magnetic field strength.


Plasma Physics and Controlled Fusion | 2001

Derivation of energy confinement time and ICRF absorption in LHD by power modulation

Y. Torii; T. Watari; R. Kumazawa; K. Saito; T. Mutoh; T. Seki; F. Shimpo; Goro Nomura; T. Watanabe; N. Takeuchi; T. Yamamoto; Yanping Zhao; D. Hartmann; H. Yamada; T. Ozaki; S. Masuzaki; Kenji Tanaka; M. Yokota; A Katoh; Kenya Akaishi; N. Ashikawa; P. de Vries; M. Emoto; H. Funaba; M. Goto; K. Ida; H. Idei; K. Ikeda; S. Inagaki; N. Inoue

A power modulation experiment was conducted in the third campaign of the LHD. In a conventional analysis of the modulation experiments, the energy confinement time and heating efficiency are taken as constant, disregarding their dependence on the plasma parameters. In this paper, their dependence on the plasma temperature and heating power is taken into consideration to improve the analysis of the power modulation experiments. Several models, with differing dependence on the plasma parameters, have been examined. There have been several reports suggesting that the transport coefficients obtained from the dynamical method are different from those obtained from power balance analyses. This paper finally concludes that the energy confinement time obtained from the power modulation experiments well agrees with that obtained from the power balance analysis, made including temperature dependence both in energy confinement time and heating efficiency.

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T. Seki

Graduate University for Advanced Studies

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H. Kasahara

Graduate University for Advanced Studies

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T. Mutoh

Graduate University for Advanced Studies

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Yanping Zhao

Chinese Academy of Sciences

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