View source for List of fusion experiments

{{Short description|List of efforts toward artificial nuclear fusion}}
{{Multiple issues|
{{external links|date=April 2018}}
{{citation style|date=April 2018}}
}}
[[File:Shiva laser target chamber.jpg|thumb|upright=1.5|Target chamber of the [[Shiva laser]], used for inertial confinement fusion experiments from 1978 until decommissioned in 1981]]
[[File:U.S. Department of Energy - Science - 114 035 002 (14281232230).jpg|thumb|upright=1.5|Plasma chamber of [[TFTR]], used for magnetic confinement fusion experiments, which produced {{val|11|u=MW}} of fusion power in 1994]]
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 (physics)|plasma]] fuel and keep it hot.

The major division is between [[Magnetic confinement fusion|magnetic confinement]] and [[Inertial confinement fusion|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 {{val|e=18}} to {{val|e=22|u=m<sup>−3</sup>}} and the linear dimensions in the range of {{val|0.1|to|10|u=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 {{val|e=31}} to {{val|e=33|u=m<sup>−3</sup>}} and the plasma radius in the range of 1 to 100 micrometers. These conditions are obtained by [[irradiation|irradiating]] a millimeter-sized solid pellet with a nanosecond laser or ion pulse. The outer layer of the pellet is [[ablation|ablated]], providing a reaction force that compresses the central 10% of the fuel by a factor of 10 or 20 to 10<sup>3</sup> or {{val|e=4}} 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 fusion|magnetic confinement]] experiments, there is a basic division between [[torus|toroidal]] and open magnetic field [[topology|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 [[magnetic mirror|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-[[Maxwell–Boltzmann distribution|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 toroid]]s, 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<ref>{{Cite web |title=International tokamak research |url=http://www.iter.org/sci/tkmkresearch |website=ITER}}</ref> ====
{| class="wikitable sortable"
|-
! Device name !! Status !! Construction !! Operation !! Location !! Organisation !!data-sort-type=number| Major/minor radius !!data-sort-type=number| B-field !!data-sort-type=number| Plasma current !! Purpose !! Image
|-
| T-1 (Tokamak-1)<ref name="Smirnov2009">{{cite journal | last1 = Smirnov | first1 = V.P. | title = Tokamak foundation in USSR/Russia 1950–1990 | journal = Nuclear Fusion | date = 30 December 2009 | volume = 50 | issue = 1 | page = 014003 | issn = 0029-5515 | eissn = 1741-4326 | doi = 10.1088/0029-5515/50/1/014003 | s2cid = 17487157 | doi-access = free }}</ref> || {{no|Shut down}} || 1957 || 1958–1959 || {{flagicon|SOV}} Moscow || [[Kurchatov Institute]] || {{val|0.625|u=m}}/{{val|0.13|u=m}} || {{val|1|u=T}} || {{val|0.04|u=MA}} || First tokamak || [[File:Tokamak T-1.jpg|frameless|154x154px|T-1]]
|-
| {{Anchor|T-2}}T-2 (Tokamak-2)<ref name="Smirnov2009"/> || {{CRecurring|Recycled}} →[[#FT-1|FT-1]] || 1959 || 1960–1970 || {{flagicon|SOV}} Moscow || [[Kurchatov Institute]] || {{val|0.62|u=m}}/{{val|0.22|u=m}} || {{val|1|u=T}} || {{val|0.04|u=MA}} ||  ||
|-
| T-3 (Tokamak-3)<ref name="Smirnov2009"/> || {{no|Shut down}} || 1960 || 1962–? || {{flagicon|SOV}} Moscow || [[Kurchatov Institute]] || {{val|1|u=m}}/{{val|0.12|u=m}} || {{val|3.5|u=T}} || {{val|0.15|u=MA}} || Overcame Bohm diffusion by a factor of 10, temperature {{val|10|u=MK}}, confinement time {{val|10|u=ms}} ||
|-
| T-5 (Tokamak-5)<ref name="Smirnov2009"/> || {{no|Shut down}} || ? || 1962–1970 || {{flagicon|SOV}} Moscow || [[Kurchatov Institute]] || {{val|0.625|u=m}}/{{val|0.15|u=m}} || {{val|1.2|u=T}} || {{val|0.06|u=MA}} || Investigation of plasma equilibrium in vertical and horizontal direction ||
|-
| TM-1 || {{no|Shut down}} || ? || ? || {{flagicon|SOV}} Moscow || [[Kurchatov Institute]] ||  ||  ||  ||  ||
|-
| TM-2 || {{no|Shut down}} || ? || 1965 || {{flagicon|SOV}} Moscow || [[Kurchatov Institute]] ||  ||  ||  ||  ||
|-
| TM-3 || {{no|Shut down}} || ? || 1970 || {{flagicon|SOV}} Moscow || [[Kurchatov Institute]] ||  ||  ||  ||  ||
|-
| {{Anchor|FT-1}}FT-1<ref name="Smirnov2009"/> || {{CRecurring|Recycled}} →CASTOR || data-sort-value="1970"| [[#T-2|T-2]] || 1972–2002 || {{flagicon|SOV}} Saint Petersburg || [[Ioffe Institute]] || {{val|0.62|u=m}}/{{val|0.22|u=m}} || {{val|1.2|u=T}} || {{val|0.05|u=MA}} ||  ||
|-
| {{Anchor|ST}}ST (Symmetric Tokamak) || {{no|Shut down}} || data-sort-value="1969"| [[#Model C|Model C]] || 1970–1974 || {{flagicon|USA}} Princeton || [[Princeton Plasma Physics Laboratory]] || {{val|1.09|u=m}}/{{val|0.13|u=m}} || {{val|5.0|u=T}} || {{val|0.13|u=MA}} || First American tokamak, converted from Model C stellarator ||
|-
| T-6 (Tokamak-6) || {{no|Shut down}} || ? || 1970–1974 || {{flagicon|SOV}} Moscow || [[Kurchatov Institute]] || {{val|0.7|u=m}}/{{val|0.25|u=m}} || {{val|1.5|u=T}} || {{val|0.22|u=MA}} ||  ||
|-
| TUMAN-2, 2A || {{no|Shut down}} || ? || 1971–1985 || {{flagicon|SOV}} Saint Petersburg || [[Ioffe Institute]] || {{val|0.4|u=m}}/{{val|0.08|u=m}} || {{val|1.5|u=T}} || {{val|0.012|u=MA}} ||  ||
|-
| ORMAK (Oak Ridge tokaMAK) || {{no|Shut down}} ||  || 1971–1976 || {{flagicon|USA}} Oak Ridge || [[Oak Ridge National Laboratory]] || {{val|0.8|u=m}}/{{val|0.23|u=m}} || {{val|2.5|u=T}} || {{val|0.34|u=MA}} || First to achieve {{val|20|u=MK}} plasma temperature || [[File:ORMAK (46436229152).jpg|frameless|154x154px|ORMAK plasma vessel]]
|-
| Doublet II || {{no|Shut down}} ||  || 1972–1974 || {{flagicon|USA}} San Diego || [[General Atomics]] || {{val|0.63|u=m}}/{{val|0.08|u=m}} || {{val|0.95|u=T}} || {{val|0.21|u=MA}} ||  || [https://images.squarespace-cdn.com/content/53475027e4b01ccabb36ceb0/1398742664271-H9FP5GAQOZFLFHVS3BBZ/?format=750w&content-type=image%2Fjpeg]
|-
| ATC (Adiabatic Toroidal Compressor) || {{no|Shut down}} || 1971–1972 || 1972–1976 || {{flagicon|USA}} Princeton || [[Princeton Plasma Physics Laboratory]] || {{val|0.88|u=m}}/{{val|0.11|u=m}} || {{val|2|u=T}} || {{val|0.05|u=MA}} || Demonstrate compressional plasma heating || [[File:HD.6D.745 (13471450163).jpg|frameless|154x154px|Schematic of ATC]]
|-
| T-9 (Tokamak-9) || {{no|Shut down}} || ? || 1972–1977 || {{flagicon|SOV}} Moscow || [[Kurchatov Institute]] || {{val|0.36|u=m}}/{{val|0.07|u=m}} || {{val|1|u=T}} ||  ||  ||
|-
| TO-1 || {{no|Shut down}} || ? || 1972–1978 || {{flagicon|SOV}} Moscow || [[Kurchatov Institute]] || {{val|0.6|u=m}}/{{val|0.13|u=m}} || {{val|1.5|u=T}} || {{val|0.07|u=MA}} ||  ||
|-
| Alcator A (Alto Campo Toro) || {{no|Shut down}} || ? || 1972–1978 || {{flagicon|USA}} Cambridge || [[Massachusetts Institute of Technology]] || {{val|0.54|u=m}}/{{val|0.10|u=m}} || {{val|9.0|u=T}} || {{val|0.3|u=MA}} ||  || 
|-
| JFT-2 (JAERI Fusion Torus 2) || {{no|Shut down}} || ? || 1972–1982 || {{flagicon|JP}} Naka || [[Japan Atomic Energy Research Institute]] || {{val|0.9|u=m}}/{{val|0.25|u=m}} || {{val|1.8|u=T}} || {{val|0.25|u=MA}} ||  || 
|-
| Turbulent Tokamak Frascati (TTF, torello) || {{no|Shut down}} || || 1973 || {{flagicon|ITA}} Frascati || [[ENEA (Italy)|ENEA]] || {{val|0.3|u=m}}/{{val|0.04|u=m}} || {{val|1|u=T}} || {{val|0.005|u=MA}} || Study of turbulent plasma heating || [https://www.eai.enea.it/images/2-2019/tokamak-turbolento__759x711.jpg]
|-
| Pulsator<ref>{{Cite web|url=https://www.ipp.mpg.de/3951851/pulsator|title=Pulsator}}</ref> || {{no|Shut down}} || 1970–1973 || 1973–1979 || {{flagicon|DEU}} [[Garching]] || [[Max Planck Institute for Plasma Physics]] || {{val|0.7|u=m}}/{{val|0.12|u=m}} || {{val|2.7|u=T}} || {{val|0.125|u=MA}} || Discovery of high-density operation with tokamaks || [https://www.ipp.mpg.de/4332317/original-1580917311.webp]
|-
| [[Tokamak de Fontenay aux Roses|TFR]] (Tokamak de Fontenay-aux-Roses) || {{no|Shut down}} || || 1973–1984 || {{flagicon|FRA}} Fontenay-aux-Roses || [[French Alternative Energies and Atomic Energy Commission|CEA]] || {{val|0.98|u=m}}/{{val|0.2|u=m}} || {{val|6|u=T}} || {{val|0.49|u=MA}} || || [http://www.jp-petit.org/NUCLEAIRE/ITER/ITER_fusion_non_controlee/DISRUPTIONS/illustrations/TFR_Fontenay.gif]
|-
| T-4 (Tokamak-4)<ref name="Smirnov2009"/> || {{no|Shut down}} || ? || 1974–1978 || {{flagicon|SOV}} Moscow || [[Kurchatov Institute]] || {{val|0.9|u=m}}/{{val|0.16|u=m}} || {{val|5|u=T}} || {{val|0.3|u=MA}} || Observed fast thermal quench before major plasma disruptions ||
|-
| Doublet IIA || {{no|Shut down}} ||  || 1974–1979 || {{flagicon|USA}} San Diego || [[General Atomics]] || {{val|0.66|u=m}}/{{val|0.15|u=m}} || {{val|0.76|u=T}} || {{val|0.35|u=MA}} ||  || 
|-
| Petula-B || {{no|Shut down}} || ? || 1974–1986 || {{flagicon|FRA}} Grenoble || [[French Alternative Energies and Atomic Energy Commission|CEA]] || {{val|0.72|u=m}}/{{val|0.18|u=m}} || {{val|2.7|u=T}} || {{val|0.23|u=MA}} || ||
|-
| T-10 (Tokamak-10)<ref name="Smirnov2009"/> || {{active|Operational}} ||  || 1975– || {{flagicon|SOV}} Moscow || [[Kurchatov Institute]] || {{val|1.50|u=m}}/{{val|0.37|u=m}} || {{val|4|u=T}} || {{val|0.8|u=MA}} || Largest tokamak of its time || [[File:Polytec TOKAMAK model (4260325496).jpg|frameless|154x154px|Model of the T-10]]
|-
| T-11 (Tokamak-11) || {{no|Shut down}} || ? || 1975–1984 || {{flagicon|SOV}} Moscow || [[Kurchatov Institute]] || {{val|0.7|u=m}}/{{val|0.25|u=m}} || {{val|1|u=T}} ||  ||  ||
|-
| [[Princeton Large Torus|PLT]] (Princeton Large Torus) || {{no|Shut down}} || 1972–1975 || 1975–1986 || {{flagicon|USA}} Princeton || [[Princeton Plasma Physics Laboratory]] || {{val|1.32|u=m}}/{{val|0.42|u=m}} || {{val|4|u=T}} || {{val|0.7|u=MA}} || First to achieve {{val|1|u=MA}} plasma current || [[File:HD.6B.701 (10348295326).jpg|frameless|154x154px|Construction of the Princeton Large Torus]]
|-
| Divertor Injection Tokamak Experiment (DITE) || {{no|Shut down}} || || 1975–1989 || {{flagicon|UK}} Culham || [[United Kingdom Atomic Energy Authority]]|| {{val|1.17|u=m}}/{{val|0.27|u=m}} || {{val|2.7|u=T}} || {{val|0.26|u=MA}} ||  ||
|-
| JIPP T-II || {{no|Shut down}} || ? || 1976 || {{flagicon|JP}} Nagoya || Nagoya University || {{val|0.91|u=m}}/{{val|0.17|u=m}} || {{val|3|u=T}} || {{val|0.16|u=MA}} ||  || 
|-
| TNT-A || {{no|Shut down}} || ? || 1976 || {{flagicon|JP}} Tokyo || Tokyo University || {{val|0.4|u=m}}/{{val|0.09|u=m}} || {{val|0.42|u=T}} || {{val|0.02|u=MA}} ||  || 
|-
| T-8 (Tokamak-8)<ref name="Smirnov2009"/> || {{no|Shut down}} || ? || 1976–? || {{flagicon|SOV}} Moscow || [[Kurchatov Institute]] || {{val|0.28|u=m}}/{{val|0.048|u=m}} || {{val|0.9|u=T}} || {{val|0.024|u=MA}} || First D-shaped tokamak || 
|-
| Microtor<ref name="ICRF1980">{{cite report|author=Taylor, R. J. |author2=Lee, P. |author3=Luhmann, N. C. Jr | date=1981| title=ICRF heating, particle transport and fluctuations in tokamaks| url=http://plasma.caltech.edu/Rwgpubs/Pub66.pdf |archive-url=https://web.archive.org/web/20220225031806/http://plasma.caltech.edu/Rwgpubs/Pub66.pdf|archive-date=2022-02-25}}</ref> || {{no|Shut down}} || ? || 1976–1983? || {{flagicon|USA}} Los Angeles || [[UCLA]] || {{val|0.3|u=m}}/{{val|0.1|u=m}} || {{val|2.5|u=T}} || {{val|0.12|u=MA}} || Plasma impurity control and diagnostic development ||
|-
| Macrotor<ref name="ICRF1980"/> || {{no|Shut down}} || ? || 1970s–80s || {{flagicon|USA}} Los Angeles || [[UCLA]] || {{val|0.9|u=m}}/{{val|0.4|u=m}} || {{val|0.4|u=T}} || {{val|0.1|u=MA}} || Understanding plasma rotation driven by radial current ||
|-
| TUMAN-3<ref name="Smirnov2009"/> || {{active|Operational}} || ? || 1977–<br/>(1990–, 3M) || {{flagicon|SOV}} Saint Petersburg || [[Ioffe Institute]] || {{val|0.55|u=m}}/{{val|0.23|u=m}} || {{val|3|u=T}} || {{val|0.18|u=MA}} || Study adiabatic compression, RF and NB heating, H-mode and parametric instability ||
|-
| Thor<ref name="ArgentiBonizzoniCirant1981">{{cite journal | last1 = Argenti | first1 = D. | last2 = Bonizzoni | first2 = G. | last3 = Cirant | first3 = S. | last4 = Corti | first4 = S. | last5 = Grosso | first5 = G. | last6 = Lampis | first6 = G. | last7 = Rossi | first7 = L. | last8 = Carretta | first8 = U. | last9 = Jacchia | first9 = A. | last10 = De Luca | first10 = F. | last11 = Fontanesi | first11 = M. | title = The Thor tokamak experiment | journal = Il Nuovo Cimento B | date = June 1981 | volume = 63 | issue = 2 | pages = 471–486 | eissn = 1826-9877 | doi = 10.1007/BF02755093 | bibcode = 1981NCimB..63..471A | s2cid = 123205206 }}</ref> || {{no|Shut down}} || || ? || {{flagicon|ITA}} Milano || University of Milano || {{val|0.52|u=m}}/{{val|0.195|u=m}} || {{val|1|u=T}} || {{val|0.055|u=MA}} ||  || [https://www.eai.enea.it/images/2-2019/thor__400x313.jpg]
|-
| FT (Frascati Tokamak) || {{no|Shut down}} || || 1978 || {{flagicon|ITA}} Frascati || [[ENEA (Italy)|ENEA]] || {{val|0.83|u=m}}/{{val|0.20|u=m}} || {{val|10|u=T}} || {{val|0.8|u=MA}} ||  ||
|-
| PDX (Poloidal Divertor Experiment) || {{no|Shut down}} || ? || 1978–1983 || {{flagicon|USA}} Princeton || [[Princeton Plasma Physics Laboratory]] || {{val|1.4|u=m}}/{{val|0.4|u=m}} || {{val|2.4|u=T}} || {{val|0.5|u=MA}} ||  ||
|-
| ISX-B || {{no|Shut down}} || ? || 1978–1984 || {{flagicon|USA}} Oak Ridge || [[Oak Ridge National Laboratory]] || {{val|0.93|u=m}}/{{val|0.27|u=m}} || {{val|1.8|u=T}} || {{val|0.2|u=MA}} || Attempt high-beta operation ||
|-
| Doublet III || {{no|Shut down}} ||  || 1978–1985 || {{flagicon|USA}} San Diego || [[General Atomics]] || {{val|1.45|u=m}}/{{val|0.45|u=m}} || {{val|2.6|u=T}} || {{val|0.61|u=MA}} ||  || [https://i.redd.it/mr6t7857jcm21.jpg]
|-
| T-12 (Tokamak-12) || {{no|Shut down}} || ? || 1978–1985 || {{flagicon|SOV}} Moscow || [[Kurchatov Institute]] || {{val|0.36|u=m}}/{{val|0.08|u=m}} || {{val|1|u=T}} || {{val|0.03|u=MA}} ||  ||
|-
| Alcator C (Alto Campo Toro) || {{no|Shut down}} || ? || 1978–1986 || {{flagicon|USA}} Cambridge || [[Massachusetts Institute of Technology]] || {{val|0.64|u=m}}/{{val|0.16|u=m}} || {{val|13|u=T}} || {{val|0.8|u=MA}} ||  || 
|-
| {{Anchor|T-7}}T-7 (Tokamak-7)<ref name="Smirnov2009"/> || {{CRecurring|Recycled}} →[[#HT-7|HT-7]]<ref>{{Cite web|url=https://www.iter.org/newsline/81/508|title=From Russia with love|date=2009-05-18|author=Robert Arnoux}}</ref> || ? || 1979–1985 || {{flagicon|SOV}} Moscow || [[Kurchatov Institute]] || {{val|1.2|u=m}}/{{val|0.31|u=m}} || {{val|3|u=T}} || {{val|0.3|u=MA}} || First tokamak with superconducting toroidal field coils ||
|-
| [[ASDEX Upgrade#ASDEX|ASDEX]] (Axially Symmetric Divertor Experiment)<ref>{{Cite web|url=https://www.ipp.mpg.de/3951875/asdex|title=ASDEX|website=www.ipp.mpg.de}}</ref> || {{CRecurring|Recycled}} →[[#HL-2A|HL-2A]] || 1973–1980 || 1980–1990 || {{flagicon|DEU}} [[Garching]] || [[Max-Planck-Institut für Plasmaphysik]] || {{val|1.65|u=m}}/{{val|0.4|u=m}} || {{val|2.8|u=T}} || {{val|0.5|u=MA}} || Discovery of the [[High-confinement mode|H-mode]] in 1982 || [https://www.ipp.mpg.de/4332327/original-1580918149.webp]
|-
| FT-2<ref name="Smirnov2009"/> || {{active|Operational}} || ? || 1980– || {{flagicon|SOV}} Saint Petersburg || [[Ioffe Institute]] || {{val|0.55|u=m}}/{{val|0.08|u=m}} || {{val|3|u=T}} || {{val|0.05|u=MA}} || H-mode physics, LH heating ||
|-
| [[Forschungszentrum Jülich#TEXTOR tokamak|TEXTOR]] (''Tokamak Experiment for Technology Oriented Research'')<ref>{{Cite web|url=http://www.fz-juelich.de/ief/ief-4//textor_en/#|title=Forschungszentrum Jülich – Plasmaphysik (IEK-4)|website=fz-juelich.de|language=de}}</ref><ref>[https://web.archive.org/web/20161019163554/http://www.fz-juelich.de/SharedDocs/Downloads/IEK/IEK-4/DE/30years_TEXTOR_pdf.pdf?__blob=publicationFile Progress in Fusion Research – 30 Years of TEXTOR]</ref> || {{no|Shut down}} || 1976–1980 || 1981–2013 || {{flagicon|DEU}} Jülich || [[Forschungszentrum Jülich]] || {{val|1.75|u=m}}/{{val|0.47|u=m}} || {{val|2.8|u=T}} || {{val|0.8|u=MA}} || Study plasma-wall interactions ||
|-
| [[TFTR]] (Tokamak Fusion Test Reactor)<ref>{{Cite web|url=http://www.pppl.gov/projects/pages/tftr.html|archive-url=https://web.archive.org/web/20110426091028/http://www.pppl.gov/projects/pages/tftr.html|archive-date=2011-04-26|title=Tokamak Fusion Test Reactor|date=2011-04-26}}</ref> || {{no|Shut down}} || 1980–1982 || 1982–1997 || {{flagicon|USA}} Princeton || [[Princeton Plasma Physics Laboratory]] || {{val|2.4|u=m}}/{{val|0.8|u=m}} || {{val|5.9|u=T}} || {{val|3|u=MA}} || Attempted scientific break-even, reached record fusion power of {{val|10.7|u=MW}} and temperature of {{val|510|u=MK}} || [[File:U.S. Department of Energy - Science - 114 035 002 (14281232230).jpg|frameless|154x154px|TFTR plasma vessel]]
|-
| [[Tokamak de Varennes]] (TdeV) || {{no|Shut down}} || ? || 1983–1997 || {{flagicon|CAN}} Montreal || [[National Research Council Canada]] || {{val|0.83|u=m}}/{{val|0.27|u=m}} || {{val|1.5|u=T}} || {{val|0.3|u=MA}} || <ref>{{cite web |url=https://www.iter.org/newsline/-/3033 |title=The second-hand market |author=Robert Arnoux |work=ITER newsline |date=2018-06-18}}</ref> || [https://www.iter.org/img/resize-900-90/www/content/com/Lists/Stories/Attachments/3033/tok_varennes_ottawa.jpg]
|-
| JFT-2M  (JAERI Fusion Torus 2M) || {{no|Shut down}} || ? || 1983–2004 || {{flagicon|JP}} Naka || [[Japan Atomic Energy Research Institute]] || {{val|1.3|u=m}}/{{val|0.35|u=m}} || {{val|2.2|u=T}} || {{val|0.5|u=MA}} ||  || [https://www-jt60.naka.qst.go.jp/jft2m/images/introductionfig1.jpg]
|-
| [[Joint European Torus|JET]] (Joint European Torus)<ref>{{Cite web|url=http://www.jet.efda.org/index.html|archive-url=https://web.archive.org/web/20060430205106/http://www.jet.efda.org/index.html|archive-date=2006-04-30|title=EFDA-JET, the world's largest nuclear fusion research experiment|date=2006-04-30}}</ref> || {{no|Shut down}} || 1978–1983 || 1983–2023 || {{flagicon|UK}} [[Culham]] || [[United Kingdom Atomic Energy Authority]]|| {{val|2.96|u=m}}/{{val|0.96|u=m}} || {{val|4|u=T}} || {{val|7|u=MA}} || Records for fusion output power {{val|16.1|u=MW}} (1997), fusion energy {{val|69|u=MJ}} (2023) || [[File:JET cutaway drawing 1980.jpg|frameless|154x154px|JET in 1991]]
|-
| [[:es:Tokamak Novillo|Novillo]]<ref>{{Cite web|url=http://www.inin.mx/paraconocer/fusionnuclear.cfm|archive-url=https://web.archive.org/web/20091125165554/http://www.inin.mx/paraconocer/fusionnuclear.cfm|archive-date=2009-11-25|title=:::. Instituto Nacional de Investigaciones Nucleares {{!}} Fusión nuclear .|date=2009-11-25}}</ref><ref>{{Cite web|url=http://www.tokamak.info/|title=All-the-Worlds-Tokamaks|website=tokamak.info}}</ref> || {{no|Shut down}} || NOVA-II || 1983–2004 || {{flagicon|MEX}} Mexico City || Instituto Nacional de Investigaciones Nucleares || {{val|0.23|u=m}}/{{val|0.06|u=m}} || {{val|1|u=T}} || {{val|0.01|u=MA}} || Study plasma-wall interactions ||
|-
| [[JT-60]] (Japan Torus-60)<ref>{{Cite journal|url=http://www-jt60.naka.jaea.go.jp/english/jt60/index.html|archive-url=https://web.archive.org/web/20061002101524/http://www-jt60.naka.jaea.go.jp/english/jt60/index.html|archive-date=2006-10-02|title=JT-60 Project |journal=Fusion Technology 1978 |volume=2 |page=1079 |date=2006-10-02|bibcode=1979fute.conf.1079Y |last1=Yoshikawa |first1=M. }}</ref> || {{CRecurring|Recycled}} →[[#JT-60SA|JT-60SA]] || || 1985–2010 || {{flagicon|JP}} Naka || [[Japan Atomic Energy Research Institute]] || {{val|3.4|u=m}}/{{val|1.0|u=m}} || {{val|4|u=T}} || {{val|3|u=MA}} || High-beta steady-state operation, highest [[fusion triple product]] ||
|-
| CCT (Continuous Current Tokamak) || {{no|Shut down}} || ? || 1986–199? || {{flagicon|USA}} Los Angeles || [[UCLA]] || {{val|1.5|u=m}}/{{val|0.4|u=m}} || {{val|0.2|u=T}} || {{val|0.05|u=MA}} || H-mode studies ||
|-
| [[DIII-D (tokamak)|DIII-D]]<ref>{{Cite web|url=https://fusion.gat.com/global/diii-d/home|title=diii-d:home [MFE: DIII-D and Theory]|website=fusion.gat.com|language=en|access-date=2018-09-04}}</ref> || {{active|Operational}} || 1986<ref>{{Cite web|url=https://science.energy.gov/fes/facilities/user-facilities/diii-d/|title=DIII-D National Fusion Facility (DIII-D) {{!}} U.S. DOE Office of Science (SC)|website=science.energy.gov|language=en-us|access-date=2018-09-04}}</ref> || 1986– || {{flagicon|USA}} San Diego || [[General Atomics]] || {{val|1.67|u=m}}/{{val|0.67|u=m}} || {{val|2.2|u=T}} || {{val|3|u=MA}} || Tokamak Optimization || [[File:2017 TOCAMAC Fusion Chamber N0689.jpg|frameless|154x154px|DIII-D vacuum vessel]]
|-
| [[Plasma Physics Laboratory (Saskatchewan)|STOR-M]] (Saskatchewan Torus-Modified)<ref>{{Cite web|url=http://plasma.usask.ca/storm/index.php|archive-url=https://web.archive.org/web/20110706211727/http://plasma.usask.ca/storm/index.php|archive-date=2011-07-06|title=U of S|date=2011-07-06}}</ref> || {{active|Operational}} || || 1987– || {{flagicon|CAN}} Saskatoon || [[Plasma Physics Laboratory (Saskatchewan)]] || {{val|0.46|u=m}}/{{val|0.125|u=m}} || {{val|1|u=T}} || {{val|0.06|u=MA}} || Study plasma heating and anomalous transport || [https://cna.ca/wp-content/uploads/2014/05/STORM.jpg]
|-
| [[T-15 (reactor)|T-15]]<ref name="Smirnov2009"/> || {{CRecurring|Recycled}} →[[#T-15MD|T-15MD]] || 1983–1988 || 1988–1995 || {{flagicon|SOV}} Moscow || [[Kurchatov Institute]] || {{val|2.43|u=m}}/{{val|0.78|u=m}} || {{val|3.6|u=T}} || {{val|1|u=MA}} || First superconducting tokamak, pulse duration {{val|1.5|u=s}} || [[File:1987 CPA 5891.jpg|frameless|154x154px|T-15 on a stamp]]
|-
| [[Tore Supra]]<ref>{{Cite web|url=http://www-fusion-magnetique.cea.fr/gb/cea/ts/ts.htm|title=Tore Supra|website=www-fusion-magnetique.cea.fr|access-date=2018-09-04}}</ref> || {{CRecurring|Recycled}} →[[#WEST|WEST]] || || 1988–2011 || {{flagicon|FRA}} Cadarache || Département de Recherches sur la Fusion Contrôlée || {{val|2.25|u=m}}/{{val|0.7|u=m}} || {{val|4.5|u=T}} || {{val|2|u=MA}} || Large superconducting tokamak with active cooling ||
|-
| [[ADITYA (tokamak)]] || {{active|Operational}} ||  || 1989– || {{flagicon|IND}} Gandhinagar || [[Institute for Plasma Research]] || {{val|0.75|u=m}}/{{val|0.25|u=m}} || {{val|1.2|u=T}} || {{val|0.25|u=MA}} || ||
|-
| [[COMPASS tokamak|COMPASS]] (COMPact ASSembly)<ref>{{Cite web|url=http://www.ipp.cas.cz/Tokamak/index?m=comp|archive-url=https://web.archive.org/web/20140512214251/http://www.ipp.cas.cz/Tokamak/index?m=comp|archive-date=2014-05-12|date=2014-05-12| title=Tokamak Department, Institute of Plasma Physics }}</ref><ref>{{Cite web|url=http://www.ipp.cas.cz/Tokamak/euratom/index.php/en/compass-general-information|archive-url=https://web.archive.org/web/20131025051208/http://www.ipp.cas.cz/Tokamak/euratom/index.php/en/compass-general-information|archive-date=2013-10-25|title=COMPASS – General information|date=2013-10-25}}</ref> || {{active|Operational}} || 1980– || 1989– || {{flagicon|CZ}} [[Prague]] || [[Institute of Plasma Physics AS CR]] || {{val|0.56|u=m}}/{{val|0.23|u=m}} || {{val|2.1|u=T}} || {{val|0.32|u=MA}} || Plasma physics studies for ITER || [[File:COMPASStokamak chamber.jpg|frameless|154x154px|COMPASS plasma chamber]]
|-
| FTU ([[Frascati Tokamak Upgrade]]) || {{active|Operational}} || || 1990– || {{flagicon|ITA}} Frascati || [[ENEA (Italy)|ENEA]] || {{val|0.935|u=m}}/{{val|0.35|u=m}} || {{val|8|u=T}} || {{val|1.6|u=MA}} ||  || [https://web.archive.org/web/20220326201820/http://www.fusione.enea.it/multimedia/photographs/FTU/FTU01-orig.jpg]
|-
| [[Small Tight Aspect Ratio Tokamak|START]] (Small Tight Aspect Ratio Tokamak)<ref>{{Cite web|url=http://www.fusion.org.uk/culham/start.htm|archive-url=https://web.archive.org/web/20060424061102/http://www.fusion.org.uk/culham/start.htm|archive-date=2006-04-24|date=2006-04-24}}</ref> || {{CRecurring|Recycled}} →[[Proto-Sphera]] || || 1990–1998 || {{flagicon|UK}} Culham || [[United Kingdom Atomic Energy Authority]]|| {{val|0.3|u=m}}/? || {{val|0.5|u=T}} || {{val|0.31|u=MA}} || First full-sized Spherical Tokamak || [https://www.engineerlive.com/sites/engineerlive/files/Plasma2.jpeg]
|-
| [[ASDEX Upgrade]] (Axially Symmetric Divertor Experiment) || {{active|Operational}} ||  || 1991– || {{flagicon|DEU}} [[Garching]] || [[Max-Planck-Institut für Plasmaphysik]] || {{val|1.65|u=m}}/{{val|0.5|u=m}} || {{val|2.6|u=T}} || {{val|1.4|u=MA}} ||  || [[File:ASDEX Upgrade model.jpg|frameless|154x154px|ASDEX Upgrade plasma vessel segment]]
|-
| [[Alcator C-Mod]] (Alto Campo Toro)<ref>{{Cite web|url=http://www.psfc.mit.edu/research/alcator/|archive-url=https://web.archive.org/web/20150709210155/http://www.psfc.mit.edu/research/alcator/|archive-date=2015-07-09|title=MIT Plasma Science & Fusion Center: research>alcator>|date=2015-07-09}}</ref> || {{no|Shut down}} || 1986– || 1991–2016 || {{flagicon|USA}} Cambridge || [[Massachusetts Institute of Technology]] || {{val|0.68|u=m}}/{{val|0.22|u=m}} || {{val|8|u=T}} || {{val|2|u=MA}} || Record plasma pressure {{val|2.05|u=bar}} || [[File:Alcator C-Mod Fisheye from Fport.jpg|frameless|154x154px|Alcator C-Mod plasma vessel]]
|-
| [[ISTTOK]] (Instituto Superior Técnico TOKamak)<ref>{{Cite web|url=http://www.cfn.ist.utl.pt/eng/Prj_Tokamak_main_1.html#intro|title=Centro de Fusão Nuclear|website=cfn.ist.utl.pt|access-date=2012-02-13|archive-url=https://web.archive.org/web/20100307154259/http://www.cfn.ist.utl.pt/eng/Prj_Tokamak_main_1.html#intro|archive-date=2010-03-07}}</ref> || {{active|Operational}} || || 1992– || {{flagicon|POR}} [[Lisbon]] || [[Instituto de Plasmas e Fusão Nuclear]] || {{val|0.46|u=m}}/{{val|0.085|u=m}} || {{val|2.8|u=T}} || {{val|0.01|u=MA}} || ||
|-
| [[Tokamak à configuration variable|TCV]] (''Tokamak à Configuration Variable'')<ref>{{Cite web|url=http://crppwww.epfl.ch/tcv/|title=EPFL|website=crppwww.epfl.ch}}</ref> || {{active|Operational}} || || 1992– || {{flagicon|CH}} Lausanne || [[École Polytechnique Fédérale de Lausanne]] || {{val|0.88|u=m}}/{{val|0.25|u=m}} || {{val|1.43|u=T}} || {{val|1.2|u=MA}} || Confinement studies || [[File:Tcv int.jpg|frameless|154x154px|TCV plasma vessel]]
|-
| HBT-EP (High Beta Tokamak-Extended Pulse) || {{active|Operational}} || || 1993– || {{flagicon|US}} New York City || [[Columbia University]] Plasma Physics Laboratory || {{val|0.92|u=m}}/{{val|0.15|u=m}} || {{val|0.35|u=T}} || {{val|0.03|u=MA}} || High-Beta tokamak || [[File:HBT-EP shells and sensors.jpg|frameless|154x154px|HBT-EP sketch]]
|-
| {{Anchor|HT-7}}[[HT-7]] (Hefei Tokamak-7) || {{no|Shut down}} || 1991–1994 ([[#T-7|T-7]]) || 1995–2013 || {{flagicon|CHN}} Hefei || [[Hefei Institutes of Physical Science]] || {{val|1.22|u=m}}/{{val|0.27|u=m}} || {{val|2|u=T}} || {{val|0.2|u=MA}} || China's first superconducting tokamak || 
|-
| [[Pegasus Toroidal Experiment]]<ref>{{Cite web|url=http://pegasus.ep.wisc.edu|title=Pegasus Toroidal Experiment|website=pegasus.ep.wisc.edu|language=en}}</ref> || {{active|Operational}} || ? || 1996– || {{flagicon|USA}} Madison || [[University of Wisconsin–Madison]] || {{val|0.45|u=m}}/{{val|0.4|u=m}} || {{val|0.18|u=T}} || {{val|0.3|u=MA}} || Extremely low aspect ratio || [[File:Pegasus Toroidal Experiment (6140926094).jpg|frameless|154x154px|Pegasus Toroidal Experiment]]
|-
| [[National Spherical Torus Experiment|NSTX]] (National Spherical Torus Experiment)<ref>{{Cite web|url=https://nstx-u.pppl.gov/|title=NSTX-U|website=nstx-u.pppl.gov|access-date=2018-09-04}}</ref> || {{active|Operational}} || || 1999– || {{flagicon|USA}} Plainsboro Township || [[Princeton Plasma Physics Laboratory]] || {{val|0.85|u=m}}/{{val|0.68|u=m}} || {{val|0.3|u=T}} || {{val|2|u=MA}} || Study the spherical tokamak concept || [[File:U.S. Department of Energy - Science - 114 003 003 (9939887676).jpg|frameless|154x154px|National Spherical Torus Experiment]]
|-
| Globus-M (UNU Globus-M)<ref>{{Cite web|url=https://globus.rinno.ru/|title=Globus-M experiment|website= globus.rinno.ru/|language=ru|access-date=2021-10-23}}</ref> || {{active|Operational}} || || 1999– || {{flagicon|RUS}} Saint Petersburg || [[Ioffe Institute]] || {{val|0.36|u=m}}/{{val|0.24|u=m}} || {{val|0.4|u=T}} || {{val|0.3|u=MA}} || Study the spherical tokamak concept || 
|-
| [[Electric Tokamak|ET]] (Electric Tokamak) || {{CRecurring|Recycled}} →[[Enormous Toroidal Plasma Device|ETPD]] || 1998 || 1999–2006 || {{flagicon|USA}} Los Angeles || [[UCLA]] || {{val|5|u=m}}/{{val|1|u=m}} || {{val|0.25|u=T}} || {{val|0.045|u=MA}} || Largest tokamak of its time || [[File:The Electric Tokamak.jpg|frameless|154x154px|The Electric Tokamak.jpg]]
|-
|[[Tokamak Chauffage Alfvén Brésilien (TCABR)|TCABR]] (''Tokamak Chauffage Alfvén Brésilien'')|| {{active|Operational}} 
|1980–1999
|1999–
|{{flagicon|SWI}} Lausanne,<br/>{{flagicon|BRA}} Sao Paulo
|[[University of São Paulo|University of Sao Paulo]]
|{{val|0.615|u=m}} / {{val|0.18|u=m}}
|{{val|1.1|u=T}}
|{{val|0.10|u=MA}}
|Most important tokamak in the southern hemisphere 
|[[File:TCABR lab.jpg|frameless|153x153px]]
|-
| CDX-U (Current Drive Experiment-Upgrade) || {{CRecurring|Recycled}} →[[#LTX|LTX]] ||  || 2000–2005 || {{flagicon|USA}} Princeton || [[Princeton Plasma Physics Laboratory]] || {{val|0.3|u=m}}/? || {{val|0.23|u=T}} || {{val|0.03|u=MA}} || Study Lithium in plasma walls || [[File:U.S. Department of Energy - Science - 413 002 003 (9952381694).jpg|frameless|154x154px|CDX-U setup]]
|-
| [[Mega Ampere Spherical Tokamak|MAST]] (Mega-Ampere Spherical Tokamak)<ref>{{Cite web|url=http://www.fusion.org.uk/mast/index.html|archive-url=https://web.archive.org/web/20060421081115/http://www.fusion.org.uk/mast/index.html|archive-date=2006-04-21|title=MAST – the Spherical Tokamak at UKAEA Culham|date=2006-04-21}}</ref> || {{CRecurring|Recycled}} →[[#MAST-Upgrade|MAST-Upgrade]] || 1997–1999 || 2000–2013 || {{flagicon|UK}} Culham || [[United Kingdom Atomic Energy Authority]]|| {{val|0.85|u=m}}/{{val|0.65|u=m}} || {{val|0.55|u=T}} || {{val|1.35|u=MA}} || Investigate spherical tokamak for fusion || [[File:MAST plasma image.jpg|frameless|154x154px|Plasma in MAST]]
|-
| {{Anchor|HL-2A}}[[HL-2A]] (Huan-Liuqi-2A) || {{active|Operational}} || 2000–2002 || 2002–2018 || {{flagicon|CHN}} [[Chengdu]] || [[Southwestern Institute of Physics]] || {{val|1.65|u=m}}/{{val|0.4|u=m}} || {{val|2.7|u=T}} || {{val|0.43|u=MA}} || H-mode physics, ELM mitigation || [https://alltheworldstokamaks.wordpress.com/gallery-of-external-views/hl-2acolour/]
|-
| [[SST-1 (tokamak)|SST-1]] (Steady State Superconducting Tokamak)<ref>{{Cite web|url=http://www.ipr.res.in/sst1/SST-1.html|archive-url=https://web.archive.org/web/20140620232825/http://www.ipr.res.in/sst1/SST-1.html|archive-date=2014-06-20|title=The SST-1 Tokamak Page|date=2014-06-20}}</ref> || {{active|Operational}} || 2001– || 2005– || {{flagicon|IND}} Gandhinagar || [[Institute for Plasma Research]] || {{val|1.1|u=m}}/{{val|0.2|u=m}} || {{val|3|u=T}} || {{val|0.22|u=MA}} || Produce a {{val|1000|u=s}} elongated double null divertor plasma ||
|-
| [[EAST (tokamak)|EAST]] (Experimental Advanced Superconducting Tokamak)<ref>{{Cite web|url=http://english.hf.cas.cn/ic/ip/east/|title=EAST (HT-7U Super conducting Tokamak)----Hefei Institutes of Physical Science, The Chinese Academy of Sciences|website=english.hf.cas.cn}}</ref> || {{active|Operational}} || 2000–2005 || 2006– || {{flagicon|CHN}} Hefei || [[Hefei Institutes of Physical Science]] || {{val|1.85|u=m}}/{{val|0.43|u=m}} || {{val|3.5|u=T}} || {{val|0.5|u=MA}} || Superheated plasma for over {{val|101|u=s}} at {{val|120|u=M°C}} and {{val|20|u=s}} at {{val|160|u=M°C}}<ref>{{cite news |title=Chinese "Artificial Sun" experimental fusion reactor sets world record for superheated plasma time |url=https://nation.com.pk/29-May-2021/chinese-artificial-sun-experimental-fusion-reactor-sets-world-record-for-superheated-plasma-time |date=May 29, 2021 |work=The Nation }}</ref> || [[File:EAST-tokamak sketch.png|frameless|154x154px|Drawing of EAST]]
|-
| J-TEXT (Joint TEXT) || {{active|Operational}} || TEXT (Texas EXperimental Tokamak) || 2007– || {{flagicon|CHN}} [[Wuhan]] || [[Huazhong University of Science and Technology]] || {{val|1.05|u=m}}/{{val|0.26|u=m}} || {{val|2.0|u=T}} || {{val|0.2|u=MA}} || Develop plasma control || [https://alltheworldstokamaks.wordpress.com/gallery-of-external-views/jtext/]
|-
| [[KSTAR]] (Korea Superconducting Tokamak Advanced Research)<ref>{{Cite web|url=http://www.nfri.re.kr/|archive-url=https://web.archive.org/web/20080530221257/http://www.nfri.re.kr/|archive-date=2008-05-30|date=2008-05-30}}</ref> || {{active|Operational}} || 1998–2007 || 2008– || {{flagicon|KOR}} Daejeon || [[National Fusion Research Institute]] || {{val|1.8|u=m}}/{{val|0.5|u=m}} || {{val|3.5|u=T}} || {{val|2|u=MA}} || Tokamak with fully superconducting magnets, {{val|48|u=s}}-long operation at {{val|100|u=MK}}<ref>{{cite news |last1=McFadden |first1=Christopher |title=South Korean 'artificial sun' reaches 7 times the Sun's core temperature |url=https://interestingengineering.com/energy/south-korea-artificial-sun-new-record |access-date=30 March 2024 |work=Interesting Engineering |date=29 March 2024}}</ref>|| [[File:KSTAR tokamak.jpg|frameless|154x154px|KSTAR]]
|-
| {{Anchor|LTX}}[[Lithium Tokamak Experiment|LTX]] (Lithium Tokamak Experiment) || {{active|Operational}} || 2005–2008 || 2008– || {{flagicon|USA}} Princeton || [[Princeton Plasma Physics Laboratory]] || {{val|0.4|u=m}}/? || {{val|0.4|u=T}} || {{val|0.4|u=MA}} || Study Lithium in plasma walls || [[File:U.S. Department of Energy - Science - 114 001 004 (29677232615).jpg|frameless|154x154px|Lithium Tokamak Experiment plasma vessel]]
|-
| [[Campus of Kyushu University|QUEST]] (Q-shu University Experiment with Steady-State Spherical Tokamak)<ref>{{Cite web|url=http://www.triam.kyushu-u.ac.jp/QUEST_HP/quest_e.html|archive-url=https://web.archive.org/web/20131110043518/http://www.triam.kyushu-u.ac.jp/QUEST_HP/quest_e.html|archive-date=2013-11-10|date=2013-11-10}}</ref> || {{active|Operational}} || || 2008– || {{flagicon|JP}} Kasuga || [[Kyushu University]] || {{val|0.68|u=m}}/{{val|0.4|u=m}} || {{val|0.25|u=T}} || {{val|0.02|u=MA}} || Study steady state operation of a Spherical Tokamak || [[File:QUEST tokamak (cropped).jpg|frameless|154x154px|QUEST]]
|-
| Kazakhstan Tokamak for Material testing (KTM) || {{active|Operational}} || 2000–2010 || 2010– || {{flagicon|KAZ}} Kurchatov || National Nuclear Center of the Republic of Kazakhstan || {{val|0.86|u=m}}/{{val|0.43|u=m}} || {{val|1|u=T}} || {{val|0.75|u=MA}} || Testing of wall and divertor ||
|-
| ST25-HTS<ref>{{cite web | url=https://www.tokamakenergy.co.uk/mission/st25/ | title=ST25 » Tokamak Energy | access-date=2018-10-21 | archive-date=2019-03-26 | archive-url=https://web.archive.org/web/20190326141452/https://www.tokamakenergy.co.uk/mission/st25/ | url-status=dead }}</ref> || {{active|Operational}} || 2012–2015 || 2015– || {{flagicon|UK}} Culham || [[Tokamak Energy]] Ltd || {{val|0.25|u=m}}/{{val|0.125|u=m}} || {{val|0.1|u=T}} || {{val|0.02|u=MA}} || Steady state plasma || [[File:Tokamak ST25 rf discharge.jpg|frameless|154x154px|ST25-HTS with plasma]]
|-
| {{Anchor|WEST}}[[WEST (formerly Tore Supra)|WEST]] (Tungsten Environment in Steady-state Tokamak) || {{active|Operational}} || 2013–2016 || 2016– || {{flagicon|FRA}} Cadarache || Département de Recherches sur la Fusion Contrôlée || {{val|2.5|u=m}}/{{val|0.5|u=m}} || {{val|3.7|u=T}} || {{val|1|u=MA}} || Superconducting tokamak with active cooling || [[File:WEST fish-eye lens.jpg|frameless|154x154px|WEST chamber]]
|-
| ST40<ref>{{cite web | url=https://www.tokamakenergy.co.uk/st40/ | title=ST40 » Tokamak Energy | access-date=2018-10-21 | archive-date=2019-03-26 | archive-url=https://web.archive.org/web/20190326150138/https://www.tokamakenergy.co.uk/st40/ | url-status=dead }}</ref> || {{active|Operational}} || 2017–2018 || 2018– || {{flagicon|UK}} Didcot ||[[Tokamak Energy]] Ltd || {{val|0.4|u=m}}/{{val|0.3|u=m}} || {{val|3|u=T}} || {{val|2|u=MA}} || First high field spherical tokamak, reached {{val|100|u=MK}} plasma || [[File:Tokamak ST40 engineering drawing.jpg|frameless|154x154px|ST40 engineering drawing]]
|-
| {{Anchor|MAST-Upgrade}}MAST-U (Mega-Ampere Spherical Tokamak Upgrade)<ref>{{Cite web|url=http://www.firefusionpower.org/FPA2016_MAST_Upgrade_Milnes.pptx|title=Status and Plans on MAST-U|date=2016-12-13}}</ref> || {{active|Operational}} || 2013–2019 || 2020– || {{flagicon|UK}} Culham || [[United Kingdom Atomic Energy Authority]]|| {{val|0.85|u=m}}/{{val|0.65|u=m}} || {{val|0.92|u=T}} || {{val|2|u=MA}} || Test new exhaust concepts for a spherical tokamak || [https://theoxfordmagazine.com/wp-content/uploads/mast-upgrade-01-1920x1080-1.jpg]
|-
| [[HL-2M]] (Huan-Liuqi-2M)<ref>{{cite web | url=https://www.neimagazine.com/news/newschina-completes-new-tokamak-7531412 | title=China completes new tokamak| date=29 November 2019}}</ref> || {{active|Operational}} || 2018–2019 || 2020– || {{flagicon|CHN}} [[Leshan]] || [[Southwestern Institute of Physics]] || {{val|1.78|u=m}}/{{val|0.65|u=m}} || {{val|2.2|u=T}} || {{val|1.2|u=MA}} || Elongated plasma with {{val|200|u=MK}} || [[File:HL-2M tokamak CAD.jpg|frameless|154x154px|HL-2M]]
|-
| {{Anchor|JT-60SA}}[[JT-60#JT-60SA|JT-60SA]] (Japan Torus-60 super, advanced)<ref>{{Cite web|url=https://www.jt60sa.org/b/index_nav_1.htm?n1/introduction.htm|title=The JT-60SA project|website=www.jt60sa.org}}</ref> || {{active|Operational}} || 2013–2020 || 2021– || {{flagicon|JP}} Naka || [[Japan Atomic Energy Research Institute]] || {{val|2.96|u=m}}/{{val|1.18|u=m}} || {{val|2.25|u=T}} || {{val|5.5|u=MA}} || Optimise plasma configurations for ITER and DEMO with full non-inductive steady-state operation || [[File:JT-60SA Tokamak (cropped2).jpg|frameless|154x154px|panorama of JT-60SA]]
|-
| {{Anchor|T-15MD}}[[T-15 (reactor)#Upgrade to T-15MD|T-15MD]] || {{active|Operational}} || 2010–2020 || 2021– || {{flagicon|RUS}} Moscow || [[Kurchatov Institute]] || {{val|1.48|u=m}}/{{val|0.67|u=m}} || {{val|2|u=T}} || {{val|2|u=MA}} || Hybrid fusion/fission reactor || [[File:T-15MD Toroidal winding and poloidal field coils.jpg|frameless|154x154px|T-15MD coil system]]
|-
| [[IGNITOR]]<ref>{{Cite web|url=http://www.frascati.enea.it/ignitor/|title=Ignited plasma in Tokamaks – The IGNITOR project|website=frascati.enea.it|archive-url=https://web.archive.org/web/20200419133100/http://www.frascati.enea.it/ignitor/|archive-date=2020-04-19}}</ref> || {{BLACK|Cancelled}} 2022<ref>{{Cite web |title=Ignitor, il progetto del reattore nucleare italiano, è stato chiuso - Panorama |url=https://www.panorama.it/tecnologia/ignitor-progetto-reattore-nucleare |access-date=2024-06-28 |website=www.panorama.it |language=it}}</ref> ||data-sort-value="2022"| - ||data-sort-value="2022"| - || {{flagicon|RUS}} Troitzk || [[ENEA (Italy)|ENEA]] || {{val|1.32|u=m}}/{{val|0.47|u=m}} || {{val|13|u=T}} || {{val|11|u=MA}} || Compact fusion reactor with self-sustained plasma and {{val|100|u=MW}} of planned fusion power || [http://www2.lns.mit.edu/ignitorproject/Ignitor@MIT/Fact_Sheet_files/Picture%204.jpg]
|-
|HongHuang 70<ref>{{Cite web |date=June 20, 2024 |title=Fusion technology breakthrough: China unveils first commercial "artificial sun" (photo) |url=https://tech.news.am/eng/news/3733/fusion-technology-breakthrough-china-unveils-first-commercial-%E2%80%9Cartificial-sun%E2%80%9D-photo.html |access-date=2024-06-22 |website=NEWS.am TECH - Innovations and science}}</ref>
|{{active|Operational}} ||2022–2024 ||2024 ||{{Flagicon|China}}Shanghai ||Energy Singularity || {{val|0.75|u=m}}/? || {{val|2.5|u=T}} || || REBCO High-temperature superconducting coils || [https://tech.news.am/static/content/Science/HH70%202.png]
|-
| [[SPARC (tokamak)|SPARC]]<ref>{{cite web |title=2023 Climate Tech Companies to Watch: Commonwealth and its compact tokamak |url=https://www.technologyreview.com/2023/10/04/1080113/2023-climate-tech-companies-commonwealth-compact-tokamak-carbon-free-electricity-fusion-reactor-electromagents/ |last=Harris |first=Mark |website=MIT Technology Review |date=October 4, 2023 |access-date=February 10, 2024}}</ref><ref name="ARC">{{cite web|url=http://www.psfc.mit.edu/sparc|title=SPARC at MIT Plasma Science and Fusion Center}}</ref><ref>{{Cite journal|last1=Creely|first1=A. J.|last2=Greenwald|first2=M. J.|last3=Ballinger|first3=S. B.|last4=Brunner|first4=D.|last5=Canik|first5=J.|last6=Doody|first6=J.|last7=Fülöp|first7=T.|last8=Garnier|first8=D. T.|last9=Granetz|first9=R.|last10=Gray|first10=T. K.|last11=Holland|first11=C.|date=2020|title=Overview of the SPARC tokamak|journal=Journal of Plasma Physics|language=en|volume=86|issue=5|doi=10.1017/S0022377820001257|bibcode=2020JPlPh..86e8602C|issn=0022-3778|doi-access=free|hdl=1721.1/136131|hdl-access=free}}</ref><ref>{{Cite web|last=Chesto|first=Jon|date=2021-03-03|title=MIT energy startup homes in on fusion, with plans for 47-acre site in Devens|url=https://www.bostonglobe.com/2021/03/03/business/mit-energy-startup-homes-fusion-with-plans-47-acre-site-devens/|access-date=2021-03-03|website=BostonGlobe.com|language=en-US}}</ref><ref>Verma, Pranshu. [https://www.washingtonpost.com/technology/2022/08/26/nuclear-fusion-technology-climate-change/ Nuclear fusion power inches closer to reality.] The Washington Post, August 26, 2022.</ref>|| {{partial|Under construction}} || 2021– || 2025? || {{flagicon|USA}} [[Devens, Massachusetts|Devens, MA]] || [[Commonwealth Fusion Systems]] and [[MIT Plasma Science and Fusion Center]]|| {{val|1.85|u=m}}/{{val|0.57|u=m}} || {{val|12.2|u=T}} || {{val|8.7|u=MA}} || Compact, high-field tokamak with [[Rare-earth barium copper oxide|ReBCO]] coils and {{val|100|u=MW}} planned fusion power || [[File:Sparc february 2018.jpg|frameless|154x154px|Artist's impression of SPARC]]
|-
| [[ITER]]<ref>{{Cite news|url=http://www.iter.org/|title=ITER – the way to new energy|work=ITER|language=en}}</ref> || {{partial|Under construction}} || 2013–2034? || 2034? || {{flagicon|FRA}} [[Cadarache]] || ITER Council || {{val|6.2|u=m}}/{{val|2.0|u=m}} || {{val|5.3|u=T}} || {{val|15|u=MA}} ? || Demonstrate feasibility of fusion on a power-plant scale with {{val|500|u=MW}} fusion power || [[File:ITER Exhibit (01810402) (12219071813) (cropped).jpg|frameless|154x154px|Small-scale model of ITER]]
|-
| [[Divertor Tokamak Test|DTT]] (Divertor Tokamak Test facility)<ref>{{Cite web|url=https://www.fsn-fusphy.enea.it/DTT/|title=The DTT Project|access-date=2020-02-21|archive-date=2019-03-30|archive-url=https://web.archive.org/web/20190330143339/https://www.fsn-fusphy.enea.it/DTT/|url-status=dead}}</ref><ref>{{Cite web |url=https://www.elettrotecnica.unina.it/files/albanese/upload/CERN2019_Albanese.pdf |title=The new Divertor Tokamak Test facility |access-date=2020-02-21 |archive-date=2020-02-21 |archive-url=https://web.archive.org/web/20200221125034/http://www.elettrotecnica.unina.it/files/albanese/upload/CERN2019_Albanese.pdf |url-status=dead }}</ref><ref>{{Cite web |last=Antonella |date=2024-06-12 |title=Divertor Tokamak Test facility Research Plan Version 1.0 |url=https://www.pubblicazioni.enea.it/le-pubblicazioni-enea/edizioni-enea/anno-2024/divertor-tokamak-test-facility-research-plan-version-1-0.html |access-date=2024-06-28 |website=www.pubblicazioni.enea.it |language=it-it}}</ref> || {{planned|Planned}} || 2022–2029? || 2029? || {{flagicon|ITA}} [[Frascati]] || [[ENEA (Italy)|ENEA]] || {{val|2.19|u=m}}/{{val|0.70|u=m}} || {{val|5.85|u=T}} ? || {{val|5.5|u=MA}} ? || Superconducting tokamak to study power exhaust || [https://www.iter.org/img/crop-575-85//www/content/com/Lists/Of%20Interest/Attachments/838/imagine_DTT.jpg]
|-
| SST-2 (Steady State Tokamak-2)<ref name="Srinivasan2016">{{cite journal|last1=Srinivasan|first1=R.|title=Design and analysis of SST-2 fusion reactor|journal=Fusion Engineering and Design|volume=112|year=2016|pages=240–243|issn=0920-3796|doi=10.1016/j.fusengdes.2015.12.044|bibcode=2016FusED.112..240S }}</ref> || {{planned|Planned}} ||  || 2027? || {{flagicon|IND}} Gujarat || [[Institute for Plasma Research]] || {{val|4.42|u=m}}/{{val|1.47|u=m}} || {{val|5.42|u=T}} || {{val|11.2|u=MA}} || Full-fledged fusion reactor with tritium breeding and up to 500 MW output ||
|-
| [[CFETR]] (China Fusion Engineering Test Reactor)<ref name="ZhuangLiLi2019">{{cite journal | last1 = Zhuang | first1 = G. | last2 = Li | first2 = G.Q. | last3 = Li | first3 = J. | last4 = Wan | first4 = Y.X. | last5 = Liu | first5 = Y. | last6 = Wang | first6 = X.L. | last7 = Song | first7 = Y.T. | last8 = Chan | first8 = V. | last9 = Yang | first9 = Q.W. | last10 = Wan | first10 = B.N. | last11 = Duan | first11 = X.R. | last12 = Fu | first12 = P. | last13 = Xiao | first13 = B.J. | title = Progress of the CFETR design | journal = Nuclear Fusion | date = 5 June 2019 | volume = 59 | issue = 11 | page = 112010 | issn = 0029-5515 | eissn = 1741-4326 | doi = 10.1088/1741-4326/ab0e27 | bibcode = 2019NucFu..59k2010Z | s2cid = 127585754 }}</ref> || {{planned|Planned}} || data-sort-value="2024"| ≥2024 || 2030? || {{flagicon|CHN}} || Institute of Plasma Physics, Chinese Academy of Sciences || {{val|7.2|u=m}}/{{val|2.2|u=m}} ? || {{val|6.5|u=T}} ? || {{val|14|u=MA}} ? || Bridge gaps between ITER and DEMO, planned fusion power {{val|1000|u=MW}} || [https://web.archive.org/web/20240415191822/https://www.neimagazine.com/uploads/newsarticle/7436879/images/501889/large/sketch%20cfetr.jpg]
|-
| ST-F1 (Spherical Tokamak - Fusion 1)<ref>{{cite web|url=https://www.madeherenow.com/news/post/2019/10/22/energy-innovator-reaches-for-the-stars|title=Energy innovator reaches for the stars }}</ref> || {{planned|Planned}} || 2027? || || {{flagicon|UK}} Didcot ||[[Tokamak Energy]] Ltd || {{val|1.4|u=m}}/{{val|0.8|u=m}} ? || {{val|4|u=T}} || {{val|5|u=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|Planned}} || 2026? || 2030? || {{flagicon|UK}} Culham ||[[Tokamak Energy]] Ltd ||  ||  ||  || Spherical tokamak capable of 15min-pulsed operation<ref>{{cite web |url=https://www.gov.uk/government/news/tokamak-energys-fusion-prototype-to-be-built-at-ukaeas-campus |title=Tokamak Energy's fusion prototype to be built at UKAEA's campus |date=2023-02-10 |work=gov.uk}}</ref><ref>{{cite web |url=https://tokamakenergy.com/2023/02/10/tokamak-energys-new-advanced-fusion-prototype-to-be-built-at-ukaeas-culham-campus/ |title=Tokamak Energy's new advanced fusion prototype to be built at UKAEA's Culham Campus |date=2023-02-10 |work=tokamakenergy.com}}</ref> || [https://i0.wp.com/asiatimes.com/wp-content/uploads/2023/11/Tokamak-Energy-copy.jpg?resize=1200%2C800&ssl=1]
|-
| ST-E1 || {{planned|Planned}} || 2030s? ||  || {{flagicon|UK}} Culham ||[[Tokamak Energy]] Ltd ||  ||  ||  || Spherical tokamak with {{val|200|u=MW}} planned net electric output<ref>{{cite news| url=https://world-nuclear-news.org/Articles/Tokamak-to-construct-demo-fusion-reactor-at-Culham |title=Tokamak to construct demo fusion reactor at Culham |date=2023-02-10 |work=World Nuclear News}}</ref> || [https://world-nuclear-news.org/BlankSiteASPX/media/WNNImported/mainimagelibrary/corporate%20branded/Tokamak-Energy-Power-Plant-3_730.jpg]
|-
| STEP ([[Spherical Tokamak for Energy Production]]) || {{planned|Planned}} || 2032-2040 || 2040 D-D<br/>Mid 2040s DT Campaign || {{flagicon|UK}} [[West Burton, Nottinghamshire]] || [[United Kingdom Atomic Energy Authority]]|| {{val|3|u=m}}/{{val|2|u=m}} ? || ? || {{val|16.5|u=MA}} ? || Spherical tokamak with {{val|100|u=MW}} planned electrical output<ref>{{Cite web |first=UKAEA |last=STEP |title=STEP Project Partner Slide Deck |url=https://step.ukaea.uk/step-supply-chain/ |access-date=2023-04-04 |website=STEP UKAEA Portal}}</ref> || [https://imechewebresources.blob.core.windows.net/imeche-web-content/images/default-source/default-album/step.png]
|-
|JA-DEMO
|{{Planned}}
|2030?
|2050?
|{{flagicon|JP}}
|?
|{{val|8.5|u=m}}/{{val|2.4|u=m}}<ref>{{Cite journal |last1=Tobita |first1=Kenji |last2=Hiwatari |first2=Ryoji |last3=Sakamoto |first3=Yoshiteru |last4=Someya |first4=Youji |last5=Asakura |first5=Nobuyuki |last6=Utoh |first6=Hiroyasu |last7=Miyoshi |first7=Yuya |last8=Tokunaga |first8=Shinsuke |last9=Homma |first9=Yuki |last10=Kakudate |first10=Satoshi |last11=Nakajima |first11=Noriyoshi |last12=for Fusion DEMO |first12=the Joint Special Design Team |date=2019-07-04 |title=Japan's Efforts to Develop the Concept of JA DEMO During the Past Decade |journal=Fusion Science and Technology |volume=75 |issue=5 |pages=372–383 |doi=10.1080/15361055.2019.1600931 |bibcode=2019FuST...75..372T |s2cid=164357381 |issn=1536-1055|doi-access=free }}</ref>
|{{val|5.94|u=T}}
|{{val|12.3|u=MA}}
|Prototype for development of Commercial Fusion Reactors {{val|1.5|-|2|u=GW}} Fusion output.<ref>{{Cite journal |last1=Iwai |first1=Yasunori |last2=Edao |first2=Yuki |last3=Kurata |first3=Rie |last4=Isobe |first4=Kanetsugu |date=2021-05-01 |title=Basic concept of JA DEMO fuel cycle |url=https://www.sciencedirect.com/science/article/pii/S0920379621000375 |journal=Fusion Engineering and Design |language=en |volume=166 |page=112261 |doi=10.1016/j.fusengdes.2021.112261 |bibcode=2021FusED.16612261I |s2cid=233566366 |issn=0920-3796}}</ref>
| [https://www.tandfonline.com/na101/home/literatum/publisher/tandf/journals/content/ufst20/2019/ufst20.v075.i05/15361055.2019.1600931/20190620/images/large/ufst_a_1600931_f0002_oc.jpeg]
|-
| [[K-DEMO]] (Korean fusion demonstration tokamak reactor)<ref>{{Cite journal|last1=Kim|first1=K.|last2=Im|first2=K.|last3=Kim|first3=H. C.|last4=Oh|first4=S.|last5=Park|first5=J. S.|last6=Kwon|first6=S.|last7=Lee|first7=Y. S.|last8=Yeom|first8=J. H.|last9=Lee|first9=C.|date=2015|title=Design concept of K-DEMO for near-term implementation|url=http://stacks.iop.org/0029-5515/55/i=5/a=053027|journal=Nuclear Fusion|language=en|volume=55|issue=5|page=053027|doi=10.1088/0029-5515/55/5/053027|issn=0029-5515|bibcode=2015NucFu..55e3027K|doi-access=free}}</ref> || {{planned|Planned}} || 2037? || || {{flagicon|KOR}} || [[National Fusion Research Institute]] || {{val|6.8|u=m}}/{{val|2.1|u=m}} || {{val|7|u=T}} || {{val|12|u=MA}} ? || Prototype for the development of commercial fusion reactors with around {{val|2200|u=MW}} of fusion power || [[File:K-DEMO device core design features.jpg|frameless|154x154px|Engineering drawing of planned KDEMO]]
|-
| [[DEMOnstration Power Station|DEMO]] (DEMOnstration Power Station) || {{planned|Planned}} || 2040? || 2050? || ? || || {{val|9|u=m}}/{{val|3|u=m}} ? || {{val|6|u=T}} ? || {{val|20|u=MA}} ? || Prototype for a commercial fusion reactor || [[File:EUROfusion schematic diagram of fusion power plant.jpg|frameless|154x154px|Artist's conception of DEMO]]
|}

==== Stellarator ====

{| class="wikitable sortable"
|-
! Device name !! Status !! Construction !! Operation !! Type !! Location !! Organisation !! Major/minor radius !! B-field !!  Purpose !! Image
|-
| Model A || {{no|Shut down}} || 1952–1953 || 1953–? || Figure-8 || {{flagicon|USA}} Princeton || [[Princeton Plasma Physics Laboratory]] || {{val|0.3|u=m}}/{{val|0.02|u=m}} || {{val|0.1|u=T}} || First stellarator, table-top device || [https://web.archive.org/web/20210831205948/https://www.pppl.gov/sites/pppl/files/styles/news_lightbox/public/article/highlighted-related-image/432006_10150854439869045_1450162217_n.jpg]
|-
| Model B || {{no|Shut down}} || 1953–1954 || 1954–1959 || Figure-8 || {{flagicon|USA}} Princeton || [[Princeton Plasma Physics Laboratory]] || {{val|0.3|u=m}}/{{val|0.02|u=m}} || {{val|5|u=T}} || Development of plasma diagnostics ||
|-
| Model B-1 || {{no|Shut down}} ||  || ?–1959 || Figure-8 || {{flagicon|USA}} Princeton || [[Princeton Plasma Physics Laboratory]] || {{val|0.25|u=m}}/{{val|0.02|u=m}} || {{val|5|u=T}} || Yielded {{val|1|u=MK}} plasma temperatures, showed cooling by X-ray radiation from impurities ||
|-
| Model B-2 || {{no|Shut down}} || || 1957 || Figure-8 || {{flagicon|USA}} Princeton || [[Princeton Plasma Physics Laboratory]] || {{val|0.3|u=m}}/{{val|0.02|u=m}} || {{val|5|u=T}} || Electron temperatures up to {{val|10|u=MK}} || [https://lynceans.org/wp-content/uploads/2017/08/1958-stellarator-model.png]
|-
| Model B-3 || {{no|Shut down}} || 1957 || 1958– || Figure-8 || {{flagicon|USA}} Princeton || [[Princeton Plasma Physics Laboratory]] || {{val|0.4|u=m}}/{{val|0.02|u=m}} || {{val|4|u=T}} || Last figure-8 device, confinement studies of ohmically heated plasma ||
|-
| Model B-64 || {{no|Shut down}} || 1955 || 1955 || Square || {{flagicon|USA}} Princeton || [[Princeton Plasma Physics Laboratory]] || ? m/{{val|0.05|u=m}} || {{val|1.8|u=T}} || ||
|-
| Model B-65 || {{no|Shut down}} || 1957 || 1957 || Racetrack || {{flagicon|USA}} Princeton || [[Princeton Plasma Physics Laboratory]] ||  || || || [https://live.staticflickr.com/7328/12859183985_7299c91062_o.jpg]
|-
| Model B-66 || {{no|Shut down}} || 1958 || 1958–? || Racetrack || {{flagicon|USA}} Princeton || [[Princeton Plasma Physics Laboratory]] ||  || || ||
|-
| Wendelstein 1-A || {{no|Shut down}} ||  || 1960 || Racetrack || {{flagicon|DEU}} Garching || [[Max-Planck-Institut für Plasmaphysik]] || {{val|0.35|u=m}}/{{val|0.02|u=m}} || {{val|2|u=T}} || ℓ=3 showed that stellarators can overcome Bohm diffusion, "Munich mystery" ||
|-
| Wendelstein 1-B || {{no|Shut down}} ||  || 1960 || Racetrack || {{flagicon|DEU}} Garching || [[Max-Planck-Institut für Plasmaphysik]] || {{val|0.35|u=m}}/{{val|0.02|u=m}} || {{val|2|u=T}} || ℓ=2 ||
|-
| {{Anchor|Model C}}[[Model C stellarator|Model C]] || {{CRecurring|Recycled}} →[[#ST|ST]] || 1957–1961 || 1961–1969 || Racetrack || {{flagicon|USA}} Princeton || [[Princeton Plasma Physics Laboratory]] || {{val|1.9|u=m}}/{{val|0.07|u=m}} || {{val|3.5|u=T}} || Suffered from large plasma losses by [[Bohm diffusion]] through "pump-out" ||
|-
| L-1 || {{no|Shut down}} || 1963 || 1963–1971 || round || {{flagicon|SOV}} Moscow || [[Lebedev Physical Institute]] || {{val|0.6|u=m}}/{{val|0.05|u=m}} || {{val|1|u=T}} || First Soviet stellarator, overcame Bohm diffusion ||
|-
| SIRIUS || {{no|Shut down}} ||  || 1964–? || Racetrack || {{flagicon|SOV}} [[Kharkiv]] || [[Kharkiv Institute of Physics and Technology]] (KIPT) ||  ||  ||  ||
|-
| TOR-1 || {{no|Shut down}} || 1967 || 1967–1973 ||  || {{flagicon|SOV}} Moscow || [[Lebedev Physical Institute]] || {{val|0.6|u=m}}/{{val|0.05|u=m}} || {{val|1|u=T}} || ||
|-
| TOR-2 || {{no|Shut down}} || ? || 1967–1973 ||  || {{flagicon|SOV}} Moscow || [[Lebedev Physical Institute]] || {{val|0.63|u=m}}/{{val|0.036|u=m}} || {{val|2.5|u=T}} || ||
|-
| Uragan-1 || {{no|Shut down}} || 1960–1967 || 1967–? || Racetrack || {{flagicon|SOV}} [[Kharkiv]] || [[Kharkiv Institute of Physics and Technology|National Science Center, Kharkiv Institute of Physics and Technology]] (NSC KIPT) || {{val|1.1|u=m}}/{{val|0.1|u=m}} || {{val|1|u=T}} || Overcame Bohm-diffusion by a factor of 30 ||
|-
| CLASP (Closed Line And Single Particle)<ref name="Lees1985">{{cite journal | last1 = Lees | first1 = D.J. | title = Culham stellarator programme, 1965–1980 | journal = Nuclear Fusion | date = 1 September 1985 | volume = 25 | issue = 9 | pages = 1259–1265 | issn = 0029-5515 | eissn = 1741-4326 | doi = 10.1088/0029-5515/25/9/044 | s2cid = 119660036 }}</ref> || {{no|Shut down}} || ? || 1967–? ||  || {{flagicon|UK}} Culham || [[United Kingdom Atomic Energy Authority]]|| {{val|0.3|u=m}}/{{val|0.056|u=m}} || {{val|0.1|u=T}} || Study confinement of electrons in a high-shear stellarator ||
|-
| TWIST<ref name="Lees1985"/> || {{no|Shut down}} || ? || 1967–? ||  || {{flagicon|UK}} Culham || [[United Kingdom Atomic Energy Authority]]|| {{val|0.32|u=m}}/{{val|0.045|u=m}} || {{val|0.3|u=T}} || Study turbulent heating ||
|-
| Proto-CLEO<ref name="Lees1985"/> || {{no|Shut down}} || ? || 1968–? || single-turn helical winding inside toroidal field conductors || {{flagicon|UK}} Culham,<br/>{{flagicon|USA}} Madison || [[United Kingdom Atomic Energy Authority]]|| {{val|0.4|u=m}}/{{val|0.05|u=m}} || {{val|0.5|u=T}} || confirmed plasma confinement times of neoclassical theory ||
|-
| TORSO<ref name="Lees1985"/> || {{no|Shut down}} || ? || 1972–? || data-sort-value="Torsatron"| Ultimate torsatron || {{flagicon|UK}} Culham || [[United Kingdom Atomic Energy Authority]]|| {{val|0.4|u=m}}/{{val|0.05|u=m}} || {{val|2|u=T}} || ||
|-
| CLEO<ref name="Lees1985"/> || {{no|Shut down}} || ? || 1974–? ||  || {{flagicon|UK}} Culham || [[United Kingdom Atomic Energy Authority]]|| {{val|0.9|u=m}}/{{val|0.125|u=m}} || {{val|2|u=T}} || Study of particle transport and beta limits, reached similar performance as tokamaks ||
|-
| Wendelstein 2-A || {{no|Shut down}} || 1965–1968 || 1968–1974 || Heliotron || {{flagicon|DEU}} Garching || [[Max-Planck-Institut für Plasmaphysik]] || {{val|0.5|u=m}}/{{val|0.05|u=m}} || {{val|0.6|u=T}} || Good plasma confinement || [[File:DMM 1988-643 Fusionsexperiment Wendelstein-IIa.jpg|frameless|154x154px|Wendelstein 2-A]]
|-
| Saturn<ref>{{cite journal | last1 = Georgiyevskiy | first1 = A. V. | last2 = Solodovchenko | first2 = S. I. | last3 = Voitsenya | first3 = V. S. | title = Contributions of the "Saturn" to Modern Stellarator-Torsatron Research | journal = Journal of Fusion Energy | date = 13 February 2010 | volume = 29 | issue = 4 | pages = 399–406 | issn = 0164-0313 | eissn = 1572-9591 | doi = 10.1007/s10894-010-9284-0 | bibcode = 2010JFuE...29..399G | s2cid = 123305093 }}</ref> || {{no|Shut down}} || 1970 || 1970–? || Torsatron || {{flagicon|SOV}} [[Kharkiv]] || [[Kharkiv Institute of Physics and Technology]] || {{val|0.36|u=m}}/{{val|0.08|u=m}} || {{val|1|u=T}} || first Torsatron, ℓ=3, m=8 field periods, base for several torsatrons at KIPT ||
|-
| Wendelstein 2-B || {{no|Shut down}} || ?–1970 || 1971–? || Heliotron || {{flagicon|DEU}} Garching || [[Max-Planck-Institut für Plasmaphysik]] || {{val|0.5|u=m}}/{{val|0.055|u=m}} || {{val|1.25|u=T}} || Demonstrated similar performance as tokamaks || [[File:W7x 026.jpg|frameless|154x154px|Wendelstein 2-B]]
|-
| Vint-20<ref>{{cite journal | last1 = Georgievskii | first1 = A. V. | last2 = Suprunenko | first2 = V. A. | last3 = Sukhomlin | first3 = E. A. | title = Vint-20 single-helix torsatron machine with three-dimensional magnetic axis | journal = Soviet Atomic Energy | date = May 1973 | volume = 34 | issue = 5 | pages = 518–519 | issn = 0038-531X | eissn = 1573-8205 | doi = 10.1007/BF01163768 | s2cid = 94405830 }}</ref> || {{no|Shut down}} || 1972 || 1973–? || Torsatron || {{flagicon|SOV}} [[Kharkiv]] || [[Kharkiv Institute of Physics and Technology]] || {{val|0.315|u=m}}/{{val|0.0725|u=m}} || {{val|1.8|u=T}} || single-pole ℓ=1, m=13 field periods ||
|-
| L-2 || {{no|Shut down}} || ? || 1975–? ||  || {{flagicon|SOV}} Moscow || [[Lebedev Physical Institute]] || {{val|1|u=m}}/{{val|0.11|u=m}} || {{val|2.0|u=T}} || ||
|-
| WEGA (Wendelstein Experiment in Greifswald für die Ausbildung) || {{CRecurring|Recycled}} →[[#HIDRA|HIDRA]] || 1972–1975 || 1975–2013 || Classical stellarator || {{flagicon|DEU}} Greifswald || [[Max-Planck-Institut für Plasmaphysik]] || {{val|0.72|u=m}}/{{val|0.15|u=m}} || {{val|1.4|u=T}} || Test lower hybrid heating || [[File:WEGA-Stuttgart.jpg|frameless|154x154px|WEGA]]
|-
| Wendelstein 7-A || {{no|Shut down}} || ? || 1975–1985 || Classical stellarator || {{flagicon|DEU}} Garching || [[Max-Planck-Institut für Plasmaphysik]] || {{val|2|u=m}}/{{val|0.1|u=m}} || {{val|3.5|u=T}} || First "pure" stellarator without plasma current, solved stellarator heating problem ||
|-
| Heliotron-E || {{no|Shut down}} || ? || 1980–? || Heliotron || {{flagicon|JP}} ||  || {{val|2.2|u=m}}/{{val|0.2|u=m}} || {{val|1.9|u=T}} || ||
|-
| Heliotron-DR || {{no|Shut down}} || ? || 1981–? || Heliotron || {{flagicon|JP}} ||  || {{val|0.9|u=m}}/{{val|0.07|u=m}} || {{val|0.6|u=T}} || ||
|-
| [[Uragan-3]] ({{Interlanguage link multi|Uragan-3M|uk|3=Ураган-3М|lt=M}})<ref name="auto">{{Cite web|url=http://www.kipt.kharkov.ua/en/bhr.html|title=History {{!}} ННЦ ХФТИ|website=kipt.kharkov.ua}}</ref> || {{active|Operational}} || ? || 1982–?<ref>{{Cite web|url=https://ipp.kipt.kharkov.ua/u3m/u3m_eng.html|title=Uragan-3M {{pipe}} IPP NSC KIPT|website=ipp.kipt.kharkov.ua}}</ref><br/>M: 1990– || Torsatron || {{flagicon|UKR}} [[Kharkiv]] || [[Kharkiv Institute of Physics and Technology|National Science Center, Kharkiv Institute of Physics and Technology]] (NSC KIPT) || {{val|1.0|u=m}}/{{val|0.12|u=m}} || {{val|1.3|u=T}} || ? ||
|-
| Auburn Torsatron (AT) || {{no|Shut down}} || ? || 1984–1990 || Torsatron || {{flagicon|USA}} Auburn || [[Auburn University]] || {{val|0.58|u=m}}/{{val|0.14|u=m}} || {{val|0.2|u=T}} || || [[File:Auburn Torsatron.jpg|frameless|154x154px|Auburn Torsatron]]
|-
| [[Wendelstein 7-AS]] || {{no|Shut down}} || 1982–1988 || 1988–2002 || Modular, advanced stellarator || {{flagicon|DEU}} Garching || [[Max-Planck-Institut für Plasmaphysik]] || {{val|2|u=m}}/{{val|0.13|u=m}} || {{val|2.6|u=T}} || First computer-optimized stellarator, first H-mode in a stellarator in 1992 || [[File:Garching Experiment Wendelstein 7-AS.jpg|frameless|154x154px|Wendelstein 7-AS]]
|-
| Advanced Toroidal Facility (ATF) || {{no|Shut down}} || 1984–1988<ref>{{Cite web|url=https://www.ornl.gov/content/ornl-review-v17n3|title=ORNL Review v17n3 1984.pdf {{pipe}} ORNL|website=www.ornl.gov}}</ref> || 1988–1994 || Torsatron || {{flagicon|USA}} Oak Ridge || [[Oak Ridge National Laboratory]] || {{val|2.1|u=m}}/{{val|0.27|u=m}} || {{val|2.0|u=T}} || First large American stellarator after Tokamak stampede, high-beta operation, >1h plasma operation || [[File:Advanced Toroidal Facility, 1986 (49743086486).png|frameless|154x154px|Advanced Toroidal Facility]]
|-
| Compact Helical System (CHS) || {{no|Shut down}} || ? || 1989–? || Heliotron || {{flagicon|JP}} Toki || [[National Institute for Fusion Science]] || {{val|1|u=m}}/{{val|0.2|u=m}} || {{val|1.5|u=T}} ||  ||
|-
| Compact Auburn Torsatron (CAT) || {{no|Shut down}} || ?–1990 || 1990–2000 || Torsatron || {{flagicon|USA}} Auburn || [[Auburn University]] || {{val|0.53|u=m}}/{{val|0.11|u=m}} || {{val|0.1|u=T}} || Study magnetic flux surfaces || [[File:CATphoto2.jpg|frameless|154x154px|Compact Auburn Torsatron]]
|-
| [[H-1NF|H-1]] (Heliac-1)<ref>{{Cite web|url=http://prl.anu.edu.au/H-1NF|title=Plasma Research Laboratory – PRL – ANU|last1=Department|first1=Head of|last2=prl@physics.anu.edu.au|website=prl.anu.edu.au|language=en|access-date=2005-12-26|archive-date=2010-02-13|archive-url=https://web.archive.org/web/20100213172059/http://prl.anu.edu.au/H-1NF|url-status=dead}}</ref> || {{active|Operational}} ||  || 1992– || Heliac || {{flagicon|AUS}} [[Canberra]],<br/>{{flagicon|CHN}} || [[Research School of Physical Sciences and Engineering]], [[Australian National University]] || {{val|1.0|u=m}}/{{val|0.19|u=m}} || {{val|0.5|u=T}} || shipped to China in 2017 || [[File:H1 Heliac.jpg|frameless|154x154px|H-1NF plasma vessel]]
|-
| [[TJ-K]] (Tokamak de la Junta Kiel)<ref>{{Cite web|url=http://fusionwiki.ciemat.es/wiki/TJ-K|title=TJ-K – FusionWiki|website=fusionwiki.ciemat.es|language=en}}</ref> || {{active|Operational}} || TJ-IU (1999) || 1994– || Torsatron || {{flagicon|DEU}} Kiel, Stuttgart || [[University of Stuttgart]] || {{val|0.60|u=m}}/{{val|0.10|u=m}} || {{val|0.5|u=T}} || One helical and two vertical coil sets; Teaching; moved from Kiel to Stuttgart in 2005 ||
|-
| [[TJ-II]] (Tokamak de la Junta II)<ref>{{Cite web|url=http://www.ciemat.es|title=Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas|last=CIEMAT|website=ciemat.es|language=es}}</ref> || {{active|Operational}} || 1991–1996 || 1997– || flexible Heliac || {{flagicon|ESP}} Madrid || National Fusion Laboratory, [[Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas]] || {{val|1.5|u=m}}/{{val|0.28|u=m}} || {{val|1.2|u=T}} || Study plasma in flexible configuration || [[File:TJ-II model including plasma, coils and vacuum vessel.jpg|frameless|154x154px|CAD drawing of TJ-II]]
|-
| [[Large Helical Device|LHD]] (Large Helical Device)<ref>{{Cite web|url=http://www.lhd.nifs.ac.jp/en/home/lhd.html|title=Large Helical Device Project|website=lhd.nifs.ac.jp|access-date=2006-04-20|archive-url=https://web.archive.org/web/20100412200938/http://www.lhd.nifs.ac.jp/en/home/lhd.html|archive-date=2010-04-12}}</ref> || {{active|Operational}} || 1990–1998 || 1998– || Heliotron || {{flagicon|JP}} Toki || [[National Institute for Fusion Science]] || {{val|3.5|u=m}}/{{val|0.6|u=m}} || {{val|3|u=T}}|| Demonstrated long-term operation of large superconducting coils || [[File:LHD Querschnitt.png|frameless|154x154px|LHD cross section]]
|-
| [[Helically Symmetric Experiment|HSX]] (Helically Symmetric Experiment)<ref>{{Cite web|url=https://hsx.wisc.edu/|title=HSX – Helically Symmetric eXperiment|website=hsx.wisc.edu}}</ref> || {{active|Operational}} ||  || 1999– || Modular, quasi-helically symmetric || {{flagicon|USA}} Madison || [[University of Wisconsin–Madison]] || {{val|1.2|u=m}}/{{val|0.15|u=m}} || {{val|1|u=T}} || Investigate plasma transport in quasi-helically-symmetric field, similar to tokamaks || [[File:HSX picture.jpg|frameless|154x154px|HSX with clearly visible non-planar coils]]
|-
| [[Heliotron J]]<ref>{{Cite web|url=http://www.iae.kyoto-u.ac.jp/en/joint/heliotron-j.html|title=Heliotron J Project|website=iae.kyoto-u.ac.jp/en/joint/heliotron-j.html}}</ref> || {{active|Operational}} ||  || 2000– || Heliotron || {{flagicon|JP}} Kyoto || [[Institute of Advanced Energy]] || {{val|1.2|u=m}}/{{val|0.1|u=m}} || {{val|1.5|u=T}} || Study helical-axis heliotron configuration || [http://www.iae.kyoto-u.ac.jp/center/equipment/images/image01l.jpg]
|-
| [[Columbia Non-neutral Torus]] (CNT) || {{active|Operational}} || ? || 2004– || Circular interlocked coils || {{flagicon|USA}} New York City || [[Columbia University]] || {{val|0.3|u=m}}/{{val|0.1|u=m}} || {{val|0.2|u=T}} || Study of non-neutral (mostly electron) plasmas ||
|-
| [[Uragan-2]]([[Uragan-2M|M]])<ref name="auto"/> || {{active|Operational}} || 1988–2006 || 2006–<ref>{{Cite web|url=https://ipp.kipt.kharkov.ua/u2m/u2m_en.html|title=Uragan-2M {{pipe}} IPP NSC KIPT|website=ipp.kipt.kharkov.ua}}</ref> || Heliotron, Torsatron || {{flagicon|UKR}} [[Kharkiv]] || [[Kharkiv Institute of Physics and Technology|National Science Center, Kharkiv Institute of Physics and Technology]] (NSC KIPT) || {{val|1.7|u=m}}/{{val|0.22|u=m}} || {{val|2.4|u=T}} || ℓ=2 Torsatron || [https://ipp.kipt.kharkov.ua/img/u2m/u2m_2.jpg]
|-
| Quasi-poloidal stellarator (QPS)<ref>{{cite web | url=http://web.utk.edu/~qps/ | title=QPS Home Page | access-date=2018-09-01 | archive-date=2016-04-24 | archive-url=https://web.archive.org/web/20160424174351/http://web.utk.edu/~qps/ | url-status=dead }}</ref><ref>[https://web.archive.org/web/20041019073850/http://qps.fed.ornl.gov/pvr/pdf/qpsentire.pdf http://qps.fed.ornl.gov/pvr/pdf/qpsentire.pdf]</ref> || {{BLACK|Cancelled}} || 2001–2007 || – || Modular || {{flagicon|USA}} Oak Ridge || [[Oak Ridge National Laboratory]] || {{val|0.9|u=m}}/{{val|0.33|u=m}} || {{val|1.0|u=T}} || Stellarator research || [[File:Quasi-Poloidal Stellarator 3d render.jpg|frameless|154x154px|Engineering drawing of the QPS]]
|-
| [[National Compact Stellarator Experiment|NCSX]] (National Compact Stellarator Experiment) || {{BLACK|Cancelled}} || 2004–2008 || – || Helias || {{flagicon|USA}} Princeton || [[Princeton Plasma Physics Laboratory]] || {{val|1.4|u=m}}/{{val|0.32|u=m}} || {{val|1.7|u=T}} || High-β stability || [[File:NCSXmachine.jpg|frameless|154x154px|CAD drawing of NCSX]]
|-
| Compact Toroidal Hybrid (CTH) || {{active|Operational}} || ? || 2007?– || Torsatron || {{flagicon|USA}} Auburn || [[Auburn University]] || {{val|0.75|u=m}}/{{val|0.2|u=m}} || {{val|0.7|u=T}} || Hybrid stellarator/tokamak || [[File:Compact Toroidal Hybrid at Auburn University.jpg|frameless|154x154px|CTH]]
|-
| {{Anchor|HIDRA}}[[Hybrid Illinois Device for Research and Applications|HIDRA]] (Hybrid Illinois Device for Research and Applications)<ref>{{Cite web|url=http://cpmi.illinois.edu/2016/04/26/hidra-hybrid-illinois-device-for-research-and-applications/|title=HIDRA – Hybrid Illinois Device for Research and Applications {{!}} CPMI – Illinois|website=cpmi.illinois.edu|language=en-US}}</ref> || {{active|Operational}} || 2013–2014 (WEGA) || 2014– || ? || {{flagicon|USA}} [[Urbana, Illinois|Urbana]], IL || [[University of Illinois at Urbana – Champaign|University of Illinois]] || {{val|0.72|u=m}}/{{val|0.19|u=m}} || {{val|0.5|u=T}} || Stellarator and tokamak in one device, capable of long pulse steady-state operation; study plasma-wall interactions || [[File:HIDRA.jpg|frameless|154x154px|HIDRA after its reassembly in Illinois]]
|-
| UST_2<ref>{{Cite web|url=http://www.fusionvic.org/index_UST_2.shtml|title=Vying Fusion Energy - V. Queral|website=www.fusionvic.org}}</ref> || {{active|Operational}} || 2013 || 2014– || modular three period quasi-isodynamic || {{flagicon|ESP}} [[Madrid]] || [[Charles III University of Madrid]] || {{val|0.29|u=m}}/{{val|0.04|u=m}} || {{val|0.089|u=T}} || [[3D printing|3D-printed]] stellarator || [[File:UST 2 stellarator concept and design.jpg|frameless|154x154px|UST_2 design concept]]
|-
| [[Wendelstein 7-X]]<ref>{{Cite web|url=http://www.ipp.mpg.de/w7x|title=Wendelstein 7-X|website=ipp.mpg.de/w7x}}</ref> || {{active|Operational}} || 1996–2022 || 2015– || Helias || {{flagicon|DEU}} Greifswald || [[Max-Planck-Institut für Plasmaphysik]] || {{val|5.5|u=m}}/{{val|0.53|u=m}} || {{val|3|u=T}} || Steady-state plasma in large fully optimized stellarator || [[File:Schematic diagram of Wendelstein 7-X.jpg|frameless|154x154px|Schematic diagram of Wendelstein 7-X]]
|-
| [[SCR-1]] (Stellarator of Costa Rica) || {{active|Operational}} || 2011–2015 || 2016– || Modular || {{flagicon|CRI}} Cartago || [[Costa Rica Institute of Technology]] || {{val|0.14|u=m}}/{{val|0.042|u=m}} || {{val|0.044|u=T}} ||  || [[File:SCR-1 vacuum vessel drawing.jpg|frameless|154x154px|SCR-1 vacuum vessel drawing]]
|-
|MUSE<ref>{{cite journal |title=Design and construction of the MUSE permanent magnet stellarator |journal=Journal of Plasma Physics |volume=89 |issue=5 |page=955890502 |doi=10.1017/S0022377823000880 |date=2023-10-31 |author=T.M. Qian, X. Chu, C. Pagano, D. Patch, M.C. Zarnstorff, B. Berlinger, D. Bishop, A. Chambliss, M. Haque, D. Seidita, C. Zhu|bibcode=2023JPlPh..89e9502Q |doi-access=free }}</ref>
|{{active|Operational}}
|2022–2023
|2023–
|Quasiaxi-symmetrical
|{{flagicon|USA}} Princeton
|[[Princeton Plasma Physics Laboratory]]
|{{val|0.3|u=m}}/{{val|0.075|u=m}}
|{{val|0.15|u=T}}
|First stellarator with permanent magnets
|[[File:Design and construction of the MUSE permanent magnet stellarator - Fig21 (cropped).jpg|frameless|154x154px|MUSE]]
|-
|CFQS (Chinese First Quasi-Axisymmetric Stellarator)<ref>{{Cite journal|last1=KINOSHITA|first1=Shigeyoshi|last2=SHIMIZU|first2=Akihiro|last3=OKAMURA|first3=Shoichi|last4=ISOBE|first4=Mitsutaka|last5=XIONG|first5=Guozhen|last6=LIU|first6=Haifeng|last7=XU|first7=Yuhong|last8=The CQFS Team|date=2019-06-03|title=Engineering Design of the Chinese First Quasi-Axisymmetric Stellarator (CFQS)|journal=Plasma and Fusion Research|volume=14|pages=3405097 |doi=10.1585/pfr.14.3405097|bibcode=2019PFR....1405097K|issn=1880-6821|doi-access=free}}</ref>
|{{partial|Under construction}}
|2017– 
|
|Helias
|{{flagicon|CHN}} Chengdu
|Southwest Jiaotong University, National Institute for Fusion Science in Japan
|{{val|1|u=m}}/{{val|0.25|u=m}}
|{{val|1|u=T}}
|m=2 quasi-axisymmetric stellarator, modular
| [[File:CFQS coils Bfield Su2020.jpg|frameless|154x154px|CFQS coils and field]]
|-
|EFPP (European Fusion Power Plant)<ref>{{Cite web|url=https://www.filo.kit.edu/downloads/Forum%20FUSION%20Dtl/Event_FFD_081222/Presentationen/6-Gauss%20Fusion%20Initiative-Introduction%202.pdf|title=Introduction to the Gauss Fusion Initiative|date=2022-12-08}}</ref>
|{{planned|Planned}}
|2030 ?
|2045 ?
|Helias
|{{flagicon|DEU}}
|Gauss Fusion
|
|7–{{val|9|u=T}} ?
|Fusion power plant with 2–{{val|3|u=GW}} output
| 
|}

==== [[Magnetic mirror]] ====
* Tabletop/Toytop, [[Lawrence Livermore National Laboratory]], Livermore CA.
* DCX/DCX-2, [[Oak Ridge National Laboratory]]
* OGRA (Odin GRAm neitronov v sutki, one gram of neutrons per day), Akademgorodok, Russia. A 20-meter-long pipe
* Baseball I/Baseball II [[Lawrence Livermore National Laboratory]], Livermore CA.
* 2X/2XIII/2XIII-B, [[Lawrence Livermore National Laboratory]], Livermore CA.
* [[Tandem Mirror Experiment|TMX, TMX-U]] [[Lawrence Livermore National Laboratory]], Livermore CA.
* [[Mirror Fusion Test Facility|MFTF]] [[Lawrence Livermore National Laboratory]], Livermore CA.
* [[Gas Dynamic Trap]] at [[Budker Institute of Nuclear Physics]], Akademgorodok, Russia.

==== Toroidal [[Z-pinch]] ====
* [[Perhapsatron]] (1953, USA)
* [[ZETA (fusion reactor)|ZETA]] (Zero Energy Thermonuclear Assembly) (1957, United Kingdom)

==== Reversed field pinch (RFP) ====
* ETA-BETA II in Padua, Italy (1979–1989)
* [[Reversed-Field eXperiment|RFX]] (Reversed-Field eXperiment), Consorzio RFX, Padova, Italy<ref>{{Cite web|url=http://www.igi.cnr.it/|title=CONSORZIO RFX – Ricerca Formazione Innovazione|website=igi.cnr.it|access-date=2018-04-16|archive-url=https://web.archive.org/web/20090901010034/http://www.igi.cnr.it/|archive-date=2009-09-01}}</ref>
* [[Madison Symmetric Torus|MST]] (Madison Symmetric Torus), [[University of Wisconsin–Madison]], United States<ref>{{Cite web|url=http://plasma.physics.wisc.edu/viewpage.php?id=mst|title=MST – UW Plasma Physics|last=Hartog|first=Peter Den|website=plasma.physics.wisc.edu|access-date=2013-02-28|archive-date=2019-03-13|archive-url=https://web.archive.org/web/20190313201537/http://plasma.physics.wisc.edu/viewpage.php?id=mst|url-status=dead}}</ref>
* T2R, [[Royal Institute of Technology]], Stockholm, Sweden
* TPE-RX, [[National Institute of Advanced Industrial Science and Technology|AIST]], Tsukuba, Japan
* KTX (Keda Torus eXperiment) in China (since 2015)<ref name="LiuLan2017">{{cite journal|last1=Liu|first1=Wandong|last2=et|first2=al.|title=Overview of Keda Torus eXperiment initial results|journal=Nuclear Fusion|volume=57|issue=11|year=2017|page=116038|issn=0029-5515|doi=10.1088/1741-4326/aa7f21|bibcode=2017NucFu..57k6038L|s2cid=116431906 }}</ref>

==== [[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

==== Other toroidal machines ====
* TMP (''Tor s Magnitnym Polem'', torus with magnetic field): A porcelain torus with major radius {{val|80|u=cm}}, minor radius {{val|13|u=cm}}, toroidal field of {{val|1.5|u=T}} and plasma current {{val|0.25|u=MA}}, predecessor to the first tokamak (1955, USSR)

=== Open field lines ===

==== [[Pinch (plasma physics)|Plasma pinch]] ====
* [[Trisops]] – 2 facing theta-pinch guns
* FF-2B, [[Lawrenceville Plasma Physics]], United States<ref>{{Cite web|url=https://lppfusion.com/wp-content/uploads/2021/10/LPPFusion%20Report%20Oct.15,%202021.pdf|archive-url=https://web.archive.org/web/20211025065311/https://lppfusion.com/wp-content/uploads/2021/10/LPPFusion%20Report%20Oct.15,%202021.pdf|url-status=live|archive-date=2021-10-25|title=Report Oct 15, 2021|date=2021-10-15}}</ref>

==== [[Levitated dipole]] ====
* [[Levitated Dipole Experiment]] (LDX), MIT/[[Columbia University]], United States<ref>{{Cite web|url=http://www.psfc.mit.edu/ldx/|archive-url=https://web.archive.org/web/20040823034735/http://www.psfc.mit.edu/ldx/|archive-date=2004-08-23|title=Levitated Dipole Experiment|date=2004-08-23}}</ref>

== Inertial confinement ==
{{Main|Inertial confinement fusion}}

=== Laser-driven ===

{| class="wikitable sortable"
|-
! Device name !! Status !!width=55| Construction !!width=55| Operation !! Description !! Peak laser power !! Pulse energy !! Fusion yield !! width=110| Location !! Organisation !! Image
|-
| [[4 pi laser]] || {{no|Shut down}} || 196? || || Semiconductor laser || {{val|5|u=GW}} || {{val|12|u=J}} || || {{flagicon|USA}} [[Livermore, California|Livermore]] || [[LLNL]] || [https://web.archive.org/web/20041109063546im_/http://www.llnl.gov/50science/lasers_images/50th2.jpg]
|-
| [[Long path laser]] || {{no|Shut down}} || 1972 || 1972 || First ICF laser with neodymium doped glass (Nd:glass) as lasing medium || {{val|5|u=GW}} || {{val|50|u=J}} || || {{flagicon|USA}} [[Livermore, California|Livermore]] || [[LLNL]] || [https://www.lle.rochester.edu/wp-content/uploads/2019/02/38mmRodAmplifier.jpg]
|-
| Single Beam System (SBS) "67" || {{no|Shut down}} || 1971-1973 || 1973 || Single-beam [[Carbon-dioxide laser|CO<sub>2</sub> laser]]<ref>{{cite web|url=http://library.sciencemadness.org/lanl2_a/lib-www/la-pubs/00322724.pdf|title=Los Alamos Laser Fusion Program|date=July 1967|author=F Skoberne}}</ref> || {{val|200|u=GW}} || {{val|1|u=kJ}} || || {{flagicon|USA}} [[Los Alamos, New Mexico|Los Alamos]] || [[LANL]] || 
|-
| Double Bounce Illumination System (DBIS) || {{no|Shut down}} || 1972-1974 || 1974-1990 || First private laser fusion effort, YAG laser, neutron yield {{val|e=4}} to {{val|3|e=5}} neutrons || || {{val|1|u=kJ}} || data-sort-value="{{val|100|u=nJ}}"| ≈{{val|100|u=nJ}} || {{flagicon|USA}} [[Ann Arbor, Michigan]] || [[KMS Fusion]] || [[File:Double Bounce System KMS Fusion 1974.png|frameless|154x154px]]
|-
| MERLIN (Medium Energy Rod Laser Incorporating Neodymium), N78 laser || {{no|Shut down}} || 1972-1975 || 1975-? || Nd:glass laser || {{val|100|u=GW}} || {{val|40|u=J}} || || {{flagicon|UK}} [[RAF Aldermaston]] || [[Atomic Weapons Establishment|AWE]] || [[File:MERLIN target chamber.jpg|frameless|154x154px]]
|-
| [[Cyclops laser]] || {{no|Shut down}} || 1975 || 1975 || Single-beam Nd:glass laser, prototype for [[#Shiva|Shiva]]<ref>{{cite web|url=https://lasers.llnl.gov/multimedia/publications/pdfs/etr/1976_02_3.pdf|title=Beam-propagation studies on Cyclops|date=February 1976}}</ref> || {{val|1|u=TW}} || {{val|270|u=J}} || || {{flagicon|USA}} [[Livermore, California|Livermore]] || [[LLNL]] || [[File:Cyclops laser 1975.jpg|frameless|154x154px]]
|-
| [[Janus laser]] || {{no|Shut down}} || 1974-1975 || 1975 || Two-beam Nd:glass laser demonstrated laser compression and thermonuclear burn of deuterium–tritium || {{val|1|u=TW}} || {{val|10|u=J}} || || {{flagicon|USA}} [[Livermore, California|Livermore]] || [[LLNL]] || [[File:Janus laser 1975.jpg|frameless|154x154px]]
|-
| [[Gemini laser]], Dual-Beam Module (DBM) || {{no|Shut down}} || ≤ 1975 || 1976 || Two-beam [[Carbon-dioxide laser|CO<sub>2</sub> laser]], tests for [[#Helios|Helios]] || {{val|5|u=TW}} || {{val|2.5|u=kJ}} || || {{flagicon|USA}} [[Los Alamos, New Mexico|Los Alamos]] || [[LANL]] || 
|-
| [[Argus laser]] || {{no|Shut down}} || 1976 || 1976-1981 || Two-beam Nd:glass laser, advanced the study of laser-target interaction and paved the way for [[#Shiva|Shiva]] || {{val|4|u=TW}} || {{val|2|u=kJ}} || data-sort-value="{{val|3|u=mJ}}"| ≈{{val|3|u=mJ}} || {{flagicon|USA}} [[Livermore, California|Livermore]] || [[LLNL]] || [[File:Argus_laser_1976.jpg|frameless|154x154px]]
|-
| [[Vulcan laser]] (Versicolor Ultima Lux Coherens pro Academica Nostra)<ref name="DansonWhiteBarr2021">{{cite journal | last1 = Danson | first1 = Colin N. | display-authors=etal | title = A history of high-power laser research and development in the United Kingdom | journal = High Power Laser Science and Engineering | date = 2021 | volume = 9 | issn = 2095-4719 | eissn = 2052-3289 | doi = 10.1017/hpl.2021.5 | bibcode = 2021HPLSE...9E..18D | s2cid = 233401354 | doi-access = free | hdl = 10044/1/89337 | hdl-access = free }}</ref> || {{active|Operational}} || 1976-1977 || 1977- || 8-beam Nd:glass laser, highest-intensity focussed laser in the world in 2005<ref>{{cite web | url=https://www.clf.stfc.ac.uk/Pages/Meet-the-CLF-lasers.aspx | title=CLF Get to know the CLF Lasers }}</ref> || {{val|1|u=PW}} || {{val|2.6|u=kJ}} || || {{flagicon|UK}} [[Didcot]] || [[Rutherford Appleton Laboratory|RAL]] || [[File:Green Lase.JPG|frameless|154x154px]]
|-
| {{Anchor|Shiva}}[[Shiva laser]] || {{no|Shut down}} || 1977 || 1977-1981 || 20-beam Nd:glass laser; proof-of-concept for Nova; fusion yield of 10<sup>11</sup> neutrons; found that its infrared wavelength of 1062&nbsp;nm was too long to achieve ignition || {{val|30|u=TW}} || {{val|10.2|u=kJ}} || data-sort-value="{{val|0.1|u=J}}"| ≈{{val|0.1|u=J}} || {{flagicon|USA}} [[Livermore, California|Livermore]] || [[LLNL]] || [[File:Shiva laser target chamber.jpg|frameless|154x154px]]
|-
| {{Anchor|Helios}}[[Helios laser]], Eight-Beam System (EBS) || {{no|Shut down}} || 1975-1978 || 1978 || 8-beam [[Carbon-dioxide laser|CO<sub>2</sub> laser]]; [[:commons:Category:Helios laser, Los Alamos National Laboratory|Media]] at Wikimedia Commons || {{val|20|u=TW}} || {{val|10|u=kJ}} || || {{flagicon|USA}} [[Los Alamos, New Mexico|Los Alamos]] || [[LANL]] || [[File:U.S. Department of Energy - Science - 282 005 003 (16388751641).jpg|frameless|154x154px]]
|-
| HELEN (High Energy Laser Embodying Neodymium) || {{no|Shut down}} || 1976-1979 || 1979-2009 || Two-beam Nd:glass laser || {{val|1|u=TW}} || {{val|200|u=J}} || || {{flagicon|UK}} [[Didcot]] || [[Rutherford Appleton Laboratory|RAL]] || [[File:HELEN laser.jpg|frameless|154x154px]]
|-
| [[ISKRA-4]] || {{active|Operational}} || -1979 || 1979- || 8-beam iodine gas laser, prototype for [[#ISKRA-5|ISKRA-5]]<ref name="vniief">{{Cite web|url=http://www.vniief.ru/science/laserphysics_1_e.html|archive-url=https://web.archive.org/web/20050406140306/http://www.vniief.ru/science/laserphysics_1_e.html|archive-date=2005-04-06|title=RFNC-VNIIEF – Science – Laser physics|date=2005-04-06}}</ref> || {{val|10|u=TW}} || {{val|2|u=kJ}} || {{val|6|u=mJ}} || {{flagicon|SOV}} [[Sarov]] || [[RFNC-VNIIEF]] || 
|-
| [[Sprite laser]]<ref name="DansonWhiteBarr2021"/> || {{no|Shut down}} || 1981-1983 || 1983-1995 || First high-power [[Krypton fluoride laser]] used for target irradiation, λ={{val|249|u=nm}} || {{val|1|u=TW}} || {{val|7.5|u=J}} || || {{flagicon|UK}} [[Didcot]] || [[Rutherford Appleton Laboratory|RAL]] || [[File:Sprite e-beam pumped amplifier cell 1982.jpg|frameless|154x154px]]
|-
| [[Gekko XII laser|Gekko XII]] || {{active|Operational}} ||  || 1983- || 12-beam, Nd:glass laser || {{val|500|u=TW}} || {{val|10|u=kJ}} || || {{flagicon|JP}} [[Osaka]] || Institute for Laser Engineering || 
|-
| [[Novette laser]] || {{no|Shut down}} || 1981-1983 || 1983-1984 || Nd:glass laser to validate the [[#Nova|Nova]] design, first X-ray laser<ref name="Springer US1984">{{cite book | title = Laser Interaction and Related Plasma Phenomena | date = 1984 | publisher = Springer US | doi = 10.1007/978-1-4615-7332-6 | isbn = 978-1-4615-7334-0 | editor-last1 = Hora | editor-last2 = Miley | editor-first1 = Heinrich | editor-first2 = George H }}</ref> || {{val|13|u=TW}} || {{val|18|u=kJ}} || || {{flagicon|USA}}[[Livermore, California|Livermore]] || [[LLNL]] || [[File:U.S. Department of Energy - Science - 281 004 001 (16315143010).jpg|frameless|154x154px]]
|-
| [[Antares laser]], High Energy Gas Laser Facility (HEGLF) || {{no|Shut down}} || || 1983<ref>{{cite journal | url=https://physicstoday.scitation.org/doi/10.1063/1.2916397 | doi=10.1063/1.2916397 | title=Fusion experiments have begun at Antares | journal=Physics Today | year=1984 | volume=37 | issue=9 | page=19 | bibcode=1984PhT....37i..19S | last1=Schwarzschild | first1=Bertram M. }}</ref> || 24-beam largest [[Carbon-dioxide laser|CO<sub>2</sub> laser]] ever built. Missed goal of scientific fusion breakeven, because production of hot electrons in target plasma due to long 10.6&nbsp;μm wavelength of laser resulted in poor laser/plasma energy coupling<ref name="Springer US1984"/> || {{val|200|u=TW}} || {{val|40|u=kJ}} || || {{flagicon|USA}} [[Los Alamos, New Mexico|Los Alamos]] || [[LANL]] || 
|-
| [[PHAROS laser]] || {{active|Operational}} || 198? || || Two-beam Nd:glass laser || {{val|300|u=GW}} || {{val|1|u=kJ}} || || {{flagicon|USA}} [[Washington D.C.]] || [[United States Naval Research Laboratory|NRL]] || 
|-
| {{Anchor|Nova}}[[Nova laser]] || {{no|Shut down}} ||  || 1984-1999 || 10-beam NIR and frequency-tripled 351&nbsp;nm UV laser; fusion yield of 10<sup>13</sup> neutrons; attempted ignition, but failed due to fluid instability of targets; led to construction of [[#NIF|NIF]] || {{val|1.3|u=PW}} || {{val|120|u=kJ}} || {{val|30|u=J}} || {{flagicon|USA}}[[Livermore, California|Livermore]] || [[LLNL]] || 
|-
| {{Anchor|ISKRA-5}}[[ISKRA-5]] || {{active|Operational}} || -1989 || || 12-beam iodine gas laser, fusion yield 10<sup>10</sup> to 10<sup>11</sup> neutrons<ref name="vniief"/> || {{val|100|u=TW}} || {{val|30|u=kJ}} || {{val|0.3|u=J}} || {{flagicon|SOV}} [[Sarov]] || [[RFNC-VNIIEF]] || 
|-
| [[Aurora laser]] || {{no|Shut down}} || ≤ 1988-1989 || 1990 || 96-beam [[Krypton fluoride laser]] || data-sort-value="{{val|300|u=GW}}"| ≈{{val|300|u=GW}} || {{val|1.3|u=kJ}} || || {{flagicon|USA}} [[Los Alamos, New Mexico|Los Alamos]] || [[LANL]] || 
|-
| [[Prague Asterix Laser System|PALS]], formerly "Asterix IV" || {{active|Operational}} || -1991 || 1991- || [[All gas-phase iodine laser|Iodine gas laser]], λ={{val|1315|u=nm}} || {{val|3|u=TW}} || {{val|1|u=kJ}} || || {{flagicon|DEU}} [[Garching]],<br/>{{flagicon|CZE}} [[Prague]] || [[Max Planck Institute of Quantum Optics|MPQ]], [[Czech Academy of Sciences|CAS]]  || [[File:Prague asterix laser system.jpeg|frameless|154x154px]]
|-
| [[Trident laser]] || {{active|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 || {{val|200|u=TW}} || {{val|500|u=J}} || || {{flagicon|USA}} [[Los Alamos, New Mexico|Los Alamos]] || [[LANL]] || [[File:Alfoil.jpg|frameless|154x154px]]
|-
| [[Nike laser]] || {{active|Operational}} || ≤ 1991-1994 || 1994- || 56-beam, most-capable [[Krypton fluoride laser]] for laser target interactions<ref name="LeheckaBodnerDeniz1991">{{cite journal | last1 = Lehecka | first1 = T. | last2 = Bodner | first2 = S. | last3 = Deniz | first3 = A. V. | last4 = Mostovych | first4 = A. N. | last5 = Obenschain | first5 = S. P. | last6 = Pawley | first6 = C. J. | last7 = Pronko | first7 = M. S. | title = The NIKE KrF laser fusion facility | journal = Journal of Fusion Energy | date = December 1991 | volume = 10 | issue = 4 | pages = 301–303 | issn = 0164-0313 | eissn = 1572-9591 | doi = 10.1007/BF01052128 | bibcode = 1991JFuE...10..301L | s2cid = 122087249 }}</ref><ref name="ObenschainLehmbergKehne2015">{{cite journal | display-authors=etal | last1 = Obenschain | first1 = Stephen | last2 = Lehmberg | first2 = Robert | last3 = Kehne | first3 = David | last4 = Hegeler | first4 = Frank | last5 = Wolford | first5 = Matthew | last6 = Sethian | first6 = John | last7 = Weaver | first7 = James | last8 = Karasik | first8 = Max | title = High-energy krypton fluoride lasers for inertial fusion | journal = Applied Optics | date = 19 August 2015 | volume = 54 | issue = 31 | pages = F103-22 | issn = 0003-6935 | eissn = 1539-4522 | doi = 10.1364/AO.54.00F103 | pmid = 26560597 | bibcode = 2015ApOpt..54F.103O }}</ref> || {{val|2.6|u=TW}} || {{val|3|u=kJ}} || || {{flagicon|USA}} [[Washington, D.C.]] || [[United States Naval Research Laboratory|NRL]] || [[File:Nike_laser_amplifier.jpg|frameless|154x154px]]
|-
| [[OMEGA laser]] || {{active|Operational}} || ?-1995 || 1995- || 60-beam UV frequency-tripled Nd:glass laser, fusion yield 10<sup>14</sup> neutrons || {{val|60|u=TW}} || {{val|40|u=kJ}} || {{val|300|u=J}} || {{flagicon|USA}} [[Rochester, New York|Rochester]] || [[LLE]] || 
|-
| Electra || {{active|Operational}} ||  ||  || [[Krypton fluoride laser]], 5 Hz operation with 90,000+ shots continuous || {{val|4|u=GW}} || {{val|730|u=J}} || || {{flagicon|USA}} [[Washington D.C.]] || [[United States Naval Research Laboratory|NRL]] || [[File:Electra Laser System NRL 2013.png|frameless|154x154px]]
|-
| [[LULI2000]] || {{active|Operational}} || ? || 2003- || 6-beam Nd:glass laser, λ={{val|1.06|u=μm}}, λ={{val|0.53|u=μm}}, λ={{val|0.26|u=μm}} || {{val|500|u=GW}} || {{val|600|u=J}} || || {{flagicon|FRA}} [[Palaiseau]] || [[École polytechnique]] || 
|-
| [[Laboratory for Laser Energetics#OMEGA EP laser|OMEGA EP]] || {{active|Operational}} ||  || 2008- || 60-beam UV  || {{val|1.4|u=PW}} || {{val|5|u=kJ}} || || {{flagicon|USA}} [[Rochester, New York|Rochester]] || [[LLE]] || 
|-
| {{Anchor|NIF}}[[National Ignition Facility]] (NIF) || {{active|Operational}} || 1997-2009 || 2010- || 192-beam Nd:glass laser, achieved [[Fusion energy gain factor#Scientific breakeven at NIF|scientific breakeven]] with fusion gain of 1.5 and {{val|1.2|e=18}} neutrons<ref>{{Cite web |last=CLERY |first=DANIEL |date=13 December 2022 |title=With historic explosion, a long sought fusion breakthrough |url=https://www.science.org/content/article/historic-explosion-long-sought-fusion-breakthrough |access-date=2022-12-14 |website=www.science.org |language=en}}</ref> || {{val|500|u=TW}} || {{val|2.05|u=MJ}} || {{val|3.15|u=MJ}} || {{flagicon|USA}} [[Livermore, California|Livermore]] || [[LLNL]] || [[File:NIF target chamber construction.jpg|frameless|154x154px]]
|-
| [[Orion (laser)|Orion]] || {{active|Operational}} || 2006-2010 || 2010- || 10-beams, λ={{val|351|u=nm}} || {{val|200|u=TW}} || {{val|5|u=kJ}} || || {{flagicon|UK}} [[RAF Aldermaston]] || [[Atomic Weapons Establishment|AWE]] || [[File:Orion target chamber.jpg|frameless|154x154px]]
|-
| [[Laser Mégajoule]] (LMJ) || {{active|Operational}} || 1999-2014 || 2014- || Second-largest laser fusion facility, 10 out of 22 beam lines operational in 2022<ref>{{Cite web|url=http://www-lmj.cea.fr/|title=CEA – Laser Mégajoule|website=www-lmj.cea.fr}}</ref> || {{val|800|u=TW}} || {{val|1|u=MJ}} || || {{flagicon|FRA}} [[Bordeaux]] || [[French Alternative Energies and Atomic Energy Commission|CEA]] || [https://www.asso-alp.fr/wp-content/uploads/2020/09/LMJ_3.jpg]
|-
| Laser for Fast Ignition Experiments (LFEX) || {{active|Operational}} || 2003-2015 || 2015- || High-contrast heating laser for FIREX, λ={{val|1053|u=nm}} || {{val|2|u=PW}} || {{val|10|u=kJ}} || {{val|100|u=µJ}} || {{flagicon|JP}} [[Osaka]] || Institute for Laser Engineering || 
|-
| [[HiPER]] (High Power Laser Energy Research Facility) || {{BLACK|Cancelled}} || 2007-2015 || - || Pan-European project to demonstrate the technical and economic viability of laser fusion for the production of energy<ref>{{cite web| url=https://www.hiper-laser.org/ |title=The HiPER Project |archive-url=https://web.archive.org/web/20221223061920/https://www.hiper-laser.org/|archive-date=2022-12-23}}</ref> || data-sort-value="{{val|4|u=PW}}"| ({{val|4|u=PW}}) || data-sort-value="{{val|270|u=kJ}}"|({{val|270|u=kJ}}) || data-sort-value="{{val|25|u=MJ}}"|({{val|25|u=MJ}}) || {{flagicon|EU}} ||  || [[File:High Power Laser Energy Research Facility drawing.jpg|frameless|154x154px]]
|-
| [[Laser Inertial Fusion Energy]] (LIFE) || {{BLACK|Cancelled}} || 2008-2013 || - || Effort to develop a fusion power plant succeeding [[#NIF|NIF]] || || data-sort-value="{{val|2.2|u=MJ}}"| ({{val|2.2|u=MJ}}) || data-sort-value="{{val|40|u=MJ}}"| ({{val|40|u=MJ}}) || {{flagicon|USA}} [[Livermore, California|Livermore]] || [[LLNL]] || [[File:LIFE_fusion_chamber.jpg|frameless|154x154px]]
|-
| [[ISKRA lasers#ISKRA-6|ISKRA-6]] || {{planned|Planned}} || ? || ? || 128 beam Nd:glass laser || {{val|300|u=TW}}? || {{val|300|u=kJ}}? || || {{flagicon|RUS}} [[Sarov]] || [[RFNC-VNIIEF]] || 
|}

=== Z-pinch ===
{{Main|Z-pinch}}
*[[Z Pulsed Power Facility]]
*ZEBRA device at the University of Nevada's Nevada Terawatt Facility<ref>{{Cite news|url=http://physics.unr.edu/facility/ntf/index.html|archive-url=https://archive.today/20000919130352/http://physics.unr.edu/facility/ntf/index.html|archive-date=2000-09-19|title=University of Nevada, Reno. Nevada Terawatt Facility|date=2000-09-19|work=archive.is}}</ref>
*Saturn accelerator at [[Sandia National Laboratory]]<ref>{{Cite web|url=http://www.sandia.gov/capabilities/pulsed-power/facilities/saturn.html|title=Sandia National Laboratories: National Security Programs|website=sandia.gov|language=en}}</ref>
* [[MAGPIE]] at [[Imperial College London]]
*COBRA at [[Cornell University]]
*PULSOTRON<ref>{{Cite web|url=http://pulsotron.org|title=PULSOTRON|website=pulsotron.org|access-date=2020-03-09|archive-url=https://web.archive.org/web/20190401022923/http://www.pulsotron.org/|archive-date=2019-04-01}}</ref>
*Z-FFR (Z(-pinch)-Fission-Fusion Reactor), a [[nuclear fusion–fission hybrid]] machine to be built in Chengdu, China by 2025 and generate power as early as 2028

== Inertial electrostatic confinement ==
{{Main|Inertial electrostatic confinement}}
*[[Fusor]]
** [[List of fusor examples]]
*[[Polywell]]

== Magnetized target fusion ==
{{Main|Magnetized target fusion}}
*FRX-L
*FRCHX
*[[General Fusion]] – under development
*[[LINUS (fusion experiment)|LINUS]] project

== References ==
{{Reflist}}

==See also==
* [[List of nuclear reactors]]

{{Fusion power}}

[[Category:Fusion power]]
[[Category:Magnetic confinement fusion devices]]