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Journal Articles

Development of operation scenarios for plasma breakdown and current ramp-up phases in JT-60SA tokamak

Urano, Hajime; Fujita, Takaaki*; Ide, Shunsuke; Miyata, Yoshiaki; Matsunaga, Go; Matsukawa, Makoto

Fusion Engineering and Design, 100, p.345 - 356, 2015/11

 Times Cited Count:6 Percentile:39.55(Nuclear Science & Technology)

The operation scenarios for plasma breakdown and current ramp-up phases in JT-60SA tokamak have been developed. The induced current in the in-vessel conducting elements such as vacuum vessel and stabilizing plate increases to the comparable level of plasma current of $$sim$$600 kA during the breakdown phase and thus enhances the strength of error field. The optimized scenarios for half and full pre-magnetization cases satisfied the conditions required for the plasma initiation. At the initial plasma, the vertical magnetic field required to sustain the plasma position was controlled by the outer equilibrium field (EF) coil currents which compensate for a vertical field due to a large eddy current. The condition for the formation of divertor configurations given by the combination of the magnetic flux for plasma and the plasma current enables us to develop the operational scenarios with a smooth transition from a limiter to a divertor configuration.

Journal Articles

Assessment of the accuracy of plasma shape reconstruction by the Cauchy condition surface method in JT-60SA

Miyata, Yoshiaki; Suzuki, Takahiro; Takechi, Manabu; Urano, Hajime; Ide, Shunsuke

Review of Scientific Instruments, 86(7), p.073511_1 - 073511_13, 2015/07

 Times Cited Count:3 Percentile:78.72(Instruments & Instrumentation)

It is essential for a stable plasma equilibrium control to reconstruct an accurate plasma boundary in tokamak devices. Cauchy Condition Surface (CCS) method is a numerical approach to calculate the spatial distribution of the magnetic flux outside a hypothetical plasma surface and reconstruct the plasma boundary from the magnetic measurements located outside the plasma. It is found that the optimum number of unknown parameters and shape of the CCS for minimizing errors in the reconstructed plasma shape increase in proportion to the plasma size. It is shown that the accuracy of the plasma shape reconstruction greatly improves by using the optimum number of unknown parameters. The assessment of accuracy of plasma shape reconstruction by CCS method in JT-60SA is reported.

Journal Articles

Advance in integrated modelling towards prediction and control of JT-60SA plasmas

Hayashi, Nobuhiko; Honda, Mitsuru; Shiraishi, Junya; Miyata, Yoshiaki; Wakatsuki, Takuma; Hoshino, Kazuo; Toma, Mitsunori; Suzuki, Takahiro; Urano, Hajime; Shimizu, Katsuhiro; et al.

Europhysics Conference Abstracts (Internet), 39E, p.P5.145_1 - P5.145_4, 2015/06

Journal Articles

Meeting report; 18th Plasma Seminar for young researchers

Fukumoto, Masakatsu; Miyata, Yoshiaki; Tojo, Hiroshi

Purazuma, Kaku Yugo Gakkai-Shi, 91(5), P. 371, 2015/05

"18th Plasma Seminar for young researches" (by Department of Advanced Plasma Research, Sector of Fusion Research and Development, Japan Atomic Energy Agency) was held in Naka Fusion Institute, March 3rd through 6th of 2015. The objective of this seminar is that the young researchers in charge of the future fusion research expand their cross-sectoral network. This seminar was entitled "Crystallization of technology of plasma measurement and control" and we invited the lectures not just for fusion plasma but for technology of plasma measurement and control to study the technology of measurement and control of different fields from their fields. There were 8 invited lectures and 17 public lectures and young researchers had an animated discussion.

Journal Articles

The Cauchy-condition surface (CCS) method for plasma equilibrium shape reproduction

Kurihara, Kenichi; Itagaki, Masafumi*; Miyata, Yoshiaki; Nakamura, Kazuo*; Urano, Hajime

Purazuma, Kaku Yugo Gakkai-Shi, 91(1), p.10 - 47, 2015/01

no abstracts in English

Journal Articles

Study of plasma equilibrium control for JT-60SA using MECS

Miyata, Yoshiaki; Suzuki, Takahiro; Ide, Shunsuke; Urano, Hajime

Plasma and Fusion Research (Internet), 9(Sp.2), p.3403045_1 - 3403045_5, 2014/05

The precise control of the plasma position is essential in safe and stable plasma operation. An MHD equilibrium control simulator has been developed in order to study the techniques of plasma equilibrium control for JT-60SA. In this study, the modules of plasma shape reconstruction, power supply, PF and FPPC coils are incorporated in order to simulate the real plasma equilibrium control. The plasma equilibrium control is simulated during Ip ramp-up within the power supply capability using MECS.

Journal Articles

Validation of plasma shape reconstruction by Cauchy condition surface method in KSTAR

Miyata, Yoshiaki; Hahn, S. H.*; Suzuki, Takahiro; Ide, Shunsuke; Chung, J.*; Bak, J. G.*; Ko, W. H.*

Physics of Plasmas, 21(3), p.032502_1 - 032502_11, 2014/03

 Times Cited Count:5 Percentile:67.01(Physics, Fluids & Plasmas)

Cauchy condition surface (CCS) method is a numerical approach to reconstruct the plasma boundary precisely and calculate the quantities related to plasma shape using small number of magnetic diagnostics in real time. It has been applied to the KSTAR plasma in order to establish the plasma shape reconstruction with the high elongation of plasma shape and the large effect of eddy current flowing in the structure for the first time. Calculations have been performed to validate the plasma shape reconstruction in 2012 KSTAR experimental campaign. Comparison between the CCS calculation and non-magnetic measurements revealed that the CCS calculation can reconstruct the accurate plasma shape even with a small Ip. The application of CCS calculation to the KSTAR plasma and the validation results of the plasma shape reconstruction are reported.

Journal Articles

Study of JT-60SA operation scenario using a plasma equilibrium control simulator

Miyata, Yoshiaki; Suzuki, Takahiro; Ide, Shunsuke; Urano, Hajime; Fujita, Takaaki

Plasma and Fusion Research (Internet), 8(Sp.1), p.2405109_1 - 2405109_6, 2013/08

The precise control of the plasma position is a key issue in safe and stable plasma operation. A plasma equilibrium control simulator has been developed in order to study the techniques of plasma equilibrium control for JT-60SA. The simulator consists of an equilibrium solver and controller. The equilibrium solver identifies the plasma equilibrium under the given coil current and unknown eddy current by iteration. The function which calculates the self-consistent $$I$$$$_{rm p}$$ with magnetic flux consumption has been incorporated in order to simulate the $$I$$$$_{rm p}$$ control. The waveforms of JT-60SA plasma operation scenario during the $$I$$$$_{rm p}$$ ramp-up and the controllability of the plasma equilibrium control using the equilibrium control simulator were reported.

Journal Articles

Optimization of JT-60SA plasma operational scenario with capabilities of installed actuators

Ide, Shunsuke; Aiba, Nobuyuki; Bolzonella, T.*; Challis, C. D.*; Fujita, Takaaki; Giruzzi, G.*; Joffrin, E.*; Hamamatsu, Kiyotaka; Hayashi, Nobuhiko; Honda, Mitsuru; et al.

Proceedings of 24th IAEA Fusion Energy Conference (FEC 2012) (CD-ROM), 8 Pages, 2013/03

Journal Articles

Investigation of the JT-60SA operation scenarios combined with integrated real-time controls

Suzuki, Takahiro; Hayashi, Nobuhiko; Urano, Hajime; Miyata, Yoshiaki; Honda, Mitsuru; Ide, Shunsuke; JT-60SA Team

Europhysics Conference Abstracts (Internet), 37D, p.P2.136_1 - P2.136_4, 2013/00

no abstracts in English

Journal Articles

Development of a simulator for plasma position and shape control in JT-60SA

Miyata, Yoshiaki; Suzuki, Takahiro; Fujita, Takaaki; Ide, Shunsuke; Urano, Hajime

Plasma and Fusion Research (Internet), 7, p.1405137_1 - 1405137_9, 2012/10

The plasma position and shape control is important issue in JT-60SA, ITER and future fusion reactor. In order to study the plasma position and shape control, we have developed a simulator which consists of an equilibrium solver and an "isoflux" controller. It is possible to simulate the position and shape control by using the "isoflux" technique and optimize the control logic of coil current in JT-60SA. It was demonstrated that the simulator can simulate the position and shape control in response to prescribed change in the configuration and internal parameters.

Journal Articles

Plasma domains and development of operation scenarios in JT-60SA

Ide, Shunsuke; Hayashi, Nobuhiko; Honda, Mitsuru; Urano, Hajime; Suzuki, Takahiro; Miyata, Yoshiaki; Aiba, Nobuyuki; Shiraishi, Junya; Kurita, Genichi; Fujita, Takaaki

Plasma and Fusion Research (Internet), 7(Sp.1), p.2403131_1 - 2403131_4, 2012/09

no abstracts in English

Journal Articles

Observation of radial particle transport induced by the fluctuation measured with a gold neutral beam probe

Kojima, Atsushi; Ishii, Kameo*; Miyata, Yoshiaki*; Kakiuchi, Hideto*; Kaido, Norihiro*; Yoshikawa, Masayuki*; Itakura, Akiyoshi*; Ichimura, Makoto*; Chujo, T.*

Fusion Science and Technology, 51(2T), p.274 - 276, 2007/02

 Times Cited Count:2 Percentile:79.6(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Simultaneous measurements of ion and electron currents using a novel compact electrostatic end-loss-current detector

Hirata, Mafumi*; Miyake, Yasuhiro*; Chujo, T.*; Kohagura, Junko*; Numakura, Tomoharu*; Shimizu, Kiyoaki*; Ito, Marie*; Kiminami, Serina*; Morimoto, Naomichi*; Hirai, Katsuaki*; et al.

Review of Scientific Instruments, 77(10), p.10E719_1 - 10E719_3, 2006/10

 Times Cited Count:0 Percentile:100(Instruments & Instrumentation)

no abstracts in English

Oral presentation

Development of simulator for plasma position and shape control in JT-60SA

Miyata, Yoshiaki; Suzuki, Takahiro; Fujita, Takaaki; Ide, Shunsuke; Urano, Hajime

no journal, , 

The plasma position and shape control is important issue in JT-60SA, ITER and future fusion reactor which has a small number of coils. In order to study the plasma position and shape control, we are developing a simulator which consists of an equilibrium solver and an "isoflux" controller. The controller controls poloidal field (PF) coil currents so as to keep the poloidal flux is equal at all of specified locations. The equilibrium solver identifies an equilibrium under the specified PF coil current and implements the effect of eddy current. The position and shape control has been simulated in response to prescribed change in the poloidal beta and the internal inductance due to heating.

Oral presentation

Development of discharge scenario using plasma equilibrium control simulator in JT-60SA

Miyata, Yoshiaki; Suzuki, Takahiro; Fujita, Takaaki; Ide, Shunsuke; Urano, Hajime

no journal, , 

no abstracts in English

Oral presentation

Investigation of JT-60SA operation scenario through development of equilibrium control simulator

Suzuki, Takahiro; Miyata, Yoshiaki; Ide, Shunsuke; Urano, Hajime; Fujita, Takaaki

no journal, , 

We have developed an equilibrium control simulator and investigated the JT-60SA operation scenario using the simulator. The simulator consists of an equilibrium construction component that solves temporal evolution of plasma coupled with conducting wall and a controller that controls the plasma current, position and shape via external coil current in the feedback manner. An operation scenario based on the feedback control has been developed, where the plasma current is raised by flux swing in center solenoids and plasma position and shapes are controlled in order to form divertor configuration and apply heating. Results on controllability of the position and shape during heating and flux swing and controllability of the vertical instability are presented as well.

Oral presentation

Assessment of the range of controls in JT-60SA plasmas and scenario development

Ide, Shunsuke; Aiba, Nobuyuki; Bolzonella, T.*; Challis, C. D.*; Fujita, Takaaki; Giruzzi, G.*; Joffrin, E.*; Hamamatsu, Kiyotaka; Hayashi, Nobuhiko; Honda, Mitsuru; et al.

no journal, , 

Oral presentation

Extending KSTAR operation regime for advanced operation scenario development

Suzuki, Takahiro; Kim, J. H.*; Na, Y. S.*; Ide, Shunsuke; Mueller, D.*; Miyata, Yoshiaki; Kim, H. S.*; Hahn, S. H.*; Yoon, S. W.*; Kim, W. C.*

no journal, , 

We have started advanced operation scenario development in KSTAR in this campaign, which opens up a new research area directly connecting to ITER and DEMO. The advanced scenario, which has higher performance than the standard H-mode, typically possesses lower internal inductance li (safety factor q above unity without sawtooth). In conventional KSTAR operation scenarios, divertor configuration with high elongation is realized after or near the end of Ip ramp-up, where sawtooth activity starts during the ramp-up before entering into the higher performance phase. Thus, we need a new KSTAR operation scenario without sawtooth during the Ip ramp-up and with lower li than unity. Our idea is to delay the inductive current penetration by simultaneous EC&NB heating application into the full-bore divertor plasma during the Ip ramp-up as early as possible. After the optimization, we have successfully established a start-up scenario without sawtooth throughout the Ip ramp-up. In a shot 7897, high $$beta_{N}sim2.5$$ reaching an advanced scenario regime has been achieved in ELM-free H-mode ($$H_{89P}sim2.3$$) at $$q_{95}sim6$$.

Oral presentation

Confinement characteristics of the extended operation regime of KSTAR toward advanced scenarios

Na, Y. S.*; Suzuki, Takahiro; Ide, Shunsuke; Mueller, D.*; Kim, J. H.*; Miyata, Yoshiaki; Kim, S. H.*; Kim, H. S.*; Jeon, Y. M.*; Bae, Y. S.*; et al.

no journal, , 

Development of advanced scenarios, an important experimental goal for the KSTAR project, has just begun. Target plasmas were successfully produced using large bore plasma and early divertor formation which exhibit low internal inductance with low magnetic shear at the centre and no sawtooth instability. Auxilliary heating during the current rampup phase was employed to slow the inductive current diffusion to the centre of the plasma. With respect to hybrid scenario development, so-called "Ip-overshoot" method being used in JET is applied for tailoring magnetic shear at reduced plasma current for higher poloidal beta and bootstrap current fraction. The confinement characteristics of these scenarios are investigated. Transport modeling is performed self-consistently with an integrated simulation package incorporating plasma equilibrium, transport, heating and current drive. Firstly, the current rampup phase is simulated and its impact on the target q-profile is addressed. Secondly, energy confinement of flattop phases is discussed. In addition, the non-inductive current drive fraction including the bootstrap current fraction is calculated. Lastly, these scenarios are compared with advanced scenarios developed in other tokamak devices and future directions in achieving advanced regimes are discussed.

28 (Records 1-20 displayed on this page)