Fusion Device data

Fusion Device data - JT60U

[Index] [DIII-D] [GAMMA10] [GekkoXII] [JT60] [LHD] [ST] [TRIAM] [W7AS] [W7X] [HT-7] [HT-7U] [EXTRAP] [TJ-II] [MST] [TPERX] [RFX] / [DPC home]

A. Device concept and components
Title of Device	JT-60U, Japan Atomic Energy Research Institute Tokamak-60 Upgrade
Organization	Japan Atomic Energy Research Institute
Location	Naka, Japan
Concept	tokamak [1]
Vacuum vessel: -- Plasma facing material:	carbon [1]
Divertor/limiter facing material	carbon-fiber composites [1]
Working Gas	D2 [1]
Boundary configuration:	divertor [1]
Toroidal magnetic field (on axis), B (T):	4.2 [1]
Remarks	-
B. Plasma geometry
Major radius, R(m):	~3.4 [1]
Minor radius, a(m):	~1.0 [1]
Plasma volume (m³):	< 100 [1]
Remarks:	Plasma elongation = 1.2-1.8 [1]
C. Plasma parameters (maximum values)
Central ion temperature, T_i (keV):	45 [2]
Central electron temperature, T_e (keV):	26 [3]
Line averaged plasma density, <n> (10²⁰ m^-3):	-
Central electron density, n (10²⁰ m^-3):	2.8 [4]
Plasma current, I (MA):	5 [13]
Discharge pulse duration (s):	15 [1]
Plasma beta, <β> (%):	2.7 [5]
Stored energy, (MJ):	10.9 [6]
Energy confinement time, τ_E (s):	1.1 [7]
Remarks:	-
D. Plasma heating and current drive (device values)
Ohmic heating, (MW):	-
NBI heating, (MW):	40 [8]
RF heating: -IC: (MW):	7 [9]
RF heating: -EC: (MW):	3 [10]
RF heating: -LH: (MW):	8 [11]
E. Reactor relevant plasma performance parameters
Triple fusion product, ( 10²⁰ keV s m^-3):	15.3 [2]
Q_DT factor (if available):	1.25 [12]
F. Input information
Date of entry	7-Mar-2003
Data was entered by:	-

Reference:

[1] N. Hosogane et al., "Development and Operational Experiences on the JT-60U Tokamak and Power Supplies", Fusion Science and Technology, 42, 368 (2002).
[2] S.Ishida et al., "HIGH PERFORMANCE EXPERIMENTS IN JT-60U HIGH CURRENT DIVERTOR DISCHARGES", Proc. 16th Inter. Conf. on Fusion Energy, Montreal, Vol.1, 315 (1996).
[3] S. Ishida and the JT-60 Team, "Recent Results and Future Plan on JT-60U", to be published in Proc. in 19th IEEE/NPSS Symposium on Fusion Engineering, Atlantic.
[4] Y. Kamada, et al., "Pellet injection with improved confinement in JT-60", Proc. 13th Inter. Conf. on Plasma Physics and Controlled Nuclear Fusion Research, Washington, Vol. 1, 291 (1991).
[5] Y. Kamada, et al, "High triangularity discharges with improved stability and confinement in JT-60U", Proc. 16th Inter. Conf. on Fusion Energy, Montreal, Vol.1, 247 (1996).
[6] S. Ishida, et al., "Achievement of High Fusion Performance in JT-60U Reversed Shear Discharges", Phys. Rev. Lett., 79, 3917 (1997).
[7] T. Fujita, et al., "High performance reversed shear plasmas with a large radius transport barrier in JT-60U", Nucl. Fusion, 38, 207 (1998).
[8] M.Kuriyama et al, "OPERATION AND DEVELOPMENT ON THE POSITIVE-ION BASED NEUTRAL BEAM INJECTION SYSTEM FOR JT-60 AND JT-60U", Fusion Science and Technology, 42, 410 (2002).
[9] H. Kimura et al., "ICRF HEATING AND TAE MODES IN REACTOR RELEVANT JT-60U DISCHARGES", Proc. 16th Inter. Conf. on Fusion Energy, Montreal, Vol.3, 295 (1996).
[10] Y. Ikeda et al., "The 110 GHz electron cyclotron range of frequency system on JT-60U: Design and operation", Fusion Science and Technology, 42, 435 (2002).
[11] Y. Ikeda et al., "Development and operation of JT-60 LHRF launchers Plasma Devices and Operations", Vol.1, 155 (1991).
[12] T. Fujita, et al., "High performance experiments in JT-60U reversed shear discharges", Nucl. Fusion, 39, 1627 (1999).
[13] JT-60TEAM(Presented by M.Kikuchi), "Recent JT-60U Result towards Steady State Operation of Tokamaks", Proc. 15th Inter. Conf. on Plasma Physics and Controlled Nuclear Fusion Research, Seville, Vol. 1, 31(1994).