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Kazuaki Hanada Last modified date：2023.10.17

Professor / Interdisciplinary Graduate School of Engineering Sciences.　Plasma and Quantum Science and Engineering
Advanced Fusion Research Center
Research Institute for Applied Mechanics


Graduate School
Department of Interdisciplinary Engineering Sciences
Interdisciplinary Graduate School of Engineering Sciences
Department of Interdisciplinary Engineering Sciences
Interdisciplinary Graduate School of Engineering Sciences
Department of Interdisciplinary Engineering Sciences
Interdisciplinary Graduate School of Engineering Sciences


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Homepage
https://kyushu-u.elsevierpure.com/en/persons/kazuaki-hanada
　Reseacher Profiling Tool　Kyushu University Pure
http://www.triam.kyushu-u.ac.jp
https://hanadalab.triam.kyushu-u.ac.jp/
Hanada Laboratory Homepage .
Phone
092-583-7706
Fax
092-573-6899
Academic Degree
Dr.Sci
Country of degree conferring institution (Overseas)
No
Field of Specialization
plasma physics
Total Priod of education and research career in the foreign country
00years00months
Outline Activities
During 1988-1994, the radio-frequency(RF) heating and current drive of the high temperature plasma bu use of WT-3 tokamak device in Faculty of Science, Kyoto University. During 1994-1997, the design and consturuction of TST-M spherical tokamak was executed in Fucultu of Science, University of Tokyo and the collaborating study on confinement of high temperature plasma was executed on JFT-2M, which is in Japan Atomic Energy Research Institute. SInce 1997, study on steady state operation of tokamak has been executed by radio-frequency current drive on TRIAM-1M in Research Institute for Applied Mechanics, Kyushu Univesity. In 2004, Compact PWI EXperimental Device (CPD) was established and the experiments on CPD was started from 2005. From 2005　to 2007, Main parts of Kyushu University Experiment with Steady-state Spherical Tokamak (QUEST) has been completed. From 2008, full-fledged experiments was executed and spherical tokamak configurations has been established using full non-inductive current drive technique. Plasma current of 25kA and maintenance of plasmas for more than 30 s were achieved in 2010. Divertor configurations in the spherical tokamak has been successfully established in 2010. The hot wall has been installed since 2014 and several discharges more than 1 hour could be achieved using the hot wall. A 6 hours discharge with lower power was obtained on the wall of 200 centigrade in 2017. Two 6 hour discharges were achieved using local cooling of plasma-facing wall in 2020. Especially one of the discharges could be maintained by local cooling of the hot wall during the discharge. This indicates that the effect of temperature regulated plasma-facing wall to fuel particle recycling is successfully demonstrated.
Research
Research Interests
  • Study on Plasma heating and particle circulation control in spherical tokamaks
    keyword : spherical tokamak, steady state operation , recycling at hot walls
    2023.04.
  • Steady state operation by particle control and high power injection on QUEST
    keyword : Non-inductive current drive, plasma start-up, hot wall, RF heating, particle transport
    2019.04～2023.03.
  • Particle circulation control and high power non-inductive current drive under the hot wall in QUES
    keyword : Non-inductive current drive, plasma start-up, hot wall, RF heating, particle transport
    2015.04～2018.03.
  • Study of hot plasmas and related plasma-wall interactions on QUEST
    keyword : Non-inductive current drive, plasma start-up, hot wall, RF heating, particle transport
    2008.04～2015.03.
  • Physical Design and construction of QUEST
    keyword : plasma wall interaction, steady-state plasma, divertor
    2005.04～2007.03Q-shu University experimet with Steady-state Spherical Tokamak(QUEST) is the main device in the next project and the design and the construction are the key for the project..
  • (*)metering experiment
    Compact PWI experimetal Device (CPD) is the development of currrent drive technique on sperical tokamak.
    keyword : plasma wall interaction
    2005.04～2010.03One of the purpose of Compact PWI experimetal Device (CPD) is the development of currrent drive technique on sperical tokamak. To do this, the design, product and experiments are carried out. Moreover As CPD should play an role in the platform for collaboration program, the proposed collaboration program has been conducted..
  • The basic research to realize nuclear fusion plant has been executed by use of a superconducting tokamak, TRIMA-1M
    keyword : TRIMA-1M
    1997.07～2006.03The basic research to realize nuclear fusion plant has been executed by use of a superconducting tokamak, TRIMA-1M. The research for steady state operation of tokamak has been executed, since steady magnetic field can be produced by superconducting magnets..
Current and Past Project
  • The basic research to realize fusion plants has been executed by a steady-state sperical tokamak, QUEST.
  • The basic research to realize fusion plants has been executed by a superconducting tokamak, TRIAM-1M.
Academic Activities
Papers
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1. K. Hanada, N. Yoshida, I. Takagi, T. Hirata, A. Hatayama, K. Okamoto, Y. Oya, T. Shikama, Z. Wang, H. Long, C. Huang, M. Oya, H. Idei, Y. Nagashima, T. Onchi, M. Hasegawa, K. Nakamura, H. Zushi, K. Kuroda, S. Kawasaki, A. Higashijima, T. Nagata, S. Shimabukuro, Y. Takase, S. Murakami, X. Gao, H. Liu, J. Qian, R. Raman, M. Ono, Estimation of fuel particle balance in steady state operation with hydrogen barrier model, Nuclear Materials and Energy, 10.1016/j.nme.2019.03.015, 19, 544-549, 2019.05, This research investigated fuel particle balance during long duration discharge in an all-metal plasma facing wall (PFW)through intensive QUEST execution. A simple wall model including the plasma-induced deposition layer that creates hydrogen (H)barriers, called the H barrier model, was established. A simple calculation, based on a combination of H state rate equations and the H barrier model, was applied to real plasma in the early phase of its longest discharge. The model accurately reconstructed the evolutions of electron density and wall-stored H over time, proper values are chosen for the parameters that are difficult to determine experimentally. Comparative calculations that used the H barrier and a fully reflective models, predicted significant impacts of wall models on the plasma density time response and value of electron density, indicating that a proper wall model should be developed for all-metal PFW devices..
2. K. Hanada, N. Yoshida, M. Hasegawa, A. Hatayama, K. Okamoto, I. Takagi, T. Hirata, Y. Oya, M. Miyamoto, M. Oya, T. Shikama, A. Kuzmin, Z. X. Wang, H. Long, H. Idei, Y. Nagashima, K. Nakamura, O. Watanabe, T. Onchi, H. Watanabe, K. Tokunaga, A. Higashijima, S. Kawasaki, T. Nagata, S. Shimabukuro, Y. Takase, S. Murakami, X. Gao, H. Liu, J. Qian, R. Raman, M. Ono, Particle balance investigation with the combination of the hydrogen barrier model and rate equations of hydrogen state in long duration discharges on an all-metal plasma facing wall in QUEST, Nuclear Fusion, 10.1088/1741-4326/ab1858, 59, 7, 2019.05, The fuel particle balance during long duration discharges in the Q-shu University Experiment with steady state spherical tokamak (QUEST) was investigated. QUEST has all-metal plasma facing walls (PFWs) that were temperature controlled during the experiments. The presence of a transport barrier for hydrogen (H) at the interface between a plasma-induced deposition layer and metallic substrate was confirmed by nuclear reaction analysis with exposing deuterium plasma. An effective method to evaluate global hydrogen flux to PFWs is proposed, taking advantage of the nature of wall saturation. The outgoing flux of fuel particles from the PFWs just after the plasma termination was proportional to the square of wall-stored H, which indicates that enhanced recombination of solved hydrogen played an essential role in dynamic retention and was in agreement with predictions from the H-barrier model. A simple calculation based on the combination of wall modelling and rate equations of the H states denoted a significant impact of wall modelling on the time response of the plasma density. Hence, a proper wall model including the effects of the deposition layer creating the H barrier is required to be developed, even for all-metal PFW devices..
3. K. Hanada, N. Yoshida, T. Honda, Z. Wang, A. Kuzmin, I. Takagi, T. Hirata, Y.Oya, M.Miyamoto, H. Zushi, M. Hasegawa, K. Nakamura, A. Fujisawa, H. Idei, Y. Nagashima, O. Watanabe, T. Onchi, H. Watanabe, K. Tokunaga, A. Higashijima, S.Kawasaki, H.Nakashima, T.Nagata, Y.Takase, A.Fukuyama, and O.Mitarai, Investigation of hydrogen recycling property and its control with hot wall in long duration discharges on QUEST, Nuclear Fusion, 10.1088/1741-4326/aa8121, 57 (2017) 126061 (10pp), 2017.10, Abstract. Fully non-inductive plasma maintenance was achieved by a microwave of 8.2 GHz and 40 kW for more than 1 h 55 min with a well-controlled plasma-facing wall (PFW) temperature of 393 K using a hot wall on the middle-sized spherical tokamak QUEST until, finally, the discharge was terminated by the uncontrollability of the density. The PFW was composed of atmospheric plasma-sprayed tungsten and stainless steel. The hot wall plays essential roles in reducing the amount of wall-stored H and facilitating hydrogen recycling. The behaviour of fuel hydrogen in the PFW was investigated by monitoring the injection and evacuation of hydrogen into and from the plasma-producing vessel. A fuel particle balance equation based on the presence of a hydrogen transport barrier between the deposited layer and the substrate was applied to the long-duration discharges. It was found that the model could readily predict the observed behaviour that a higher wall temperature likely gives rise to faster wall saturation..
4. Kazuaki Hanada, H. Zushi, Hiroshi Idei, K. Nakamura, M. Ishiguro, S. Tashima, E. I. Kalinnikova, Yoshihiko Nagashima, Makoto Hasegawa, akihide fujisawa, A. Higashijima, S. Kawasaki, H. Nakashima, O. Mitarai, A. Fukuyama, Y. Takase, X. Gao, H. Liu, J. Qian, M. Ono, R. Raman, Power Balance Estimation in Long Duration Discharges on QUEST, Plasma Science and Technology, 10.1088/1009-0630/18/11/03, 18, 11, 1069-1075, 2016.11, Fully non-inductive plasma start-up was successfully achieved by using a well-controlled microwave source on the spherical tokamak, QUEST. Non-inductive plasmas were maintained for approximately 3-5 min, during which time power balance estimates could be achieved by monitoring wall and cooling-water temperatures. Approximately 70%-90% of the injected power could be accounted for by calorimetric measurements and approximately half of the injected power was found to be deposited on the vessel wall, which is slightly dependent on the magnetic configuration. The power distribution to water-cooled limiters, which are expected to be exposed to local heat loads, depends significantly on the magnetic configuration, however some of the deposited power is due to energetic electrons, which have large poloidal orbits and are likely to be deposited on the plasma facing components..
5. K.Hanada, H.Zushi, N.Yosida, N.Yugami, T.Honda, M.Hasegawa, K.Mishra, A.Kuzmin, K.Nakamura, A.Fujisawa, H. Idei, Y.Nagashima, O.Wtanabe, T.Onchi, H. Watanabe, K. Tokunaga, A.Hgashijima, S.Kwasaki, H.Nakashima, Particle balance in long duration RF driven plasmas on QUEST, Journal of Nuclear Materials, Vol.463, 1084-1086, 2015.08.
6. Kazuaki Hanada, Hideki Zushi, Hiroshi Idei, Kazuo Nakamura, Masaki Ishiguro, Saya Tashima, Evgeniya Kalinnikova, Mizuki Sakamoto, Makoto Hasegawa, Akihide Fujisawa, Konosuke Sato, Naoaki Yoshida, Hideo Watanabe, Kazutoshi Tokunaga, Yoshihiko Nagashima, Aki Higashijima, Shoji Kawasaki, Hisatoshi Nakashima, Haiqing Liu, Osamu Mitarai, Takashi Maekawa, Atsushi Fukuyama, Yuichi Takase, Jinping Qian, QUEST Experiments Towards Steady State Operation of Spherical Tokamaks, IEEJ Transactions on Fundamentals and Materials, 132.0, 7.0, 490.0-498.0, 2012.07, QUEST計画の大きな目標の一つは、高温プラズマの定常化にかかわる研究である。本論文は、論文は論文は発表時点での長時間維持についての報告（国際球状トカマクワークショップ：平成23年11月於核融合科学研究所）をまとめたものである。特に長時間運転での粒子バランスについてのポイントモデルを用いて、QUESTのパラメータを用いると粒子バランスの定常化に必要な時間が1018秒程度になることを示した。.
7. Ishiguro, Masaki; Hanada, Kazuaki; Liu, Haiqing; Zushi, Hideki; Nakamura, Kazuo; Fujisawa, Akihide; Idei, Hiroshi; Nagashima, Yoshihiko; Hasegawa, Makoto; Tashima, Saya; Takase, Yuichi; Kishimoto, Yasuaki; Mitarai, Osamu; Kawasaki, Shoji; Nakashima, Hisatoshi; Higashijima, Aki, Non-inductive current start-up assisted by energetic electrons in Q-shu University experiment with steady-state spherical tokamak, PHYSICS OF PLASMAS, 10.1063/1.4731700, 19.0, 6.0, Article No. 062508, 2012.06, After intensive discharge cleaning of the chamber wall, non-inductive current start-up experiments have been successfully performed in QUEST in moderate vertical fields of about 1.0-1.5mT with positive n-index. Simultaneously, with increasing plasma current, an asymmetric toroidal flow of energetic electrons was observed and direct measurements of current driven by this asymmetric flow were taken with a newly developed Langmuir probe technique. A numerical study of the energetic electron orbits indicates that the total current is enough to play a dominant role in the formation of a closed flux surface in QUEST. (C) 2012 American Institute of Physics. [http://dx.doi.org/10.1063/1.4731700].
8. Hanada, K.; Sasaki, K.; Zushi, H.; Nakamura, K.; Sato, K. N.; Sakamoto, M.; Idei, H.; Hasegawa, M.; Kawasaki, S.; Nakashima, H.; Higashijima, A., Metallic dusts behavior in all-metal first wall on TRIAM-1M, JOURNAL OF NUCLEAR MATERIALS, 10.1016/j.jnucmat.2010.11.017, 415.0, 1.0, S1123-S1126, 2011.08, Metallic dust behavior was observed in full lower hybrid current drive plasmas on TRIAM-1M, which had all-metal plasma facing components. TRIAM-1M was shut-down on December 2005 and then in-vessel dusts were collected with a suction aspirator through a membrane filter of 100 nm meshes. The toroidal distribution of the total mass of collected in-vessel dusts was measured and the largest amount was found to be near the vertical movable limiter (VML). The typical size of in-vessel dusts was 1-10 mu m and the impact on augmenting the surface area was not significant. Dusts were observed to be either flaky or spherical in form and the majority of the flakes had accumulated around the VML Eruption detritus were observed on the surface of large flakes and this suggests that the burst of blistering are one of the origins of in-vessel dusts. (C) 2010 Elsevier B.V. All rights reserved..
9. Hanada, K.; Zushi, H.; Idei, H.; Nakamura, K.; Ishiguro, M.; Tashima, S.; Kalinnikova, E. I.; Sakamoto, M.; Hasegawa, M.; Fujisawa, A.; Higashijima, A.; Kawasaki, S.; Nakashima, H.; Liu, H.; Mitarai, O.; Maekawa, T.; Fukuyama, A.; Takase, Y.; Qian, J., Non-Inductive Start up of QUEST Plasma by RF Power, PLASMA SCIENCE & TECHNOLOGY, 10.1088/1009-0630/13/3/08, 13.0, 3.0, 307.0-311.0, 0.0, 2011.06, Both start-up and sustainment of plasma were successfully achieved by fully non-inductive current drive using microwave with a frequency of 8.2 GHz. Plasmas current of 15 kA was implemented for 1 s. Magnetic surface reconstruction exhibited a plasma shape with an aspect ratio of below 1.5. The plasma current was dependent significantly on the launched microwave power and vertical magnetic field, while not affected by the mode of launched wave and the toroidal refractive index. Hard X-ray (HXR) emitted from energetic electrons accelerated by the microwave was observed, and the discharge with a plasma current over 4 kA followed the same trend as the number of photons of 10 keV to 12 keV. This suggests that the plasma current may be driven by energetic electrons. Based on the experimental conditions, alternative explanations of how the plasma current could be driven are discussed..
10. Kazuaki HANADA, Keisuke SASAKI, Makoto HASEGAWA, Hiroshi IDEI, Hideki ZUSHI, Kazuo NAKAMURA, Mizuki SAKAMOTO, Konosuke SATO, Shoji KAWASAKI, Hisatoshi NAKASHIMA, Aki HIGASHIJIMA and TRIAM group, Current profile estimation in full LHCD plasmas using Hard X-ray measurement along the top and bottom identical line of sight on TRIAM-1M, Plasma and Fusion Research, 2.0, RA, 2007.11, A new technique to measure the current profile in plasmas with asymmetric distribution function such as lower hybrid current drive (LHCD) by using hard X-ray (HXR) energy spectrum measurement along the top and bottom identical line of sights (ILOS) is proposed and is applied to the full and partially LHCD plasmas on the TRIAM-1M tokamak at the first time in the world. The pitch angles were measured at R - R0 = (plus/minus) 2.5 cm, where R, R0 mean the major radii of the ILOS and the magnetic axis, respectively. The measured pitch angle of the magnetic field inverted at the magnetic axis estimated magnetic measurement in partially LHCD plasmas. This indicates that the difference of the measured pitch angles is caused by the plasma current in the plasma and this new method is available in detecting the current profile in tokamaks. In full LHCD plasma, no difference between the HXR signals along the top and bottom ILOS appear. This indicates that the current density around the magnetic axis was reduced compared with that in partially LHCD plasmas. This observation is no contradiction with power deposition of LHCD..
11. Hanada, K.; Sugata, T.; Sakamoto, M.; Zushi, H.; Nakamura, K.; Sato, K. N.; Idei, H.; Hasegawa, M.; Higashijima, A.; Kawasaki, S.; Nakashima, H., Power balance investigation in steady-state LHCD discharges on TRIAM-1M, FUSION ENGINEERING AND DESIGN, 10.1016/j.fusengdes.2006.03.004, 81.0, 19.0, 2257.0-2265.0, 0.0, 2006.09, A discharge longer than 5h was successfully achieved on TRIAM-1M by fully non-inductive lower hybrid current drive (LHCD). The heat load distribution into the plasma facing components (PFCs) during the 5 h discharge was investigated using calorimetric measurements, which estimated that the injected radio frequency (RF) power coincided with the total heat load amount to the PFCs. The power balance, including the portion of direct loss power of the fast electrons and the heat flux due to the charge exchange (CX) process, was also investigated. (c) 2006 Elsevier B.V. All rights reserved..
12. Shiraiwa, S; Hanada, K; Hasegawa, M; Idei, H; Kasahara, H; Mitarai, O; Nakamura, K; Nishino, N; Nozato, H; Sakamoto, M; Sasaki, K; Sato, K; Takase, Y; Yamada, T; Zushi, H, Heating by an electron Bernstein wave in a spherical tokamak plasma via mode conversion, PHYSICAL REVIEW LETTERS, 10.1103/PhysRevLett.96.185003, 96.0, 18.0, 0.0-0.0, Article No. 185003, 2006.05, The first successful high power heating of a high dielectric constant spherical tokamak plasma by an electron Bernstein wave (EBW) is reported. An EBW was excited by mode conversion (MC) of an X mode cyclotron wave injected from the low magnetic field side of the TST-2 spherical tokamak. Evidence of electron heating was observed as increases in the stored energy and soft x-ray emission. The increased emission was concentrated in the plasma core region. A heating efficiency of over 50% was achieved, when the density gradient in the MC region was sufficiently steep..
Presentations
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1. K. Hanada,M. Hasegawa,N. Yoshida,H. Idei,R. Ikezoe,T. Onchi,K. Kuroda, M. Oya,Q.Yue,S. Kojima,Y. Oya,T. Shikama,A. Kuzmin,N. Yoneda,I. Takagi, M. Miyamoto,A. Hatayama,K. Hoshino,T. Ido,Y. Nagashima,K. Nakamura, H. Watanabe,K. Tokunaga,S. Kawasaki,K. Kono,A. Higashijima,T. Nagata, S. Shimabukuro,A. Ejiri, Y.Takase,S. Murakami,X. Gao,H. Liu,J. Qian,R. Raman, and M. Ono, Control of fuel particle recycling using the hot wall on all-metal plasma facing wall in QUEST, IAEA Technical Meeting on Long-Pulse Operation of Fusion Devices, 2022.11.
2. T. Onchi , H. Idei , M. Fukuyama , R. Kato , M. Kudo , R. Takeda , Y. Zhang , A. Kidani , S. Kojima , T. Kariya , A. Ejiri , Y. Osawa , Y. Peng , O. Watanabe , M. Hasegawa , K. Nakamura , K. Kuroda , R. Ikezoe , T. Ido , K. Hanada , N. Bertelli , M. Ono , and A. Fukuyama , Plasma current start-up through injection of harmonic electron cyclotron waves on the QUEST spherical tokamak
, Korea-Japan Workshop on Physics and Technology of Heating and Current Drive, 2021.02.
3. ＠K. Hanada,＠N. Yoshida, ＠M. Hasegawa, ＠M. Oya, ＠Y. Oya, ＠I. Takagi, A. Hatayama, T.Shikama, H. Idei, Y. Nagashima, R. Ikezoe, T. Onchi, K. Kuroda, S. Kawasaki, A. Higashijima, T. Nagata, S. Shimabukuro, K. Nakamura, S. Murakami, Y.Takase, X. Gao, H. Liu, J. Qian, Overview of Recent Progress on Steady State Operation of All-metal Plasma Facing Wall Device,QUEST, the 24th International Conference on Plasma Surface Interaction in Fusion Devices (PSI-24), 2021.01.
4. K. Hanada, N. Yoshida, M. Hasegawa, A. Hatayama, K. Okamoto, I. Takagi, Y. Oya, M.Miyamoto, M. Oya, T. Shikama, A. Kuzmin, Z. X. Wang, H. Long, S. Kojim, H. Idei, Y. Nagashima, K. Nakamura, O. Watanabe, T. Onchi, H. Watanabe, K. Tokunaga, A. Higashijima, S. Kawasaki, H. Nakashima, T. Nagata, S. Shimabukuro, Y. Takase, S. Murakami, X. Gao, H. Liu, J. Qian, R. Raman, and M. Ono, Fuel particle balance for steady state operation on all-metal fusion experimental device, QUEST., 2nd Asia-Pacific Conference on Plasma Physics (AAPPS-DPP2018), 2018.11.
5. K. Hanada, N. Yoshida, M. Hasegawa, A. Hatayama, K.Okamoto, I. Takagi, T. Hirata, Y.Oya, M.Miyamoto, M. Oya, T. Shikama, A. Kuzmin, Z. X. Wang, H. Long, H. Idei, Y. Nagashima, K.Nakamura, O. Watanabe, T. Onchi, H. Watanabe, K. okunaga, A. Higashijima, S.Kawasaki, H.Nakashima, T.Nagata, S.Shimabukuro, Y.Takase, S. Murakami, X. Gao, H. Liu, J.Qian, R. Raman, and M. Ono., Particle balance investigation with the combination of rate equations of hydrogen state and hydrogen barrier model in long duration discharges on all-metal PFW QUEST, 27th IAEA Fusion Energy Conference (FEC2018), 2018.10.
6. K. Hanada, N. Yoshida, I. Takagi, T.Hirata, A. Hatayama, K. Okamoto, Y. Oya, T. Shikama, Z. Wang, H. Long, M. Oya, H. Idei, Y. Nagashima, T. Onchi, M. Hasegawa, K. Nakamura, H. Zushi, K. Kuroda, S. Kawasaki, A. Higashijima, T. Nagata, S. Shimabukuro, Y. Takase, S. Murakami, X. Gao, H. Liu, J. Qian, R. Raman, and M. Ono, Estimation of Fuel Particle balance in steady state operation with hydrogen barrier model, PSI 2018, 2018.06.
7. K.Hanada, H.Idei, N.Yoshida, M.Hasegawa, K.Nakamura, H.Zushi1, A.Fujisawa, Y.Nagashima, T.Onchi, K.Kuroda, S.Kawasaki, A.Higashijima, T.Nagata, S.Shimabukuro, A.Fukuyama2, O.Mitarai3, Y.Takase, R.Raman, and M.Ono, Overview of recent progress on plasma current start-up and long-duration plasma maintenance in QUEST, 19th International Spherical Torus Workshop (ISTW 2017), 2017.09.
8. K. Hanada, N. Yoshida, T. Honda, H. Idei, Z. Wang, A. Kuzmin, I. Takagi, T. Hirata, Y. Oya, M. Miyamoto, H. Zushi, M. Hasegawa, K. Nakamura, A. Fujisawa, H. Idei, Y. Nagashima, O. Watanabe, T. Onchi, H. Watanabe, Investigation of hydrogen recycling property and its control with hot wall in long duration discharges on QUEST, FEC-26(IAEA), 2016.10.
9. 花田 和明, 吉田 直亮, 本田 拓己, Z.Wang, A.Kuzumin, I. Takagi, Y. Oya, M. Miyamoto, H. Zushi, 長谷川 真, 中村 一男, Akihide Fujisawa, H. Idei, 永島 芳彦, O. Watanabe, 恩地 拓己, 渡邉 英雄, 德永 和俊, Investigation of the role of deposition layer in hydrogen recycling property on QUEST, PSI2016, 2016.05.
10. hanada kazuaki, H. Idei, Naoaki Yoshida, zushi hideki, Kazuo Nakamura, Akihide Fujisawa, Nagashima Yoshihiko, Makoto Hasegawa, 渡邉 理, Takumi Onchi, Aleksandrovich Arseniy Kuzmin, H. Watanabe, A.Higashijima, S.Kawasaki, H.Nakashima, T.Nagata, T.Kariya, T.Imai, A.Ejiri, Recent progress on non-inductive current drive and particle balance control towards steady-state operation on QUEST, The 18th International Spherical Torus Workshop (ISTW-2015), 2015.11.
11. hanada kazuaki, Naoaki Yoshida, Takumi Honda, KUZMIN ARSENIY ALEKSANDROVI, Hideki zushi, Ikuji Takagi, Akiyoshi Hatayama, Akihide Fujisawa, Kazuo Nakamura, Hiroshi Idei, Yoshihiko Nagashima, makoto hasegawa, Takumi Onchi, Aki Higashijima, Shoji Kawasaki, Hisatoshi Nakashima, 渡邉 理, Osamu Mitarai, Atsushi Fukuyama, Dynamic retention characteristics in RF driven long duration discharges on QUEST, 8th IAEA Technical Meeting on Steady State Operations of Magnetic Fusion Devices, 2015.05.
12. hanada kazuaki, Investigation of particle balance in long duration discharges on QUEST, Third Kyushu Workshop on Solenoid-Free RF-Only ST Plasmas, 2015.03.
13. hanada kazuaki, Plasma wall interaction in long duration plasmas on ST, プラズマ・核融合学会第31回年会 / PLASMA2014/シンポジウム9：定常プラズマ運転進展に向けた物理工学課題の国際連携研究, 2014.11.
14. hanada kazuaki, Naoaki Yoshida, hideki zushi, Kazuo Nakamura, Akihide Fujisawa, Hiroshi Idei, Yoshihiko Nagashima, HIDEO WATANABE, makoto hasegawa, Investigation of Progression from Low to High Hydrogen Recycling during Long Duration Discharges on a Spherical Tokamak, QUEST, 25th Fusion Energy Conference (FEC 2014), 2014.10.
15. hanada kazuaki, hideki zushi, Naoaki Yoshida, makoto hasegawa, K. Mishra, KUZMIN ARSENIY ALEKSANDROVI, Kazuo Nakamura, Akihide Fujisawa, Hiroshi Idei, Yoshihiko Nagashima, 渡邉 理, Takumi Onchi, Particle balance in long duration RF driven plasmas on QUEST, 21st International Conference on Plasma Surface Interactions 2014, 2014.05.
16. kazuaki hanada, Recent progress on non-inductive driven plasma start-up and investigation towards EBWCD on QUEST, International Spherical Torus Workshop 2013, 2013.09.
17. kazuaki hanada, hideki zushi, Hiroshi Idei, Kazuo Nakamura, M.Ishiguro, S.Tashima, Power balance estimation in long duration discharges on QUEST, A3 Foresight Program Workshop on Critical Physics Issues Specific to Steady State Sustainment of High-Performance Plasmas 19-24 May, 2013, Beijing, China, 2013.05.
18. kazuaki hanada, Recent QUEST experiments on non-inductive current drive and plasma-wall interaction towards steady, 7th IAEA Technical Meeting on Steady-State Operation og Magnetic Fusion Devices; 14-17 May 2013; Aix en Provence, France, 2013.05.
19. hanada kazuaki, Heat and particle handling, Workshop on QUEST and Ralatad ST RF Startup and Sustainment Plasma Research, 2013.02.
20. hanada kazuaki, Present status of QUEST experiment, NIFS ST Workshop, 2012.02.
21. hanada kazuaki, QUEST experiments towards steady state operation of spherical tokamaks, The Joint Meeting of 5th IAEA Technical Meeting on Spherical Tori 16th International Workshop on Spherical Torus (ISTW2011), 2011 US-Japan Workshop on ST Plasma September 27-30, 2011, National Institute for Fusion Science, Toki, Japan, 2011.09.
Educational
Educational Activities
In Kyoto University, the education for graduated students on experiments, data aquisition, and deta analysis by use of the big experimental devices was executed. In University of Tokyo, the education for graduated students on experiments, data aquisition, and deta analysis by use of the big experimental devices was executed and the education for under-graduated students on the experiments by the table-top device was also executed. In kyushu University, the education for graduated students on experiments, data aquisition, and deta analysis by use of the big experimental devices was executed and the lectures on magneto-hydro-dynamics and instability in the plasma.


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