Spherical Tokamak Table contents

ACST	S Korea Seoul	2000 - 2002	2	0.06	0.02	0.0005	-	-	-	-	AC operation. Helicon plasma discharge.
Asperator T-3	Japan Tohoku	1974 - ?	1.6	0.27	?	0.1
BATORM	Egypt, Cairo	1998	2	0.06	?	?	-	-	-	-	A very small tokamak used for materials testing and tokamak physics studies.
CDX-U Current Drive Experiment	USA, Princeton	1993-2004	1.4	0.3	0.23	0.03	-	-	-	-	FW heating. Now resurrected as the Lithium Tokamak Experiment, LTX.
CPD (Compact Plasma wall interaction Device)	Japan, Kasuga City	Approx. 2007	1.5	0.3	0.3	0.15	0.2	-	-	-	New spherical tokamak at Kyushu University. Only four TF coils, but they are large enough to give a tolerable ripple (8% at r = 0.5m). Includes a thermal lithium beam diagnostic for 2-D density. Also studying non-inductive start-up using ECRH.
ETE (Experimento Tokamak Esférico)	Brazil INPE	2000	1.5	0.3	0.6	0.4	-	-	-	-	Limiter machine
Globus-M	Russia IOFFE	2002	1.5	0.36	0.62	0.5	-	1	1.5	-	0.3 second pulses
GUTTA at IOFFE	Russia St Petersburg State University	1980-1985	2	0.16	1.5	0.15	0.03	-	-	-	Russia's first spherical tokamak.
GUTTA (at St Petersburg University)	Russia St Petersburg State University	2004	2	0.16	1.5	0.15	0.03	-	-	-	Formerly operated at IOFFE Institute. Operations restarted 2004 in St Petersburg State University. Start-up and ECRH studies.
HIST	Japan, Himeji	1998	1.3	0.3	0.2	0.1	-	-	-	-
HIT2	USA Seattle	1997-2004	1.5	0.3	0.6	0.37	-	-	-	-	Limiter / single null divertor machine to study Coaxial Helicity Injection (CHI).
HSE (Heidelberg Spheromak Experiment)	Germany Heidelberg	1986-1987	1.1	0.08	0.25	0.1	-	-	-	-	Heidelberg Spheromak Experiment was converted with an axial conductor to a Spherical Tokamak, and operated in this configuration for only a short time, 1986-7. This was the first spherical tokamak experiment at the several kG and 100 kA level. (Spheromak generated by theta-z-pinch method ( equipped with axial conductor. Full diameter of plasma: 0.3m, length of discharge vessel: 1m, Formation of plasma: ~14-20 microseconds, lifetime of plasma after formation: ~40-50 microseconds, magnetic energy content (in plasma ring): 600 J, electron temperature estimate: 15-20 eV.) Thanks to Hardo Bruhns for this information.
KTM Kazakh Tokamak for Material studies	Kazakhstan, Kurchatov	2011	2	0.9	1	0.75		5			Low aspect ratio tokamak for material testing. Will be able to exchange the divertor plates without breaking vacuum. 20 single turn TF coils. Thanks to Alexey Kirilenko for recent information.
LATE Low Aspect ratio Torus Experiment	Japan, Kyoto University	2005	1.25	0.25	0.12	0.004	0.2				Low aspect ratio spherical tokamak for material testing. Will be able to exchange the divertor plates without breaking vacuum. 20 single turn TF coils.
LTX, Lithium Tokamak Experiment	USA, Princeton	2005	1.5	0.4	0.4	0.4	-	-	-	-	Liquid lithium walls. FW heating.
MAST Mega Amp Spherical Tokamak	UK, Culham	1999	1.4	0.85	0.5	1.4	1	-	4	-	Merging compression technique to drive plasma current, saving solenoid flux.
MEDUSA (Madison EDUcational Small Aspect ratio)	USA Madison	1994 - ?	1.5	0.12	0.45	0.04	-	-	-	-	Test bed for educational purposes and studies leading to the construction of PEGASUS.
NSST Next Step Spherical Torus	USA Princeton	?	?	1.5	2.7	5-10	?	?	?	?	Proposed as the step between today's spherical tokamaks and a large Component Test Facility (CTF). Possibly to use the site that was previously used for TFTR.
NSTX	US Princeton	1999	1.4	0.85	0.6	1.4	?	3 HHFW	7.4	?	1 second + pulses
NUCTE-ST	Japan Nihon University	1998	1.2	0.062	0.45	0.34	?	?	?	?	High elongation machine (10).
PEGASUS	USA Madison	1996	1.1 - 1.2	0.2 - 0.45	0.18	0.1 - 0.3		2			Extremely low aspect ratio tokamak. Double null divertor. EBW heating.
Proto-Sphera	Italy Frascati	Soon	?	?	?	?	?	?	?	?	Uses START vacuum vessel.
QUEST (Q-shu University Experiment with steady-state Spherical Tokamak)	Japan, Kasuga City	Soon 2008?	1.7	0.68	0.25	0.02	?	?	?	?	New spherical tokamak replacing TRIAM-1M. Mission to study issues related to steady-state operation within the All-Japan ST Research Program. In particular, to develop a fully non-inductive current drive scheme that is effective in ST plasmas with high beta and high dielectric constant; to perform integrated studies of recycling and advanced PWI control in steady state, by active control of wall temperature and divertor pumping, and compatibility with high plasma performance; to develop a divertor in ST magnetic configuration which can handle power and particle fluxes in steady state.
Rotamak	Australia Lucas Heights	1987 - 1997	1.1	0.07	0.02	0.003	?	?	?	?	Rotamak with central rod.
Rotamak	Australia Flinders	1998 - 2002	1.6	0.10	0.016	0.012	?	?	?	?	Rotamak with central rod.
SPHEX	UK Manchester	?	1.05	0.23	0.045	0.2					Spheromak, fitted with TF rod in 1991.
START	UK Culham	1991-1998	1.25	0.3	0.5	0.31	-	-	1	-	First 'hot' ST, achieved world record betaT =40%. To ENEA at Frascati, June 2004 to become Proto-Sphera.
STPC-EX	Turkey Ankara	1986	1.5	0.084	0.12	0.0065	-	-	-	-
SUNIST Sino UNIted Spherical Tokamak	China Beijing	2003	1.3	0.3	0.15	0.05	0.1	?	?	?	Double null divertor / limiter. 0.2MW of EBW heating. ECRH heating system mainly used for pre-ionisation. Currently installing a 0.5 to 1MHz, 100kW, power supply and antenna for Alfven Wave heating and current drive.
TS-3	Japan Tokyo	1986	1.4	0.2	0.2	0.3	-	-	-	-	Limiter machine
TS-4	Japan Tokyo	2000	1.2	0.55	0.5	0.08	-	-	-	-	Limiter machine
TST-M	Japan Tokyo	?	?	?	?	?	-	-	-	-
TST-2 Tokyo Spherical Tokamak	Japan Tokyo	1999	1.5	0.38	0.4	0.2	0.2 EBW	-	-	-	Major upgrade of TST-M. Double null divertor / limiter. 0.2 sec pulses. Studying plasma turbulence. Upgrades to heating and current drive systems planned soon.