Status of JT-60SA tokamak under the EU-JA Broader Approach Agreement

Matsukawa, M.; Kikuchi, M.; Fujii, T.; Fujita, Takashi; Hayashi, Takao; Higashijima, S.; Hosogane, N.; Ikeda, Yoshitaka; Ide, S.; Ishida, S.; Kamada, Y.; Kimura, Hiroyuki; Kizu, K.; Kurihara, Kazuo; Kurita, G.; Masaki, K.; Matsunaga, G.; Miya, N.; Moriyama, S.; Sakasai, A.; Sakurai, S.; Shibama, Yusuke; Shimada, Kaoru; Sukegawa, Atsuhiko M.; Suzuki, T.; Suzuki, Y.; Takase, Y.; Takechi, M.; Tamai, Hiroshi; Tsuchiya, Kazuyoshi; Urano, H.; Yamamoto, T.; Yoshida, Kiyoshi; Andreani, Roberto; Alonso, J.; Barabaschi, P.; Botija, J.; Cara, Philippe; Coletti, A.; Coletti, R.; Costa, P.; Cucchiaro, A.; Decool, P.; Corte, A. della; Dolgetta, N.; Duchateau, J.L.; Fietz, W.H.; Gaio, E.; Grosman, A.; Gruber, O.; Heller, R.; Henry, D.; Hertout, P.; Hourtoule, J.; Lacroix, Benoît; Magne, R.; Medrano, M.; Michel, Frédéric; Muzzi, L.; Nicollet, S.; Novello, L.; Petrizzi, L.; Piovan, R.; Pizzuto, A.; Portafaix, C.; Rincón, E.; Roccella, S.; Semeraro, L.; Turtù, S.; Verder, J.-M.; Villari, R.; Zani, L.; Zenobio, A. Di

doi:10.1016/j.fusengdes.2008.06.047

Cited by 22 publications

(8 citation statements)

References 2 publications

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“…This is required to overcome the above mentioned issue of material operating temperature gap between the heat sink and the plasma-facing material within a PFC. The preferred heat sink material currently used for PFC applications is the precipitation hardened CuCrZr Alloy [32,33,34,35]. W f /Cu composite materials are practically relevant as the constituent materials for such a composite are readily available and the composite can be produced straightforwardly by means of liquid Cu melt infiltration of open porous W fibre preforms.…”

Section: Tungsten-fibre Reinforced Coppermentioning

confidence: 99%

Materials development for new high heat-flux component mock-ups for DEMO

Coenen

Mao

Sistla

et al. 2019

Fusion Engineering and Design

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Material issues pose a significant challenge for future fusion reactors like DEMO. When using materials in a fusion environment a highly integrated approach is required. Damage resilience, power exhaust, as well as oxidation resistance during accidental air ingress are driving issues when deciding for new materials. Neutron induced effects e.g. transmutation adding to embrittlement are crucial to material performance. Here advanced materials such as tungsten fiber-reinforced tungsten W f /W and fiber-reinforced copper W f /Cu composites could allow the step towards a fusion reactor. Recent developments in the area W f /W mark a possible path towards a component mock-up early enough for utilisation in DEMO. High heat-flux tests show that having short fibres at the exposed surface leads to their selective erosion and melting. Initial tests in the linear plasma device PSI-2 confirm this behaviour.

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Section: Tungsten-fibre Reinforced Coppermentioning

confidence: 99%

Materials development for new high heat-flux component mock-ups for DEMO

Coenen

Mao

Sistla

et al. 2019

Fusion Engineering and Design

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“…Similarly the stabilizing plates have been discretized with 36 conductors placed in a central position with respect to its inner and outer walls. Table 1 summarizes the main geometrical data assumed for coils, which correspond to the conclusion of the machine re-baseline design in 2008 [1]. For superconducting coils the geometrical data at the 4 K operation temperature were considered.…”

Section: Poloidal Circuit Modelmentioning

confidence: 99%

“…The new satellite tokamak JT-60SA [1], to be built in Naka, Japan, will be equipped with a number of magnets aimed at producing the magnetic field for the generation and position control of the plasma current that can reach 5.5 MA with a flat-top time of 100 s. Both superconducting and copper magnets will be installed.…”

Section: Introductionmentioning

confidence: 99%

Overcurrent analyses in JT-60SA poloidal circuits due to plasma disruption and quench protection intervention

Novello

Gaio

Piovan

et al. 2011

Fusion Engineering and Design

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“…The JT-60SA device, which has 18 toroidal coils and 6 poloidal coils with superconducting magnets, will be installed in the present JT-60 torus hall [22,23]. A birdseye view of JT-60SA is shown in Fig.…”

Section: Target Of At Research In Jt-60samentioning

confidence: 99%

Advanced Tokamak Research in JT-60U and JT-60SA

Isayama

2010

Plasma and Fusion Research

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Results of experiment in JT-60U and design study in JT-60SA (Super Advanced) are described focusing on the development of advanced tokamak. In JT-60U, a high-integrated performance plasma with the normalized beta β N = 2.6, confinement enhancement factor H H98(y,2) = 1.0-1.1 and bootstrap current fraction f BS = 0.4 has been sustained for 25 s (14 times current diffusion time (τ R )). Neoclassical tearing mode (NTM) with the poloidal mode number m = 2 and the toroidal mode number n = 1 has been stabilized with modulated electron cyclotron current drive (ECCD) in synchronization with the mode frequency (∼5 kHz). A high-beta plasma exceeding the ideal MHD limit without conducting wall has been sustained for 5 s (∼3τ R ) by suppressing resistive wall mode (RWM). In addition, two new instabilities in the high-beta regime, Energetic particle driven Wall Mode (EWM) and RWM precursor, have been observed. In JT-60SA, exploration of full non-inductive steady-state operation with current drive by neutral beams and electron cyclotron waves is planned. In addition, NTM control with ECCD and RWM suppression with external coils are planned.

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Status of JT-60SA tokamak under the EU-JA Broader Approach Agreement

Cited by 22 publications

References 2 publications

Materials development for new high heat-flux component mock-ups for DEMO

Materials development for new high heat-flux component mock-ups for DEMO

Overcurrent analyses in JT-60SA poloidal circuits due to plasma disruption and quench protection intervention

Advanced Tokamak Research in JT-60U and JT-60SA

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