List of fusion experiments

Experiments directed toward developing fusion power are invariably done with dedicated machines which can be classified according to the principles they use to confine the plasma fuel and keep it hot.

Target chamber of the Shiva laser, used for inertial confinement fusion experiments from 1978 until decommissioned in 1981.

Plasma chamber of TFTR, used for magnetic confinement fusion experiments, which produced 11 MW of fusion power in 1994.

The major division is between magnetic confinement and inertial confinement. In magnetic confinement, the tendency of the hot plasma to expand is counteracted by the Lorentz force between currents in the plasma and magnetic fields produced by external coils. The particle densities tend to be in the range of 10¹⁸ to 10²² m⁻³ and the linear dimensions in the range of 0.1 to 10 m. The particle and energy confinement times may range from under a millisecond to over a second, but the configuration itself is often maintained through input of particles, energy, and current for times that are hundreds or thousands of times longer. Some concepts are capable of maintaining a plasma indefinitely.

In contrast, with inertial confinement, there is nothing to counteract the expansion of the plasma. The confinement time is simply the time it takes the plasma pressure to overcome the inertia of the particles, hence the name. The densities tend to be in the range of 10³¹ to 10³³ m⁻³ and the plasma radius in the range of 1 to 100 micrometers. These conditions are obtained by irradiating a millimeter-sized solid pellet with a nanosecond laser or ion pulse. The outer layer of the pellet is ablated, providing a reaction force that compresses the central 10% of the fuel by a factor of 10 or 20 to 10³ or 10⁴ times solid density. These microplasmas disperse in a time measured in nanoseconds. For a fusion power reactor, a repetition rate of several per second will be needed.

Magnetic confinement

Within the field of magnetic confinement experiments, there is a basic division between toroidal and open magnetic field topologies. Generally speaking, it is easier to contain a plasma in the direction perpendicular to the field than parallel to it. Parallel confinement can be solved either by bending the field lines back on themselves into circles or, more commonly, toroidal surfaces, or by constricting the bundle of field lines at both ends, which causes some of the particles to be reflected by the mirror effect. The toroidal geometries can be further subdivided according to whether the machine itself has a toroidal geometry, i.e., a solid core through the center of the plasma. The alternative is to dispense with a solid core and rely on currents in the plasma to produce the toroidal field.

Mirror machines have advantages in a simpler geometry and a better potential for direct conversion of particle energy to electricity. They generally require higher magnetic fields than toroidal machines, but the biggest problem has turned out to be confinement. For good confinement there must be more particles moving perpendicular to the field than there are moving parallel to the field. Such a non-Maxwellian velocity distribution is, however, very difficult to maintain and energetically costly.

The mirrors' advantage of simple machine geometry is maintained in machines which produce compact toroids, but there are potential disadvantages for stability in not having a central conductor and there is generally less possibility to control (and thereby optimize) the magnetic geometry. Compact toroid concepts are generally less well developed than those of toroidal machines. While this does not necessarily mean that they cannot work better than mainstream concepts, the uncertainty involved is much greater.

Somewhat in a class by itself is the Z-pinch, which has circular field lines. This was one of the first concepts tried, but it did not prove very successful. Furthermore, there was never a convincing concept for turning the pulsed machine requiring electrodes into a practical reactor.

The dense plasma focus is a controversial and "non-mainstream" device that relies on currents in the plasma to produce a toroid. It is a pulsed device that depends on a plasma that is not in equilibrium and has the potential for direct conversion of particle energy to electricity. Experiments are ongoing to test relatively new theories to determine if the device has a future.

Toroidal machine

Toroidal machines can be axially symmetric, like the tokamak and the reversed field pinch (RFP), or asymmetric, like the stellarator. The additional degree of freedom gained by giving up toroidal symmetry might ultimately be usable to produce better confinement, but the cost is complexity in the engineering, the theory, and the experimental diagnostics. Stellarators typically have a periodicity, e.g. a fivefold rotational symmetry. The RFP, despite some theoretical advantages such as a low magnetic field at the coils, has not proven very successful.

Tokamak

Device Name	Status	Construction	Operation	Location	Organisation	Major/Minor Radius	B-field	Plasma current	Purpose	Image
T-1	Shut down	?	1957-1959	Moscow	Kurchatov Institute	0.625 m/0.13 m	1 T	0.04 MA	First tokamak
T-3	Shut down	?	1962-?	Moscow	Kurchatov Institute	1 m/0.12 m	2.5 T	0.06 MA
ST (Symmetric Tokamak)	Shut down	Model C	1970-1974	Princeton	Princeton Plasma Physics Laboratory	1.09 m/0.13 m	5.0 T	0.13 MA	First American tokamak, converted from Model C stellarator
ORMAK (Oak Ridge tokaMAK)	Shut down		1971-1976	Oak Ridge	Oak Ridge National Laboratory	0.8 m/0.23 m	2.5 T	0.34 MA	First to achieve 20 MK plasma temperature
ATC (Adiabatic Toroidal Compressor)	Shut down	1971-1972	1972-1976	Princeton	Princeton Plasma Physics Laboratory	0.88 m/0.11 m	2 T	0.05 MA	Demonstrate compressional plasma heating
TFR (Tokamak de Fontenay-aux-Roses)	Shut down		1973-1984	Fontenay-aux-Roses	CEA	1 m/0.2 m	6 T	0.49
T-10 (Tokamak-10)	Shut down		1975-?	Moscow	Kurchatov Institute	1.50 m/0.36 m	4 T	0.6 MA	Largest tokamak of its time
PLT (Princeton Large Torus)	Shut down		1975-1986	Princeton	Princeton Plasma Physics Laboratory	1.32 m/0.4 m	4 T	0.7 MA	First to achieve 1 MA plasma current
ISX-B	Shut down	?	1978-?	Oak Ridge	Oak Ridge National Laboratory	0.93 m/0.27 m	1.8 T	0.2 MA	Superconducting coils, attempt high-beta operation
ASDEX (Axially Symmetric Divertor Experiment)[1]	Recycled →HL-2A		1980-1990	Garching	Max-Planck-Institut für Plasmaphysik	1.65 m/0.4 m	2.8 T	0.5 MA	Discovery of the H-mode in 1982
TEXTOR (Tokamak Experiment for Technology Oriented Research)[2][3]	Shut down	1976-1980	1981-2013	Jülich	Forschungszentrum Jülich	1.75 m/0.47 m	2.8 T	0.8 MA	Study plasma-wall interactions
TFTR (Tokamak Fusion Test Reactor)[4]	Shut down	1980-1982	1982-1997	Princeton	Princeton Plasma Physics Laboratory	2.4 m/0.8 m	6 T	3 MA	Attempted scientific break-even, reached record fusion power of 10.7 MW and temperature of 510 MK
JET (Joint European Torus)[5]	Operational	1978-1983	1983-	Culham	Culham Centre for Fusion Energy	2.96 m/0.96 m	4 T	7 MA	Record for fusion output power 16.1 MW
Novillo[6][7]	Shut down	NOVA-II	1983-2004	Mexico City	Instituto Nacional de Investigaciones Nucleares	0.23 m/0.06 m	1 T	0.01 MA	Study plasma-wall interactions
JT-60 (Japan Torus-60)[8]	Recycled →JT-60SA		1985-2010	Naka	Japan Atomic Energy Research Institute	3.4 m/1.0 m	4 T	3 MA	High-beta steady-state operation, highest fusion triple product
DIII-D[9]	Operational	1986[10]	1986-	San Diego	General Atomics	1.67 m/0.67 m	2.2 T	3 MA	Tokamak Optimization
STOR-M (Saskatchewan Torus-Modified)[11]	Operational		1987-	Saskatoon	Plasma Physics Laboratory (Saskatchewan)	0.46 m/0.125 m	1 T	0.06 MA	Study plasma heating and anomalous transport
T-15	Recycled →T-15MD	1983-1988	1988-1995	Moscow	Kurchatov Institute	2.43 m/0.7 m	3.6 T	1 MA	First superconducting tokamak.
Tore Supra[12]	Recycled →WEST		1988-2011	Cadarache	Département de Recherches sur la Fusion Contrôlée	2.25 m/0.7 m	4.5 T	2 MA	Large superconducting tokamak with active cooling
ADITYA (tokamak)	Operational		1989-	Gandhinagar	Institute for Plasma Research	0.75 m/0.25 m	1.2 T	0.25 MA
COMPASS (COMPact ASSembly)[13][14]	Operational	1980-	1989-	Prague	Institute of Plasma Physics AS CR	0.56 m/0.23 m	2.1 T	0.32 MA
FTU (Frascati Tokamak Upgrade)	Operational		1990-	Frascati	ENEA	0.935 m/0.35 m	8 T	1.6 MA
START (Small Tight Aspect Ratio Tokamak)[15]	Shut down		1990-1998	Culham	Culham Centre for Fusion Energy	0.3 m/?	0.5 T	0.31 MA	First full-sized Spherical Tokamak
ASDEX Upgrade (Axially Symmetric Divertor Experiment)	Operational		1991-	Garching	Max-Planck-Institut für Plasmaphysik	1.65 m/0.5 m	2.6 T	1.4 MA
Alcator C-Mod (Alto Campo Toro)[16]	Operational (Funded by Fusion Startups)	1986-	1991-2016	Cambridge	Massachusetts Institute of Technology	0.68 m/0.22 m	8 T	2 MA	record plasma pressure 2.05 bar
ISTTOK (Instituto Superior Técnico TOKamak)[17]	Operational		1992-	Lisbon	Instituto de Plasmas e Fusão Nuclear	0.46 m/0.085 m	2.8 T	0.01 MA
TCV (Tokamak à Configuration Variable)[18]	Operational		1992-	Lausanne	École Polytechnique Fédérale de Lausanne	0.88 m/0.25 m	1.43 T	1.2 MA	Confinement studies
HBT-EP (High Beta Tokamak-Extended Pulse)	Operational		1993-	New York City	Columbia University Plasma Physics Laboratory	0.92 m/0.15 m	0.35 T	0.03 MA	High-Beta Tokamak
Pegasus Toroidal Experiment[19]	Operational	?	1996-	Madison	University of Wisconsin–Madison	0.45 m/0.4 m	0.18 T	0.3 MA	Extremely low aspect ratio
NSTX (National Spherical Torus Experiment)[20]	Operational		1999-	Plainsboro Township	Princeton Plasma Physics Laboratory	0.85 m/0.68 m	0.3 T	2 MA	Study the spherical tokamak concept
ET (Electric Tokamak)	Recycled →ETPD	1998	1999-2006	Los Angeles	UCLA	5 m/1 m	0.25 T	0.045 MA	Largest tokamak of its time
CDX-U (Current Drive Experiment-Upgrade)	Recycled →LTX		2000-2005	Princeton	Princeton Plasma Physics Laboratory	0.3 m/? m	0.23 T	0.03 MA	Study Lithium in plasma walls
MAST (Mega-Ampere Spherical Tokamak)[21]	Recycled →MAST-Upgrade	1997-1999	2000-2013	Culham	Culham Centre for Fusion Energy	0.85 m/0.65 m	0.55 T	1.35 MA	Investigate spherical tokamak for fusion
HL-2A	Recycled →HL-2M	2000-2002	2002-2018	Chengdu	Southwestern Institute of Physics	1.65 m/0.4 m	2.7 T	0.43 MA	H-mode physics, ELM mitigation
SST-1 (Steady State Superconducting Tokamak)[22]	Operational	2001-	2005-	Gandhinagar	Institute for Plasma Research	1.1 m/0.2 m	3 T	0.22 MA	Produce a 1000s elongated double null divertor plasma
EAST (Experimental Advanced Superconducting Tokamak)[23]	Operational	2000-2005	2006-	Hefei	Hefei Institutes of Physical Science	1.85 m/0.43 m	3.5 T	0.5 MA	H-Mode plasma for over 100 s at 50 MK
J-TEXT (Joint TEXT)	Operational	TEXT (Texas EXperimental Tokamak)	2007-	Wuhan	Huazhong University of Science and Technology	1.05 m/0.26 m	2.0 T	0.2 MA	Develop plasma control
KSTAR (Korea Superconducting Tokamak Advanced Research)[24]	Operational	1998-2007	2008-	Daejeon	National Fusion Research Institute	1.8 m/0.5 m	3.5 T	2 MA	Tokamak with fully superconducting magnets
LTX (Lithium Tokamak Experiment)	Operational	2005-2008	2008-	Princeton	Princeton Plasma Physics Laboratory	0.4 m/? m	0.4 T	0.4 MA	Study Lithium in plasma walls
QUEST (Q-shu University Experiment with Steady-State Spherical Tokamak)[25]	Operational		2008-	Kasuga	Kyushu University	0.68 m/0.4 m	0.25 T	0.02 MA	Study steady state operation of a Spherical Tokamak
Kazakhstan Tokamak for Material testing (KTM)	Operational	2000-2010	2010-	Kurchatov	National Nuclear Center of the Republic of Kazakhstan	0.86 m/0.43 m	1 T	0.75 MA	Testing of wall and divertor
ST25-HTS[26]	Operational	2012-2015	2015-	Culham	Tokamak Energy Ltd	0.25 m/0.125 m	0.1 T	0.02 MA	Steady state plasma
WEST (Tungsten Environment in Steady-state Tokamak)	Operational	2013-2016	2016-	Cadarache	Département de Recherches sur la Fusion Contrôlée	2.5 m/0.5 m	3.7 T	1 MA	Superconducting tokamak with active cooling
ST40[27]	Operational	2017-2018	2018-	Didcot	Tokamak Energy Ltd	0.4 m/0.3 m	3 T	2 MA	First high field spherical tokamak
MAST-U (Mega-Ampere Spherical Tokamak Upgrade)[28]	Operational	2013-2019	2019-	Culham	Culham Centre for Fusion Energy	0.85 m/0.65 m	0.92 T	2 MA	Test new exhaust concepts for a spherical tokamak
HL-2M[29]	Operational	2018-2019	2020-	Leshan	Southwestern Institute of Physics	1.78 m/0.65 m	2.2 T	1.2 MA	Elongated plasma with 200M °C
JT-60SA (Japan Torus-60 super, advanced)[30]	Under construction	2013-2020?	2020?	Naka	Japan Atomic Energy Research Institute	2.96 m/1.18 m	2.25 T	5.5 MA	Optimise plasma configurations for ITER and DEMO with full non-inductive steady-state operation
ITER[31]	Under construction	2013-	2025?	Cadarache	ITER Council	6.2 m/2.0 m	5.3 T	15 MA ?	Demonstrate feasibility of fusion on a power-plant scale with 500 MW fusion power
DTT (Divertor Tokamak Test facility)[32][33]	Planned	2022-2025?	2025?	Frascati	ENEA	2.14 m/0.70 m	6 T ?	5.5 MA ?	Superconducting tokamak to study power exhaust
SPARC (Soonest/Smallest Private-Funded Affordable, Robust, Compact reactor)[34]	Planned	?	2025?		MIT Plasma Science and Fusion Center	1.65 m/0.5 m	12 T	7.5 MA	Compact, high-field, fusion reactor with ReBCO coils and 100 MW planned fusion power
IGNITOR[35]	Planned[36]	?	>2024	Troitzk	ENEA	1.32 m/0.47 m	13 T	11 MA ?	Compact fustion reactor with self-sustained plasma and 100 MW of planned fusion power
CFETR (China Fusion Engineering Test Reactor)[37]	Planned	2020?	2030?		Institute of Plasma Physics, Chinese Academy of Sciences	5.7 m ?	5 T ?	10 MA ?	Bridge gaps between ITER and DEMO, planned fusion power 1000 MW
STEP (Spherical Tokamak for Energy Production)	Planned	?	2040?	Culham	Culham Centre for Fusion Energy	3 m / 2 m ?	?	?	Spherical tokamak with hundreds of MW planned electrical output
K-DEMO (Korean fusion demonstration tokamak reactor)[38]	Planned	2037?			National Fusion Research Institute	6.8 m/2.1 m	7 T	12 MA ?	Prototype for the development of commercial fusion reactors with around 2200 MW of fusion power
DEMO (DEMOnstration Power Station)	Planned	2031?	2044?	?		9 m/3 m ?	6 T ?	20 MA ?	Prototype for a commercial fusion reactor

Stellarator

Device Name	Status	Construction	Operation	Type	Location	Organisation	Major/Minor Radius	B-field	Purpose	Image
Model A	Shut down	1952-1953	1953-?	Figure-8	Princeton	Princeton Plasma Physics Laboratory	0.3 m/0.02 m	0.1 T	First stellarator
Model B	Shut down	1953-1954	1954-1959	Figure-8	Princeton	Princeton Plasma Physics Laboratory	0.3 m/0.02 m	5 T	Development of plasma diagnostics
Model B-1	Shut down		?-1959	Figure-8	Princeton	Princeton Plasma Physics Laboratory	0.25 m/0.02 m	5 T	Yielded 1 MK plasma temperatures
Model B-2	Shut down		1957	Figure-8	Princeton	Princeton Plasma Physics Laboratory	0.3 m/0.02 m	5 T	Electron temperatures up to 10 MK
Model B-3	Shut down	1957	1958-	Figure-8	Princeton	Princeton Plasma Physics Laboratory	0.4 m/0.02 m	4 T	Last figure-8 device, confinement studies of ohmically heated plasma
Model B-64	Shut down	1955	1955	Square	Princeton	Princeton Plasma Physics Laboratory	? m/0.05 m	1.8 T
Model B-65	Shut down	1957	1957	Racetrack	Princeton	Princeton Plasma Physics Laboratory
Model B-66	Shut down	1958	1958-?	Racetrack	Princeton	Princeton Plasma Physics Laboratory
Wendelstein 1-A	Shut down		1960	Racetrack	Garching	Max-Planck-Institut für Plasmaphysik	0.35 m/0.02 m	2 T	ℓ=3
Wendelstein 1-B	Shut down		1960	Racetrack	Garching	Max-Planck-Institut für Plasmaphysik	0.35 m/0.02 m	2 T	ℓ=2
Model C	Recycled →ST	1957-1962	1962-1969	Racetrack	Princeton	Princeton Plasma Physics Laboratory	1.9 m/0.07 m	3.5 T	Found large plasma losses by Bohm diffusion
L-1	Shut down	1963	1963-1971		Lebedev	Lebedev Physical Institute	0.6 m/0.05 m	1 T
SIRIUS	Shut down		1964-?		Kharkov
TOR-1	Shut down	1967	1967-1973		Lebedev	Lebedev Physical Institute	0.6 m/0.05 m	1 T
TOR-2	Shut down	?	1967-1973		Lebedev	Lebedev Physical Institute	0.63 m/0.036 m	2.5 T
Wendelstein 2-A	Shut down	1965-1968	1968-1974	Heliotron	Garching	Max-Planck-Institut für Plasmaphysik	0.5 m/0.05 m	0.6 T	Good plasma confinement “Munich mystery”
Wendelstein 2-B	Shut down	?-1970	1971-?	Heliotron	Garching	Max-Planck-Institut für Plasmaphysik	0.5 m/0.055 m	1.25 T	Demonstrated similar performance than tokamaks
L-2	Shut down	?	1975-?		Lebedev	Lebedev Physical Institute	1 m/0.11 m	2.0 T
WEGA	Recycled →HIDRA	1972-1975	1975-2013	Classical stellarator	Greifswald	Max-Planck-Institut für Plasmaphysik	0.72 m/0.15 m	1.4 T	Test lower hybrid heating
Wendelstein 7-A	Shut down	?	1975-1985	Classical stellarator	Garching	Max-Planck-Institut für Plasmaphysik	2 m/0.1 m	3.5 T	First "pure" stellarator without plasma current
Heliotron-E	Shut down	?	1980-?	Heliotron			2.2 m/0.2 m	1.9 T
Heliotron-DR	Shut down	?	1981-?	Heliotron			0.9 m/0.07 m	0.6 T
Uragan-3 (M)[39]	Operational	?	1982-?[40]	Torsatron	Kharkiv	National Science Center, Kharkiv Institute of Physics and Technology (NSC KIPT)	1.0 m/0.12 m	1.3 T	?
Auburn Torsatron (AT)	Shut down	?	1984-1990	Torsatron	Auburn	Auburn University	0.58 m/0.14 m	0.2 T
Wendelstein 7-AS	Shut down	1982-1988	1988-2002	Modular, advanced stellarator	Garching	Max-Planck-Institut für Plasmaphysik	2 m/0.13 m	2.6 T	First H-mode in a stellarator in 1992
Advanced Toroidal Facility (ATF)	Shut down	1984-1988[41]	1988-?	Torsatron	Oak Ridge	Oak Ridge National Laboratory	2.1 m/0.27 m	2.0 T	High-beta operation
Compact Helical System (CHS)	Shut down	?	1989-?	Heliotron	Toki	National Institute for Fusion Science	1 m/0.2 m	1.5 T
Compact Auburn Torsatron (CAT)	Shut down	?-1990	1990-2000	Torsatron	Auburn	Auburn University	0.53 m/0.11 m	0.1 T	Study magnetic flux surfaces
H-1NF[42]	Operational		1992-	Heliac	Canberra	Research School of Physical Sciences and Engineering, Australian National University	1.0 m/0.19 m	0.5 T
TJ-K[43]	Operational	TJ-IU	1994-	Torsatron	Kiel, Stuttgart	University of Stuttgart	0.60 m/0.10 m	0.5 T	Teaching
TJ-II[44]	Operational	1991-	1997-	flexible Heliac	Madrid	National Fusion Laboratory, Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas	1.5 m/0.28 m	1.2 T	Study plasma in flexible configuration
LHD (Large Helical Device)[45]	Operational	1990-1998	1998-	Heliotron	Toki	National Institute for Fusion Science	3.5 m/0.6 m	3 T	Determine feasibility of a stellarator fusion reactor
HSX (Helically Symmetric Experiment)	Operational		1999-	Modular, quasi-helically symmetric	Madison	University of Wisconsin–Madison	1.2 m/0.15 m	1 T	investigate plasma transport
Heliotron J (Heliotron J)[46]	Operational		2000-	Heliotron	Kyoto	Institute of Advanced Energy	1.2 m/0.1 m	1.5 T	Study helical-axis heliotron configuration
Columbia Non-neutral Torus (CNT)	Operational	?	2004-	Circular interlocked coils	New York City	Columbia University	0.3 m/0.1 m	0.2 T	Study of non-neutral plasmas
Uragan-2(M)[47]	Operational	1988-2006	2006-[48]	Heliotron, Torsatron	Kharkiv	National Science Center, Kharkiv Institute of Physics and Technology (NSC KIPT)	1.7 m/0.24 m	2.4 T	?
Quasi-poloidal stellarator (QPS)[49][50]	Cancelled	2001-2007	-	Modular	Oak Ridge	Oak Ridge National Laboratory	0.9 m/0.33 m	1.0 T	Stellarator research
NCSX (National Compact Stellarator Experiment)	Cancelled	2004-2008	-	Helias	Princeton	Princeton Plasma Physics Laboratory	1.4 m/0.32 m	1.7 T	High-β stability
Compact Toroidal Hybrid (CTH)	Operational	?	2007?-	Torsatron	Auburn	Auburn University	0.75 m/0.2 m	0.7 T	Hybrid stellarator/tokamak
HIDRA (Hybrid Illinois Device for Research and Applications)[51]	Operational	2013-2014 (WEGA)	2014-	?	Urbana, IL	University of Illinois	0.72 m/0.19 m	0.5 T	Stellarator and Tokamak in one device
UST_2[52]	Operational	2013	2014-	modular three period quasi-isodynamic	Madrid	Charles III University of Madrid	0.29 m/0.04 m	0.089 T	3D printed stellarator
Wendelstein 7-X[53]	Operational	1996-2015	2015-	Helias	Greifswald	Max-Planck-Institut für Plasmaphysik	5.5 m/0.53 m	3 T	Steady-state plasma in fully optimized stellarator
SCR-1 (Stellarator of Costa Rica)	Operational	2011-2015	2016-	Modular	Cartago	Instituto Tecnológico de Costa Rica	0.14 m/0.042 m	0.044 T

Reversed field pinch (RFP)

• ETA-BETA II in Padua, Italy (1979-1989)
• RFX (Reversed-Field eXperiment), Consorzio RFX, Padova, Italy[54]
• MST (Madison Symmetric Torus), University of Wisconsin–Madison, United States[55]
• T2R, Royal Institute of Technology, Stockholm, Sweden
• TPE-RX, AIST, Tsukuba, Japan
• KTX (Keda Torus eXperiment) in China (since 2015)[56]

Magnetic mirror

• Baseball I/Baseball II Lawrence Livermore National Laboratory, Livermore CA.
• TMX, TMX-U Lawrence Livermore National Laboratory, Livermore CA.
• MFTF Lawrence Livermore National Laboratory, Livermore CA.
• Gas Dynamic Trap at Budker Institute of Nuclear Physics, Akademgorodok, Russia.

Spheromak

• Sustained Spheromak Physics Experiment

Field-Reversed Configuration (FRC)

• C-2 Tri Alpha Energy
• C-2U Tri Alpha Energy
• C-2W TAE Technologies
• LSX University of Washington
• IPA University of Washington
• HF University of Washington
• IPA- HF University of Washington

Open field lines

Plasma pinch

• Trisops - 2 facing theta-pinch guns

Levitated Dipole

• Levitated Dipole Experiment (LDX), MIT/Columbia University, United States[57]

Inertial confinement

Main article: Inertial confinement fusion

Laser-driven

Current or under construction experimental facilities

Solid state lasers

• National Ignition Facility (NIF) at LLNL in California, US[58]
• Laser Mégajoule of the Commissariat à l'Énergie Atomique in Bordeaux, France (under construction)[59]
• OMEGA EL Laser at the Laboratory for Laser Energetics, Rochester, US
• Gekko XII at the Institute for Laser Engineering in Osaka, Japan
• ISKRA-4 and ISKRA-5 Lasers at the Russian Federal Nuclear Center VNIIEF[60]
• Pharos laser, 2 beam 1 kJ/pulse (IR) Nd:Glass laser at the Naval Research Laboratories
• Vulcan laser at the central Laser Facility, Rutherford Appleton Laboratory, 2.6 kJ/pulse (IR) Nd:glass laser
• Trident laser, at LANL; 3 beams total; 2 x 400 J beams, 100 ps – 1 us; 1 beam ~100 J, 600 fs – 2 ns.

Gas lasers

• NIKE laser at the Naval Research Laboratories, Krypton Fluoride gas laser
• PALS, formerly the "Asterix IV", at the Academy of Sciences of the Czech Republic,[61] 1 kJ max. output iodine laser at 1.315 micrometre fundamental wavelength

Dismantled experimental facilities

Solid-state lasers

• 4 pi laser built during the mid 1960s at Lawrence Livermore National Laboratory
• Long path laser built at LLNL in 1972
• The two beam Janus laser built at LLNL in 1975
• The two beam Cyclops laser built at LLNL in 1975
• The two beam Argus laser built at LLNL in 1976
• The 20 beam Shiva laser built at LLNL in 1977
• 24 beam OMEGA laser completed in 1980 at the University of Rochester's Laboratory for Laser Energetics
• The 10 beam Nova laser (dismantled) at LLNL. (First shot taken, December 1984 – final shot taken and dismantled in 1999)

Gas lasers

• "Single Beam System" or simply "67" after the building number it was housed in, a 1 kJ carbon dioxide laser at Los Alamos National Laboratory
• Gemini laser, 2 beams, 2.5 kJ carbon dioxide laser at LANL
• Helios laser, 8 beam, ~10 kJ carbon dioxide laser at LANL — Media at Wikimedia Commons
• Antares laser at LANL. (40 kJ CO₂ laser, largest ever built, production of hot electrons in target plasma due to long wavelength of laser resulted in poor laser/plasma energy coupling)
• Aurora laser 96 beam 1.3 kJ total krypton fluoride (KrF) laser at LANL
• Sprite laser few joules/pulse laser at the Central Laser Facility, Rutherford Appleton Laboratory

Z-Pinch

Main article: Z-Pinch

• Z Pulsed Power Facility
• ZEBRA device at the University of Nevada's Nevada Terawatt Facility[62]
• Saturn accelerator at Sandia National Laboratory[63]
• MAGPIE at Imperial College London
• COBRA at Cornell University
• PULSOTRON[64]

Inertial electrostatic confinement

Main article: Inertial electrostatic confinement

• Fusor
• Polywell

Magnetized target fusion

Main article: Magnetized target fusion

• FRX-L
• FRCHX
• General Fusion - under development
• LINUS project

References

1. ASDEX at the Max Planck Institute for Plasma Physics
2. "Forschungszentrum Jülich - Plasmaphysik (IEK-4)". www.fz-juelich.de (in German).
3. Progress in Fusion Research - 30 Years of TEXTOR
4. "Tokamak Fusion Test Reactor". 2011-04-26. Archived from the original on 2011-04-26.
5. "EFDA-JET, the world's largest nuclear fusion research experiment". 2006-04-30. Archived from the original on 2006-04-30.
6. ":::. Instituto Nacional de Investigaciones Nucleares | Fusión nuclear ". 2009-11-25. Archived from the original on 2009-11-25.
7. "All-the-Worlds-Tokamaks". www.tokamak.info.
8. Yoshikawa, M. (2006-10-02). "JT-60 Project". Fusion Technology 1978. 2: 1079. Bibcode:1979fute.conf.1079Y. Archived from the original on 2006-10-02.
9. "diii-d:home [MFE: DIII-D and Theory]". fusion.gat.com. Retrieved 2018-09-04.
10. "DIII-D National Fusion Facility (DIII-D) | U.S. DOE Office of Science (SC)". science.energy.gov. Retrieved 2018-09-04.
11. "U of S". 2011-07-06. Archived from the original on 2011-07-06.
12. "Tore Supra". www-fusion-magnetique.cea.fr. Retrieved 2018-09-04.
13. "Wayback Machine". 2014-05-12. Archived from the original on 2014-05-12.
14. "COMPASS - General information". 2013-10-25. Archived from the original on 2013-10-25.
15. "Wayback Machine". 2006-04-24. Archived from the original on 2006-04-24.
16. "MIT Plasma Science & Fusion Center: research>alcator>". 2015-07-09. Archived from the original on 2015-07-09.
17. "Centro de Fusão Nuclear". www.cfn.ist.utl.pt. Archived from the original on 2010-03-07. Retrieved 2012-02-13.
18. "EPFL". crppwww.epfl.ch.
19. "Pegasus Toroidal Experiment". pegasus.ep.wisc.edu.
20. "NSTX-U". nstx-u.pppl.gov. Retrieved 2018-09-04.
21. "MAST - the Spherical Tokamak at UKAEA Culham". 2006-04-21. Archived from the original on 2006-04-21.
22. "The SST-1 Tokamak Page". 2014-06-20. Archived from the original on 2014-06-20.
23. "EAST (HT-7U Super conducting Tokamak)----Hefei Institutes of Physical Science, The Chinese Academy of Sciences". english.hf.cas.cn.
24. "Wayback Machine". 2008-05-30. Archived from the original on 2008-05-30.
25. "Wayback Machine". 2013-11-10. Archived from the original on 2013-11-10.
26. "ST25 » Tokamak Energy".
27. "ST40 » Tokamak Energy".
28. "Status and Plans on MAST-U". 2016-12-13.
29. "China completes new tokamak".
30. "The JT-60SA project".
31. "ITER - the way to new energy". ITER.
32. "The DTT Project".
33. "The new Divertor Tokamak Test facility" (PDF).
34. "SPARC at MIT Plasma Science and Fusion Center".
35. "Ignited plasma in Tokamaks - The IGNITOR project". www.frascati.enea.it.
36. The Russian-Italian IGNITOR Tokamak Project: Design and status of implementation (2017)
37. Gao, X. (2013-12-17). "Update on CFETR Concept Design" (PDF). www-naweb.iaea.org.
38. Kim, K.; Im, K.; Kim, H. C.; Oh, S.; Park, J. S.; Kwon, S.; Lee, Y. S.; Yeom, J. H.; Lee, C. (2015). "Design concept of K-DEMO for near-term implementation". Nuclear Fusion. 55 (5): 053027. Bibcode:2015NucFu..55e3027K. doi:10.1088/0029-5515/55/5/053027. ISSN 0029-5515.
39. "History | ННЦ ХФТИ". www.kipt.kharkov.ua.
40. https://ipp.kipt.kharkov.ua/u3m/u3m_eng.html
41. https://www.ornl.gov/content/ornl-review-v17n3
42. Department, Head of; [e-mail]. "Plasma Research Laboratory - PRL - ANU". prl.anu.edu.au.
43. "TJ-K - FusionWiki". fusionwiki.ciemat.es.
44. CIEMAT. "Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas". www.ciemat.es (in Spanish).
45. "Large Helical Device Project". www.lhd.nifs.ac.jp. Archived from the original on 2010-04-12. Retrieved 2006-04-20.
46. "Heliotron J Project". http://www.iae.kyoto-u.ac.jp/en/joint/heliotron-j.html. External link in |website= (help)
47. "History | ННЦ ХФТИ". www.kipt.kharkov.ua.
48. https://ipp.kipt.kharkov.ua/u2m/u2m_en.html
49. "QPS Home Page".
50. http://qps.fed.ornl.gov/pvr/pdf/qpsentire.pdf
51. "HIDRA – Hybrid Illinois Device for Research and Applications | CPMI - Illinois". cpmi.illinois.edu.
52. UST_2 at Vying Fusion Energy
53. "Wendelstein 7-X". www.ipp.mpg.de/w7x.
54. "CONSORZIO RFX - Ricerca Formazione Innovazione". www.igi.cnr.it. Archived from the original on 2009-09-01. Retrieved 2018-04-16.
55. Hartog, Peter Den. "MST - UW Plasma Physics". plasma.physics.wisc.edu.
56. Liu, Wandong; et, al. (2017). "Overview of Keda Torus eXperiment initial results". Nuclear Fusion. 57 (11): 116038. doi:10.1088/1741-4326/aa7f21. ISSN 0029-5515.
57. "Levitated Dipole Experiment". 2004-08-23. Archived from the original on 2004-08-23.
58. "Lasers, Photonics, and Fusion Science: Science and Technology on a Mission". www.llnl.gov.
59. "CEA - Laser Mégajoule". www-lmj.cea.fr.
60. "RFNC-VNIIEF - Science - Laser physics". 2005-04-06. Archived from the original on 2005-04-06.
61. "PALS, Laser". archive.is. 2001-06-27. Archived from the original on 2001-06-27.
62. "University of Nevada, Reno. Nevada Terawatt Facility". archive.is. 2000-09-19. Archived from the original on 2000-09-19.
63. "Sandia National Laboratories: National Security Programs". www.sandia.gov.
64. "PULSOTRON". pulsotron.org. Archived from the original on 2019-04-01. Retrieved 2020-03-09.