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Zito, P.*; Lampasi, A.*; Novello, L.*; Matsukawa, Makoto; Shimada, Katsuhiro; Portesine, M.*; Fasce, F.*; Cinarelli, D.*; Dorronsoro, A.*; Vian, D.*
Proceedings of IEEE 15th International Conference on Environment and Electrical Engineering (IEEE-EEEIC 2015), p.156 - 160, 2015/06
Kawashima, Hisato; Sengoku, Seio; Uehara, Kazuya; Tamai, Hiroshi; Shoji, Teruaki*; Ogawa, Hiroaki; Shibata, Takatoshi; Yamamoto, Masahiro*; Miura, Yukitoshi; Kusama, Yoshinori; et al.
Fusion Science and Technology, 49(2), p.168 - 186, 2006/02
Times Cited Count：3 Percentile：24.11(Nuclear Science & Technology)Experimental efforts on JFT-2M have been devoted to understand SOL/Divertor plasmas and to investigate power and particle controllability. Open divertor configuration was used for the first decade of JFT-2M started in 1984. We found out the SOL/Divertor plasma properties such as in/out asymmetry, heat and particle diffusivities, and SOL current at ELMs. Handling of power and particle was demonstrated by active control methods such as local pumping, edge ergodization, divertor biasing, and edge heating. For improvement of power and particle control capability of divertor, it was modified to closed configuration in 1995, which demonstrated the baffling effects with narrower divertor throat. Dense and cold divertor state (n
= 4
10
m
and T = 4 eV), compatible with the improved confinement modes (e.g. H-mode), was realized by strong gas puffing. Being related with the core confinement at H-mode, the edge plasma fluctuations were identified by an electrostatic probe. These are reviewed in this paper.
analyses with ferromagnetic and plasma rotation effects and wall geometry for a high steady state tokamakKurita, Genichi; Bialek, J.*; Tsuda, Takashi; Azumi, Masafumi*; Ishida, Shinichi; Navratil, G. A.*; Sakurai, Shinji; Tamai, Hiroshi; Matsukawa, Makoto; Ozeki, Takahisa; et al.
Nuclear Fusion, 46(2), p.383 - 390, 2006/02
Times Cited Count：9 Percentile：31.21(Physics, Fluids & Plasmas)It is shown that critical beta is decreased by ferromagnetic effect by about 8% for 
/
2, and denoting the permeability of ferromagnetic wall and vacuum, respectively, for tokamak of aspect ratio 3. The existence of the stability window for resistive wall mode opened by both effects of the toroidal plasma rotation and the plasma dissipation, which was not observed for high aspect ratio tokamak, is found for tokamak of aspect ratio 3. The effect of ferromagnetism on them is also investigated. The critical beta analyses of NCT (National Centralized Tokamak) plasma using VALEN code are started with stabilizing plate and vacuum vessel geometry with finite resistivity, and the results for passive effect of stabilizing plate are obtained. The calculations including stabilizing effect of the vacuum-vessel and also active feedback control are also performed for present design of NCT plasma.
Shimada, Michiya; Costley, A. E.*; Federici, G.*; Ioki, Kimihiro*; Kukushkin, A. S.*; Mukhovatov, V.*; Polevoi, A. R.*; Sugihara, Masayoshi
Journal of Nuclear Materials, 337-339, p.808 - 815, 2005/03
Times Cited Count：65 Percentile：96.35(Materials Science, Multidisciplinary)ITER is an experimental fusion reactor for investigation and demonstration of burning plasmas, characterised of its heating dominated by alpha-particle heating. ITER is a major step from present devices and an indispensable step for fusion reactor development. ITER's success largely depends on the control of plasma-wall interactions(PWI), with power and particle fluxes and time scales one or two orders of magnitude larger than in present devices. The strategy for control of PWI includes the semi-closed divertor, strong fuelling and pumping, disruption and ELM control, replaceable plasma-facing materials and stepwise operation.
Nishitani, Takeo; Vayakis, G.*; Yamauchi, Michinori*; Sugie, Tatsuo; Kondoh, Takashi; Shikama, Tatsuo*; Ishitsuka, Etsuo; Kawashima, Hisato
Journal of Nuclear Materials, 329-333(Part2), p.1461 - 1465, 2004/08
Times Cited Count：16 Percentile：70(Materials Science, Multidisciplinary)no abstracts in English
Miura, Yukitoshi; Hoshino, Katsumichi; Kusama, Yoshinori
Purazuma, Kaku Yugo Gakkai-Shi, 80(8), p.653 - 661, 2004/08
A series of experimental program on the JAERI Fusion Torus-2M (JFT-2M) was completed in March, 2004. In the experimental operation for 21 years since the first plasma on April 27, 1983, many significant results leading the fusion energy research and plasma physics have been produced in researches on high confinement mode (H-mode), heating and current drive, advanced plasma control, compatibility of low activation ferritic steel with improved confinement mode, etc. Among these results, some important results are presented.
Sato, Minoru; Tsugita, Tomonori; Oshima, Takayuki; Sakata, Shinya; Iwasaki, Keita*; Matsuda, Toshiaki; Iba, Katsuyuki; Ozeki, Takahisa
Fusion Engineering and Design, 71(1-4), p.145 - 149, 2004/06
Times Cited Count：7 Percentile：45.11(Nuclear Science & Technology)Data processing system in JT-60 has been used CAMAC widely for control and data acquisition of plasma diagnostic. However, it has passed over fifteen years from the operation, and the problem is caused for maintenance and function enhancement by the deterioration. Then, Mini-computer and microcomputer ,which control the CAMAC system were replaced workstation based on UNIX-OS, and these system were remodeled by developing the application software for screen control by GUI and for constructing environment of remote diagnostic through the network. In addition, CAMAC device driver for Linux has been developed in for next CAMAC control system.
Tamai, Hiroshi; Kurita, Genichi; Matsukawa, Makoto; Urata, Kazuhiro*; Sakurai, Shinji; Tsuchiya, Katsuhiko; Morioka, Atsuhiko; Miura, Yushi; Kizu, Kaname; Kamada, Yutaka; et al.
Plasma Science and Technology, 6(3), p.2281 - 2285, 2004/06
Times Cited Count：0 Percentile：0.02(Physics, Fluids & Plasmas)High performance steady-state operation for JT-60SC are evaluated by the TOPICS analysis. 
5 and bootstrap current fraction 86% is kept steady at I
=1.5 MA, B
=2 T by neutral beam power of 11 MW. The ERATO-J analysis shows that the external-kink mode with multiple toroidal mode numbers of n=1 and n=2 is stable at 
5.5 at the average ratio of conducting wall radius to plasma minor radius of about 1.2 with the wall stabilisation effect. Resistive wall modes, induced by a close location of the wall to plasma, is expected to be suppressed by the active feedback stabilisation with a set of non-axisymmetric field coils behind the stabilising plates. Further optimisation for the high- accessibility by the plasma shaping is performed with the TOSCA analysis. The plasma shaping factor defined as S=(I/aB)q
and strongly correlated to the plasma elongation and triangularity, is scanned from 4 to 6, which extends the availability of current and pressure profile control for the high performance plasma operation.
Shimada, Michiya
Purazuma, Kaku Yugo Gakkai-Shi, 80(3), p.222 - 226, 2004/03
Discussion is made on objectives of edge plasma and plasma-wall interaction studies, divertor performance projection of ITER and key R&D issues on plasma-wall interaction including material issues, tritium retention, and transient events like ELMs and disruptions. A perspective of future development is discussed for the purpose of projection to and control of ITER plasma.
Takizuka, Tomonori; Hosokawa, Masanari*; Shimizu, Katsuhiro
Journal of Nuclear Materials, 313-316(1-3), p.1331 - 1334, 2003/03
Times Cited Count：15 Percentile：69.06(Materials Science, Multidisciplinary)In course of tokamak fusion research, particle and heat control is one of the most crucial issues. Helium ash exhaust and impurity retention in the divertor region owe to the plasma flow towards divertor plate. The localization of heat load on the plate depends on the flow pattern. Accordingly, particle and heat control can be achieved by the proper control of the flow in SOL and divertor plasmas. In this paper, the flow control is studied with two-dimensional particle simulations by PARASOL (PARticle Advanced simulation for SOL and divertor plasmas) code. Magnetic field configuration with separatrix like a tokamak divertor configuration is given. Hot particle source is put in the core plasma. Recycling cold particle source is located near the divertor plate. Particle source of gas puff in the SOL plasma is given for the flow control. Divertor biasing is available by changing the electrostatic potential on the plates. Effects of gas puff and biasing on the flow are studied. Controllability is evaluated from simulation results.
Tachibana, Mitsuo; Shiraishi, Kunio; Yanagihara, Satoshi
JAERI-Tech 2001-014, 42 Pages, 2001/03
In the JPDR dismantling demonstration project, the dismantling activities were conducted for the purpose of verification of remote dismantling machines and collection of various kinds of data on work activities. These lessons were categorized into safety consideration, waste treatment and work efficiency by analyzing the data on work activities. Exemplified are necessities of facility information, efficiency of mock-up tests for evaluation of remote dismantling procedures. There will be useful for implementing other decommissioning projects in safe and efficiency. This report describes the measure taken for remote dismantling activities and the lessons learned from the dismantling activities.
ITER Physics Expert Group on Disruptions, Plasma Control, and MHD; ITER Physics Expert Group on Energetic Particles, Heating and Current Drive; ITER Physics Expert Group on Diagnostics
Nuclear Fusion, 39(12), p.2577 - 2625, 1999/00
no abstracts in English
Kimura, Toyoaki; Kurihara, Kenichi; Kawamata, Yoichi; Akiba, K.*; ; Terakado, Tsunehisa; Yoshino, Ryuji
Fusion Technology, 32(3), p.404 - 415, 1997/11
no abstracts in English
Yoshino, Ryuji; Nakamura, Yukiharu; Neyatani, Yuzuru
Nuclear Fusion, 37(8), p.1161 - 1166, 1997/00
Times Cited Count：8 Percentile：30.9(Physics, Fluids & Plasmas)no abstracts in English
Senda, Ikuo*; Shoji, Teruaki; Tsunematsu, Toshihide; *; Fujieda, Hirobumi*
Nuclear Fusion, 37(8), p.1129 - 1145, 1997/00
Times Cited Count：9 Percentile：33.78(Physics, Fluids & Plasmas)no abstracts in English
Yoshino, Ryuji; JT-60 Team
Proc. of 36th IEEE Conf. on Decision and Control, 4, p.3709 - 3714, 1997/00
no abstracts in English
Yoshino, Ryuji; Nakamura, Yukiharu; Neyatani, Yuzuru
Nuclear Fusion, 36(3), p.295 - 307, 1996/00
Times Cited Count：35 Percentile：72.66(Physics, Fluids & Plasmas)no abstracts in English
; JT-60 Team
Fusion Technology 1994, 0, p.759 - 762, 1995/00
no abstracts in English
Kimura, Toyoaki; Kawamata, Yoichi; *
Fusion Technology 1994, 0, p.691 - 694, 1995/00
no abstracts in English
Kimura, Toyoaki; Kawamata, Yoichi; *
Fusion Technology 1994, Vol.1, 0, p.691 - 694, 1995/00
no abstracts in English
