Wikipedia

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

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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

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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[1]

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Device name Status Construction Operation Location Organisation Major/minor radius B-field Plasma current Purpose Image
T-1 (Tokamak-1)[2] Shut down 1957 1958–1959   Moscow Kurchatov Institute 0.625 m/0.13 m 1 T 0.04 MA First tokamak  
T-2 (Tokamak-2)[2] Recycled →FT-1 1959 1960–1970   Moscow Kurchatov Institute 0.62 m/0.22 m 1 T 0.04 MA
T-3 (Tokamak-3)[2] Shut down 1960 1962–?   Moscow Kurchatov Institute 1 m/0.12 m 3.5 T 0.15 MA Overcame Bohm diffusion by a factor of 10, temperature 10 MK, confinement time 10 ms
T-5 (Tokamak-5)[2] Shut down ? 1962–1970   Moscow Kurchatov Institute 0.625 m/0.15 m 1.2 T 0.06 MA Investigation of plasma equilibrium in vertical and horizontal direction
TM-1 Shut down ? ?   Moscow Kurchatov Institute
TM-2 Shut down ? 1965   Moscow Kurchatov Institute
TM-3 Shut down ? 1970   Moscow Kurchatov Institute
FT-1[2] Recycled →CASTOR T-2 1972–2002   Saint Petersburg Ioffe Institute 0.62 m/0.22 m 1.2 T 0.05 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
T-6 (Tokamak-6) Shut down ? 1970–1974   Moscow Kurchatov Institute 0.7 m/0.25 m 1.5 T 0.22 MA
TUMAN-2, 2A Shut down ? 1971–1985   Saint Petersburg Ioffe Institute 0.4 m/0.08 m 1.5 T 0.012 MA
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  
Doublet II Shut down 1972–1974   San Diego General Atomics 0.63 m/0.08 m 0.95 T 0.21 MA [1]
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  
T-9 (Tokamak-9) Shut down ? 1972–1977   Moscow Kurchatov Institute 0.36 m/0.07 m 1 T
TO-1 Shut down ? 1972–1978   Moscow Kurchatov Institute 0.6 m/0.13 m 1.5 T 0.07 MA
Alcator A (Alto Campo Toro) Shut down ? 1972–1978   Cambridge Massachusetts Institute of Technology 0.54 m/0.10 m 9.0 T 0.3 MA
JFT-2 (JAERI Fusion Torus 2) Shut down ? 1972–1982   Naka Japan Atomic Energy Research Institute 0.9 m/0.25 m 1.8 T 0.25 MA
Turbulent Tokamak Frascati (TTF, torello) Shut down 1973   Frascati ENEA 0.3 m/0.04 m 1 T 0.005 MA Study of turbulent plasma heating [2]
Pulsator[3] Shut down 1970–1973 1973–1979   Garching Max Planck Institute for Plasma Physics 0.7 m/0.12 m 2.7 T 0.125 MA Discovery of high-density operation with tokamaks [3]
TFR (Tokamak de Fontenay-aux-Roses) Shut down 1973–1984   Fontenay-aux-Roses CEA 0.98 m/0.2 m 6 T 0.49 MA [4]
T-4 (Tokamak-4)[2] Shut down ? 1974–1978   Moscow Kurchatov Institute 0.9 m/0.16 m 5 T 0.3 MA Observed fast thermal quench before major plasma disruptions
Doublet IIA Shut down 1974–1979   San Diego General Atomics 0.66 m/0.15 m 0.76 T 0.35 MA
Petula-B Shut down ? 1974–1986   Grenoble CEA 0.72 m/0.18 m 2.7 T 0.23 MA
T-10 (Tokamak-10)[2] Operational 1975–   Moscow Kurchatov Institute 1.50 m/0.37 m 4 T 0.8 MA Largest tokamak of its time  
T-11 (Tokamak-11) Shut down ? 1975–1984   Moscow Kurchatov Institute 0.7 m/0.25 m 1 T
PLT (Princeton Large Torus) Shut down 1972–1975 1975–1986   Princeton Princeton Plasma Physics Laboratory 1.32 m/0.42 m 4 T 0.7 MA First to achieve 1 MA plasma current  
Divertor Injection Tokamak Experiment (DITE) Shut down 1975–1989   Culham United Kingdom Atomic Energy Authority 1.17 m/0.27 m 2.7 T 0.26 MA
JIPP T-II Shut down ? 1976   Nagoya Nagoya University 0.91 m/0.17 m 3 T 0.16 MA
TNT-A Shut down ? 1976   Tokyo Tokyo University 0.4 m/0.09 m 0.42 T 0.02 MA
T-8 (Tokamak-8)[2] Shut down ? 1976–?   Moscow Kurchatov Institute 0.28 m/0.048 m 0.9 T 0.024 MA First D-shaped tokamak
Microtor[4] Shut down ? 1976–1983?   Los Angeles UCLA 0.3 m/0.1 m 2.5 T 0.12 MA Plasma impurity control and diagnostic development
Macrotor[4] Shut down ? 1970s–80s   Los Angeles UCLA 0.9 m/0.4 m 0.4 T 0.1 MA Understanding plasma rotation driven by radial current
TUMAN-3[2] Operational ? 1977–
(1990–, 3M)		   Saint Petersburg Ioffe Institute 0.55 m/0.23 m 3 T 0.18 MA Study adiabatic compression, RF and NB heating, H-mode and parametric instability
Thor[5] Shut down ?   Milano University of Milano 0.52 m/0.195 m 1 T 0.055 MA [5]
FT (Frascati Tokamak) Shut down 1978   Frascati ENEA 0.83 m/0.20 m 10 T 0.8 MA
PDX (Poloidal Divertor Experiment) Shut down ? 1978–1983   Princeton Princeton Plasma Physics Laboratory 1.4 m/0.4 m 2.4 T 0.5 MA
ISX-B Shut down ? 1978–1984   Oak Ridge Oak Ridge National Laboratory 0.93 m/0.27 m 1.8 T 0.2 MA Attempt high-beta operation
Doublet III Shut down 1978–1985   San Diego General Atomics 1.45 m/0.45 m 2.6 T 0.61 MA [6]
T-12 (Tokamak-12) Shut down ? 1978–1985   Moscow Kurchatov Institute 0.36 m/0.08 m 1 T 0.03 MA
Alcator C (Alto Campo Toro) Shut down ? 1978–1986   Cambridge Massachusetts Institute of Technology 0.64 m/0.16 m 13 T 0.8 MA
T-7 (Tokamak-7)[2] Recycled →HT-7[6] ? 1979–1985   Moscow Kurchatov Institute 1.2 m/0.31 m 3 T 0.3 MA First tokamak with superconducting toroidal field coils
ASDEX (Axially Symmetric Divertor Experiment)[7] Recycled →HL-2A 1973–1980 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 [7]
FT-2[2] Operational ? 1980–   Saint Petersburg Ioffe Institute 0.55 m/0.08 m 3 T 0.05 MA H-mode physics, LH heating
TEXTOR (Tokamak Experiment for Technology Oriented Research)[8][9] 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)[10] Shut down 1980–1982 1982–1997   Princeton Princeton Plasma Physics Laboratory 2.4 m/0.8 m 5.9 T 3 MA Attempted scientific break-even, reached record fusion power of 10.7 MW and temperature of 510 MK  
Tokamak de Varennes (TdeV) Shut down ? 1983–1997   Montreal National Research Council Canada 0.83 m/0.27 m 1.5 T 0.3 MA [11] [8]
JFT-2M (JAERI Fusion Torus 2M) Shut down ? 1983–2004   Naka Japan Atomic Energy Research Institute 1.3 m/0.35 m 2.2 T 0.5 MA [9]
JET (Joint European Torus)[12] Shut down 1978–1983 1983–2023   Culham United Kingdom Atomic Energy Authority 2.96 m/0.96 m 4 T 7 MA Records for fusion output power 16.1 MW (1997), fusion energy 69 MJ (2023)  
Novillo[13][14] 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)[15] 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
CCT (Continuous Current Tokamak) Shut down ? 1986–199?   Los Angeles UCLA 1.5 m/0.4 m 0.2 T 0.05 MA H-mode studies
DIII-D[16] Operational 1986[17] 1986–   San Diego General Atomics 1.67 m/0.67 m 2.2 T 3 MA Tokamak Optimization  
STOR-M (Saskatchewan Torus-Modified)[18] Operational 1987–   Saskatoon Plasma Physics Laboratory (Saskatchewan) 0.46 m/0.125 m 1 T 0.06 MA Study plasma heating and anomalous transport [10]
T-15[2] Recycled →T-15MD 1983–1988 1988–1995   Moscow Kurchatov Institute 2.43 m/0.78 m 3.6 T 1 MA First superconducting tokamak, pulse duration 1.5 s  
Tore Supra[19] 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)[20][21] Operational 1980– 1989–   Prague Institute of Plasma Physics AS CR 0.56 m/0.23 m 2.1 T 0.32 MA Plasma physics studies for ITER  
FTU (Frascati Tokamak Upgrade) Operational 1990–   Frascati ENEA 0.935 m/0.35 m 8 T 1.6 MA [11]
START (Small Tight Aspect Ratio Tokamak)[22] Recycled →Proto-Sphera 1990–1998   Culham United Kingdom Atomic Energy Authority 0.3 m/? 0.5 T 0.31 MA First full-sized Spherical Tokamak [12]
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)[23] Shut down 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)[24] 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)[25] 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  
HT-7 (Hefei Tokamak-7) Shut down 1991–1994 (T-7) 1995–2013   Hefei Hefei Institutes of Physical Science 1.22 m/0.27 m 2 T 0.2 MA China's first superconducting tokamak
Pegasus Toroidal Experiment[26] 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)[27] Operational 1999–   Plainsboro Township Princeton Plasma Physics Laboratory 0.85 m/0.68 m 0.3 T 2 MA Study the spherical tokamak concept  
Globus-M (UNU Globus-M)[28] Operational 1999–   Saint Petersburg Ioffe Institute 0.36 m/0.24 m 0.4 T 0.3 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  
TCABR (Tokamak Chauffage Alfvén Brésilien) Operational 1980–1999 1999–   Lausanne,
  Sao Paulo 		University of Sao Paulo 0.615 m / 0.18 m 1.1 T 0.10 MA Most important tokamak in the southern hemisphere  
CDX-U (Current Drive Experiment-Upgrade) Recycled →LTX 2000–2005   Princeton Princeton Plasma Physics Laboratory 0.3 m/? 0.23 T 0.03 MA Study Lithium in plasma walls  
MAST (Mega-Ampere Spherical Tokamak)[29] Recycled →MAST-Upgrade 1997–1999 2000–2013   Culham United Kingdom Atomic Energy Authority 0.85 m/0.65 m 0.55 T 1.35 MA Investigate spherical tokamak for fusion  
HL-2A (Huan-Liuqi-2A) Operational 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 [13]
SST-1 (Steady State Superconducting Tokamak)[30] Operational 2001– 2005–   Gandhinagar Institute for Plasma Research 1.1 m/0.2 m 3 T 0.22 MA Produce a 1000 s elongated double null divertor plasma
EAST (Experimental Advanced Superconducting Tokamak)[31] Operational 2000–2005 2006–   Hefei Hefei Institutes of Physical Science 1.85 m/0.43 m 3.5 T 0.5 MA Superheated plasma for over 101 s at 120 M°C and 20 s at 160 M°C[32]  
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 [14]
KSTAR (Korea Superconducting Tokamak Advanced Research)[33] 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, 48 s-long operation at 100 MK[34]  
LTX (Lithium Tokamak Experiment) Operational 2005–2008 2008–   Princeton Princeton Plasma Physics Laboratory 0.4 m/? 0.4 T 0.4 MA Study Lithium in plasma walls  
QUEST (Q-shu University Experiment with Steady-State Spherical Tokamak)[35] 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[36] 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[37] Operational 2017–2018 2018–   Didcot Tokamak Energy Ltd 0.4 m/0.3 m 3 T 2 MA First high field spherical tokamak, reached 100 MK plasma  
MAST-U (Mega-Ampere Spherical Tokamak Upgrade)[38] Operational 2013–2019 2020–   Culham United Kingdom Atomic Energy Authority 0.85 m/0.65 m 0.92 T 2 MA Test new exhaust concepts for a spherical tokamak [15]
HL-2M (Huan-Liuqi-2M)[39] Operational 2018–2019 2020–   Leshan Southwestern Institute of Physics 1.78 m/0.65 m 2.2 T 1.2 MA Elongated plasma with 200 MK  
JT-60SA (Japan Torus-60 super, advanced)[40] Operational 2013–2020 2021–   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  
T-15MD Operational 2010–2020 2021–   Moscow Kurchatov Institute 1.48 m/0.67 m 2 T 2 MA Hybrid fusion/fission reactor  
IGNITOR[41] Cancelled 2022[42] - -   Troitzk ENEA 1.32 m/0.47 m 13 T 11 MA Compact fusion reactor with self-sustained plasma and 100 MW of planned fusion power [16]
HongHuang 70[43] Operational 2022–2024 2024  Shanghai Energy Singularity 0.75 m/? 2.5 T REBCO High-temperature superconducting coils [17]
SPARC[44][45][46][47][48] Under construction 2021– 2025?   Devens, MA Commonwealth Fusion Systems and MIT Plasma Science and Fusion Center 1.85 m/0.57 m 12.2 T 8.7 MA Compact, high-field tokamak with ReBCO coils and 100 MW planned fusion power  
ITER[49] Under construction 2013–2034? 2034?   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)[50][51][52] Planned 2022–2029? 2029?   Frascati ENEA 2.19 m/0.70 m 5.85 T ? 5.5 MA ? Superconducting tokamak to study power exhaust [18]
SST-2 (Steady State Tokamak-2)[53] Planned 2027?   Gujarat Institute for Plasma Research 4.42 m/1.47 m 5.42 T 11.2 MA Full-fledged fusion reactor with tritium breeding and up to 500 MW output
CFETR (China Fusion Engineering Test Reactor)[54] Planned ≥2024 2030?   Institute of Plasma Physics, Chinese Academy of Sciences 7.2 m/2.2 m ? 6.5 T ? 14 MA ? Bridge gaps between ITER and DEMO, planned fusion power 1000 MW [19]
ST-F1 (Spherical Tokamak - Fusion 1)[55] Planned 2027?   Didcot Tokamak Energy Ltd 1.4 m/0.8 m ? 4 T 5 MA Spherical tokamak with Q=3 and hundreds of MW planned electrical output (no longer mentioned by company as of 2024)
STX (ST80-HTS) Planned 2026? 2030?   Culham Tokamak Energy Ltd Spherical tokamak capable of 15min-pulsed operation[56][57] [20]
ST-E1 Planned 2030s?   Culham Tokamak Energy Ltd Spherical tokamak with 200 MW planned net electric output[58] [21]
STEP (Spherical Tokamak for Energy Production) Planned 2032-2040 2040 D-D
Mid 2040s DT Campaign		   West Burton, Nottinghamshire United Kingdom Atomic Energy Authority 3 m/2 m ? ? 16.5 MA ? Spherical tokamak with 100 MW planned electrical output[59] [22]
JA-DEMO Planned 2030? 2050?   ? 8.5 m/2.4 m[60] 5.94 T 12.3 MA Prototype for development of Commercial Fusion Reactors 1.5–2 GW Fusion output.[61] [23]
K-DEMO (Korean fusion demonstration tokamak reactor)[62] 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 2040? 2050? ? 9 m/3 m ? 6 T ? 20 MA ? Prototype for a commercial fusion reactor  

Stellarator

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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, table-top device [24]
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, showed cooling by X-ray radiation from impurities
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 [25]
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 [26]
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 showed that stellarators can overcome Bohm diffusion, "Munich mystery"
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 1957–1961 1961–1969 Racetrack   Princeton Princeton Plasma Physics Laboratory 1.9 m/0.07 m 3.5 T Suffered from large plasma losses by Bohm diffusion through "pump-out"
L-1 Shut down 1963 1963–1971 round   Moscow Lebedev Physical Institute 0.6 m/0.05 m 1 T First Soviet stellarator, overcame Bohm diffusion
SIRIUS Shut down 1964–? Racetrack   Kharkiv Kharkiv Institute of Physics and Technology (KIPT)
TOR-1 Shut down 1967 1967–1973   Moscow Lebedev Physical Institute 0.6 m/0.05 m 1 T
TOR-2 Shut down ? 1967–1973   Moscow Lebedev Physical Institute 0.63 m/0.036 m 2.5 T
Uragan-1 Shut down 1960–1967 1967–? Racetrack   Kharkiv National Science Center, Kharkiv Institute of Physics and Technology (NSC KIPT) 1.1 m/0.1 m 1 T Overcame Bohm-diffusion by a factor of 30
CLASP (Closed Line And Single Particle)[63] Shut down ? 1967–?   Culham United Kingdom Atomic Energy Authority 0.3 m/0.056 m 0.1 T Study confinement of electrons in a high-shear stellarator
TWIST[63] Shut down ? 1967–?   Culham United Kingdom Atomic Energy Authority 0.32 m/0.045 m 0.3 T Study turbulent heating
Proto-CLEO[63] Shut down ? 1968–? single-turn helical winding inside toroidal field conductors   Culham,
  Madison		 United Kingdom Atomic Energy Authority 0.4 m/0.05 m 0.5 T confirmed plasma confinement times of neoclassical theory
TORSO[63] Shut down ? 1972–? Ultimate torsatron   Culham United Kingdom Atomic Energy Authority 0.4 m/0.05 m 2 T
CLEO[63] Shut down ? 1974–?   Culham United Kingdom Atomic Energy Authority 0.9 m/0.125 m 2 T Study of particle transport and beta limits, reached similar performance as tokamaks
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  
Saturn[64] Shut down 1970 1970–? Torsatron   Kharkiv Kharkiv Institute of Physics and Technology 0.36 m/0.08 m 1 T first Torsatron, ℓ=3, m=8 field periods, base for several torsatrons at KIPT
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 as tokamaks  
Vint-20[65] Shut down 1972 1973–? Torsatron   Kharkiv Kharkiv Institute of Physics and Technology 0.315 m/0.0725 m 1.8 T single-pole ℓ=1, m=13 field periods
L-2 Shut down ? 1975–?   Moscow Lebedev Physical Institute 1 m/0.11 m 2.0 T
WEGA (Wendelstein Experiment in Greifswald für die Ausbildung) 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, solved stellarator heating problem
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 [uk])[66] Operational ? 1982–?[67]
M: 1990–		 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 computer-optimized stellarator, first H-mode in a stellarator in 1992  
Advanced Toroidal Facility (ATF) Shut down 1984–1988[68] 1988–1994 Torsatron   Oak Ridge Oak Ridge National Laboratory 2.1 m/0.27 m 2.0 T First large American stellarator after Tokamak stampede, high-beta operation, >1h plasma 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-1 (Heliac-1)[69] Operational 1992– Heliac   Canberra,
 		 Research School of Physical Sciences and Engineering, Australian National University 1.0 m/0.19 m 0.5 T shipped to China in 2017  
TJ-K (Tokamak de la Junta Kiel)[70] Operational TJ-IU (1999) 1994– Torsatron   Kiel, Stuttgart University of Stuttgart 0.60 m/0.10 m 0.5 T One helical and two vertical coil sets; Teaching; moved from Kiel to Stuttgart in 2005
TJ-II (Tokamak de la Junta II)[71] Operational 1991–1996 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)[72] Operational 1990–1998 1998– Heliotron   Toki National Institute for Fusion Science 3.5 m/0.6 m 3 T Demonstrated long-term operation of large superconducting coils  
HSX (Helically Symmetric Experiment)[73] Operational 1999– Modular, quasi-helically symmetric   Madison University of Wisconsin–Madison 1.2 m/0.15 m 1 T Investigate plasma transport in quasi-helically-symmetric field, similar to tokamaks  
Heliotron J[74] Operational 2000– Heliotron   Kyoto Institute of Advanced Energy 1.2 m/0.1 m 1.5 T Study helical-axis heliotron configuration [27]
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 (mostly electron) plasmas
Uragan-2(M)[66] Operational 1988–2006 2006–[75] Heliotron, Torsatron   Kharkiv National Science Center, Kharkiv Institute of Physics and Technology (NSC KIPT) 1.7 m/0.22 m 2.4 T ℓ=2 Torsatron [28]
Quasi-poloidal stellarator (QPS)[76][77] 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)[78] 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, capable of long pulse steady-state operation; study plasma-wall interactions  
UST_2[79] 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[80] Operational 1996–2022 2015– Helias   Greifswald Max-Planck-Institut für Plasmaphysik 5.5 m/0.53 m 3 T Steady-state plasma in large fully optimized stellarator  
SCR-1 (Stellarator of Costa Rica) Operational 2011–2015 2016– Modular   Cartago Costa Rica Institute of Technology 0.14 m/0.042 m 0.044 T  
MUSE[81] Operational 2022–2023 2023– Quasiaxi-symmetrical   Princeton Princeton Plasma Physics Laboratory 0.3 m/0.075 m 0.15 T First stellarator with permanent magnets  
CFQS (Chinese First Quasi-Axisymmetric Stellarator)[82] Under construction 2017– Helias   Chengdu Southwest Jiaotong University, National Institute for Fusion Science in Japan 1 m/0.25 m 1 T m=2 quasi-axisymmetric stellarator, modular  
EFPP (European Fusion Power Plant)[83] Planned 2030 ? 2045 ? Helias   Gauss Fusion 7–9 T ? Fusion power plant with 2–3 GW output

Magnetic mirror

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Toroidal Z-pinch

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  • Perhapsatron (1953, USA)
  • ZETA (Zero Energy Thermonuclear Assembly) (1957, United Kingdom)

Reversed field pinch (RFP)

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Spheromak

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Field-reversed configuration (FRC)

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Other toroidal machines

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  • TMP (Tor s Magnitnym Polem, torus with magnetic field): A porcelain torus with major radius 80 cm, minor radius 13 cm, toroidal field of 1.5 T and plasma current 0.25 MA, predecessor to the first tokamak (1955, USSR)

Open field lines

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Plasma pinch

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Levitated dipole

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Inertial confinement

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Main article: Inertial confinement fusion

Laser-driven

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Device name Status Construction Operation Description Peak laser power Pulse energy Fusion yield Location Organisation Image
4 pi laser Shut down 196? Semiconductor laser 5 GW 12 J   Livermore LLNL [29]
Long path laser Shut down 1972 1972 First ICF laser with neodymium doped glass (Nd:glass) as lasing medium 5 GW 50 J   Livermore LLNL [30]
Single Beam System (SBS) "67" Shut down 1971-1973 1973 Single-beam CO2 laser[89] 200 GW 1 kJ   Los Alamos LANL
Double Bounce Illumination System (DBIS) Shut down 1972-1974 1974-1990 First private laser fusion effort, YAG laser, neutron yield 104 to 3×105 neutrons 1 kJ ≈100 nJ   Ann Arbor, Michigan KMS Fusion  
MERLIN (Medium Energy Rod Laser Incorporating Neodymium), N78 laser Shut down 1972-1975 1975-? Nd:glass laser 100 GW 40 J   RAF Aldermaston AWE  
Cyclops laser Shut down 1975 1975 Single-beam Nd:glass laser, prototype for Shiva[90] 1 TW 270 J   Livermore LLNL  
Janus laser Shut down 1974-1975 1975 Two-beam Nd:glass laser demonstrated laser compression and thermonuclear burn of deuterium–tritium 1 TW 10 J   Livermore LLNL  
Gemini laser, Dual-Beam Module (DBM) Shut down ≤ 1975 1976 Two-beam CO2 laser, tests for Helios 5 TW 2.5 kJ   Los Alamos LANL
Argus laser Shut down 1976 1976-1981 Two-beam Nd:glass laser, advanced the study of laser-target interaction and paved the way for Shiva 4 TW 2 kJ ≈3 mJ   Livermore LLNL  
Vulcan laser (Versicolor Ultima Lux Coherens pro Academica Nostra)[91] Operational 1976-1977 1977- 8-beam Nd:glass laser, highest-intensity focussed laser in the world in 2005[92] 1 PW 2.6 kJ   Didcot RAL  
Shiva laser Shut down 1977 1977-1981 20-beam Nd:glass laser; proof-of-concept for Nova; fusion yield of 1011 neutrons; found that its infrared wavelength of 1062 nm was too long to achieve ignition 30 TW 10.2 kJ ≈0.1 J   Livermore LLNL  
Helios laser, Eight-Beam System (EBS) Shut down 1975-1978 1978 8-beam CO2 laser; Media at Wikimedia Commons 20 TW 10 kJ   Los Alamos LANL  
HELEN (High Energy Laser Embodying Neodymium) Shut down 1976-1979 1979-2009 Two-beam Nd:glass laser 1 TW 200 J   Didcot RAL  
ISKRA-4 Operational -1979 1979- 8-beam iodine gas laser, prototype for ISKRA-5[93] 10 TW 2 kJ 6 mJ   Sarov RFNC-VNIIEF
Sprite laser[91] Shut down 1981-1983 1983-1995 First high-power Krypton fluoride laser used for target irradiation, λ=249 nm 1 TW 7.5 J   Didcot RAL  
Gekko XII Operational 1983- 12-beam, Nd:glass laser 500 TW 10 kJ   Osaka Institute for Laser Engineering
Novette laser Shut down 1981-1983 1983-1984 Nd:glass laser to validate the Nova design, first X-ray laser[94] 13 TW 18 kJ  Livermore LLNL  
Antares laser, High Energy Gas Laser Facility (HEGLF) Shut down 1983[95] 24-beam largest CO2 laser ever built. Missed goal of scientific fusion breakeven, because production of hot electrons in target plasma due to long 10.6 μm wavelength of laser resulted in poor laser/plasma energy coupling[94] 200 TW 40 kJ   Los Alamos LANL
PHAROS laser Operational 198? Two-beam Nd:glass laser 300 GW 1 kJ   Washington D.C. NRL
Nova laser Shut down 1984-1999 10-beam NIR and frequency-tripled 351 nm UV laser; fusion yield of 1013 neutrons; attempted ignition, but failed due to fluid instability of targets; led to construction of NIF 1.3 PW 120 kJ 30 J  Livermore LLNL
ISKRA-5 Operational -1989 12-beam iodine gas laser, fusion yield 1010 to 1011 neutrons[93] 100 TW 30 kJ 0.3 J   Sarov RFNC-VNIIEF
Aurora laser Shut down ≤ 1988-1989 1990 96-beam Krypton fluoride laser ≈300 GW 1.3 kJ   Los Alamos LANL
PALS, formerly "Asterix IV" Operational -1991 1991- Iodine gas laser, λ=1315 nm 3 TW 1 kJ   Garching,
  Prague		 MPQ, CAS  
Trident laser Operational 198?-1992 1992-2017 3-beam Nd:glass laser; 2 x 400 J beams, 100 ps – 1 us; 1 beam ~100 J, 600 fs – 2 ns 200 TW 500 J   Los Alamos LANL  
Nike laser Operational ≤ 1991-1994 1994- 56-beam, most-capable Krypton fluoride laser for laser target interactions[96][97] 2.6 TW 3 kJ   Washington, D.C. NRL  
OMEGA laser Operational ?-1995 1995- 60-beam UV frequency-tripled Nd:glass laser, fusion yield 1014 neutrons 60 TW 40 kJ 300 J   Rochester LLE
Electra Operational Krypton fluoride laser, 5 Hz operation with 90,000+ shots continuous 4 GW 730 J   Washington D.C. NRL  
LULI2000 Operational ? 2003- 6-beam Nd:glass laser, λ=1.06 μm, λ=0.53 μm, λ=0.26 μm 500 GW 600 J   Palaiseau École polytechnique
OMEGA EP Operational 2008- 60-beam UV 1.4 PW 5 kJ   Rochester LLE
National Ignition Facility (NIF) Operational 1997-2009 2010- 192-beam Nd:glass laser, achieved scientific breakeven with fusion gain of 1.5 and 1.2×1018 neutrons[98] 500 TW 2.05 MJ 3.15 MJ   Livermore LLNL  
Orion Operational 2006-2010 2010- 10-beams, λ=351 nm 200 TW 5 kJ   RAF Aldermaston AWE  
Laser Mégajoule (LMJ) Operational 1999-2014 2014- Second-largest laser fusion facility, 10 out of 22 beam lines operational in 2022[99] 800 TW 1 MJ   Bordeaux CEA [31]
Laser for Fast Ignition Experiments (LFEX) Operational 2003-2015 2015- High-contrast heating laser for FIREX, λ=1053 nm 2 PW 10 kJ 100 μJ   Osaka Institute for Laser Engineering
HiPER (High Power Laser Energy Research Facility) Cancelled 2007-2015 - Pan-European project to demonstrate the technical and economic viability of laser fusion for the production of energy[100] (4 PW) (270 kJ) (25 MJ)    
Laser Inertial Fusion Energy (LIFE) Cancelled 2008-2013 - Effort to develop a fusion power plant succeeding NIF (2.2 MJ) (40 MJ)   Livermore LLNL  
ISKRA-6 Planned ? ? 128 beam Nd:glass laser 300 TW? 300 kJ?   Sarov RFNC-VNIIEF

Z-pinch

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Main article: Z-pinch

Inertial electrostatic confinement

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Main article: Inertial electrostatic confinement

Magnetized target fusion

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Main article: Magnetized target fusion

References

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See also

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