Reference design of the power supply system for the resistive-wall-mode control in JT-60SA

Ferro, A.*; Gaio, E.*; Novello, L.*; Matsukawa, Makoto; Shimada, Katsuhiro; Kawamata, Yoichi; Takechi, Manabu

Fusion Engineering and Design, 98-99, p.1053 - 1057, 2015/10

https://doi.org/10.1016/j.fusengdes.2015.06.116

Overview of the new magnet power supply systems of JT-60SA procured by EU

Novello, L.*; Baulaigue, O.*; Coletti, A.*; Dumas, N.*; Ferro, A.*; Gaio, E.*; Lampasi, A.*; Maistrello, A.*; Matsukawa, Makoto; Shimada, Katsuhiro; et al.

Fusion Engineering and Design, 98-99, p.1122 - 1126, 2015/10

https://doi.org/10.1016/j.fusengdes.2015.06.014

Progress of the ITER NBI acceleration grid power supply reference design

Toigo, V.*; Zanotto, L.*; Bigi, M.*; Decamps, H.*; Ferro, A.*; Gaio, E.*; Gutirrez, D.*; Tsuchida, Kazuki; Watanabe, Kazuhiro

Fusion Engineering and Design, 88(6-8), p.956 - 959, 2013/10

https://doi.org/10.1016/j.fusengdes.2013.01.013

This paper reports the progress in the reference design of the Acceleration Grid Power Supply (AGPS) of the ITER Neutral Beam Injector (NBI). The design of the AGPS is very challenging, as it shall be rated to provide about 55 MW at 1 MV dc in quasi steady-state conditions; moreover, the procurement of the system is shared between the European Domestic Agency (F4E) and the Japanese Domestic Agency (JADA), resulting in additional design complication due to the need of a common definition of the interface parameters. A critical revision of the main design choices is presented also in light of the definition of some key interface parameters between the two AGPS subsystems. Moreover, the verification of the fulfillment of the requirements in any operational conditions taking into account the tolerance of the different parameters is also reported and discussed.

A Conceptual design study for the error field correction coil power supply in JT-60SA

Matsukawa, Makoto; Shimada, Katsuhiro; Yamauchi, Kunihito; Gaio, E.*; Ferro, A.*; Novello, L.*

Plasma Science and Technology, 15(3), p.257 - 260, 2013/03

https://doi.org/10.1088/1009-0630/15/3/13

To realize high performance plasmas in tokamak devices, error field correction (EFC) is one of the very important issues. Actually, error field correction coil is being planned in ITER using superconducting coils, while normal copper coils will be employed in JT-60SA. Similar coils are installed and under operation in many devices over the world. In the case of JT-60SA, EFC coils will be realized by 12 (or 18) sector coils installed inside the vacuum vessel. This paper describes a conceptual design study for the circuit configuration and control strategy of the power supply system of these EFC coils. In conclusion, to minimize the number of current feeders and semiconductor power devices, multi-phase inverter is the best solution not only from the cost merit but also from a view point of canceling the induced voltage of axisymmetric magnetic component.

Final design of the quench protection circuits for the JT-60SA superconducting magnets

Gaio, E.*; Maistrello, A.*; Coffetti, A.*; Gargano, T.*; Perna, M.*; Novello, L.*; Coletti, A.*; Matsukawa, Makoto; Yamauchi, Kunihito

IEEE Transactions on Plasma Science, 40(3), p.557 - 563, 2012/03

https://doi.org/10.1109/TPS.2011.2171008

Electromagnetic analyses on radial field sector coils for JT-60SA

Ferro, A.*; Gaio, E.*; Takechi, Manabu; Matsukawa, Makoto

Fusion Engineering and Design, 86(6-8), p.1527 - 1530, 2011/10

https://doi.org/10.1016/j.fusengdes.2010.12.009

In JT-60SA, to achieve the steady-state high beta plasma, suppression of Resistive Wall Modes (RWM) is necessary. Therefore, a passive stabilizing plate and a RWM active control system based on in-vessel coils are foreseen for JT-60SA. This paper deals with the electromagnetic analyses on the sector coils of JT-60SA, with the main aim to determine the voltage/current characteristic of the coils and, at the same time, to have a first estimation of amplitude and shape of the produced magnetic field; different sector coil design solutions were considered and evaluated. The studies on the coil over-currents during plasma disruption or vertical displacement events are also presented. The results give useful indications in support to the development of the sector coils and power supply design and the identification of their electrical and functional requirements.

A Design study of stable coil current control method for back-to-back thyristor converter in JT-60SA

Shimada, Katsuhiro; Terakado, Tsunehisa; Matsukawa, Makoto; Cara, P.*; Baulaigue, O.*; Gaio, E.*; Coletti, R.*; Candela, G.*; Coletti, A.*

Journal of Plasma and Fusion Research SERIES, Vol.9, p.163 - 168, 2010/08

Optimization of plasma initiation scenarios in JT-60SA

Matsukawa, Makoto; Terakado, Tsunehisa; Yamauchi, Kunihito; Shimada, Katsuhiro; Cara, P.*; Gaio, E.*; Novello, L.*; Ferro, A.*; Coletti, R.*; Santinelli, M.*; et al.

Journal of Plasma and Fusion Research SERIES, Vol.9, p.264 - 269, 2010/08

Status of JT-60SA tokamak under the EU-JA broader approach agreement

Matsukawa, Makoto; Kikuchi, Mitsuru; Fujii, Tsuneyuki; Fujita, Takaaki; Hayashi, Takao; Higashijima, Satoru; Hosogane, Nobuyuki; Ikeda, Yoshitaka; Ide, Shunsuke; Ishida, Shinichi; et al.

Fusion Engineering and Design, 83(7-9), p.795 - 803, 2008/12

https://doi.org/10.1016/j.fusengdes.2008.06.047

no abstracts in English

Design study of plasma control system on JT-60SA for high beta operation

Takechi, Manabu; Matsunaga, Go; Kurita, Genichi; Sakurai, Shinji; Fujieda, Hirobumi*; Ide, Shunsuke; Aiba, Nobuyuki; Bolzonella, T.*; Ferro, A.*; Novello, L.*; et al.

no journal, , 

One of the important missions of JT-60SA is to demonstrate and develop steady-state high beta operation in order to supplement ITER toward DEMO. Specifications of plasma control system including the stabilizing plate, the RWM control coils, the error field correction coils and fast position control coils were determined based on simulations and expected plasma regime. Full non-inductive steady-state plasma with at MA will be achieved with these control systems. Simulation of plasma disruption was also performed to evaluate design values of Electro Magnetic forces of components.