List of fusion experiments

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Template:Short description Template:Multiple issues

File:Shiva laser target chamber.jpg
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
Plasma chamber of TFTR, used for magnetic confinement fusion experiments, which produced Template:Val 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 fuel and keep it hot.

The major division is between magnetic confinement and inertial confinement. In magnetic confinement, the tendency of the hot plasma to expand is counteracted by the Lorentz force between currents in the plasma and magnetic fields produced by external coils. The particle densities tend to be in the range of Template:Val to Template:Val and the linear dimensions in the range of Template:Val. 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 Template:Val to Template:Val and the plasma radius in the range of 1 to 100 micrometers. These conditions are obtained by irradiating a millimeter-sized solid pellet with a nanosecond laser or ion pulse. The outer layer of the pellet is ablated, providing a reaction force that compresses the central 10% of the fuel by a factor of 10 or 20 to 103 or Template:Val times solid density. These microplasmas disperse in a time measured in nanoseconds. For a fusion power reactor, a repetition rate of several per second will be needed.

Magnetic confinement

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

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

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

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

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

Toroidal machine

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

Tokamak

Device name[1] Status Construction Operation Location Organisation Major/minor radius B-field Plasma current Purpose Image
T-1 (Tokamak-1)[2] Shut down 1957 1958–1959 Template:Flagicon Moscow Kurchatov Institute Template:Val/Template:Val Template:Val Template:Val First tokamak T-1
Script error: No such module "anchor".T-2 (Tokamak-2)[2] Template:CRecurringFT-1 1959 1960–1970 Template:Flagicon Moscow Kurchatov Institute Template:Val/Template:Val Template:Val Template:Val
T-3 (Tokamak-3)[2] Shut down 1960 1962–? Template:Flagicon Moscow Kurchatov Institute Template:Val/Template:Val Template:Val Template:Val Overcame Bohm diffusion by a factor of 10, temperature Template:Val, confinement time Template:Val
T-5 (Tokamak-5)[2] Shut down ? 1962–1970 Template:Flagicon Moscow Kurchatov Institute Template:Val/Template:Val Template:Val Template:Val Investigation of plasma equilibrium in vertical and horizontal direction
TM-1 Shut down ? ? Template:Flagicon Moscow Kurchatov Institute
TM-2 Shut down ? 1965 Template:Flagicon Moscow Kurchatov Institute
TM-3 Shut down ? 1970 Template:Flagicon Moscow Kurchatov Institute
Script error: No such module "anchor".FT-1[2] Template:CRecurring →CASTOR T-2 1972–2002 Template:Flagicon Saint Petersburg Ioffe Institute Template:Val/Template:Val Template:Val Template:Val
Script error: No such module "anchor".ST (Symmetric Tokamak) Shut down Model C 1970–1974 Template:Flagicon Princeton Princeton Plasma Physics Laboratory Template:Val/Template:Val Template:Val Template:Val First American tokamak, converted from Model C stellarator
T-6 (Tokamak-6) Shut down ? 1970–1974 Template:Flagicon Moscow Kurchatov Institute Template:Val/Template:Val Template:Val Template:Val
TUMAN-2, 2A Shut down ? 1971–1985 Template:Flagicon Saint Petersburg Ioffe Institute Template:Val/Template:Val Template:Val Template:Val
ORMAK (Oak Ridge tokaMAK) Shut down 1971–1976 Template:Flagicon Oak Ridge Oak Ridge National Laboratory Template:Val/Template:Val Template:Val Template:Val First to achieve Template:Val plasma temperature ORMAK plasma vessel
Doublet II Shut down 1972–1974 Template:Flagicon San Diego General Atomics Template:Val/Template:Val Template:Val Template:Val
ATC (Adiabatic Toroidal Compressor) Shut down 1971–1972 1972–1976 Template:Flagicon Princeton Princeton Plasma Physics Laboratory Template:Val/Template:Val Template:Val Template:Val Demonstrate compressional plasma heating Schematic of ATC
T-9 (Tokamak-9) Shut down ? 1972–1977 Template:Flagicon Moscow Kurchatov Institute Template:Val/Template:Val Template:Val
TO-1 Shut down ? 1972–1978 Template:Flagicon Moscow Kurchatov Institute Template:Val/Template:Val Template:Val Template:Val
Alcator A (Alto Campo Toro) Shut down ? 1972–1978 Template:Flagicon Cambridge Massachusetts Institute of Technology Template:Val/Template:Val Template:Val Template:Val
JFT-2 (JAERI Fusion Torus 2) Shut down ? 1972–1982 Template:Flagicon Naka Japan Atomic Energy Research Institute Template:Val/Template:Val Template:Val Template:Val
Turbulent Tokamak Frascati (TTF, torello) Shut down 1973 Template:Flagicon Frascati ENEA Template:Val/Template:Val Template:Val Template:Val Study of turbulent plasma heating
Pulsator[3] Shut down 1970–1973 1973–1979 Template:Flagicon Garching Max Planck Institute for Plasma Physics Template:Val/Template:Val Template:Val Template:Val Discovery of high-density operation with tokamaks
TFR (Tokamak de Fontenay-aux-Roses) Shut down 1973–1984 Template:Flagicon Fontenay-aux-Roses CEA Template:Val/Template:Val Template:Val Template:Val
T-4 (Tokamak-4)[2] Shut down ? 1974–1978 Template:Flagicon Moscow Kurchatov Institute Template:Val/Template:Val Template:Val Template:Val Observed fast thermal quench before major plasma disruptions
Doublet IIA Shut down 1974–1979 Template:Flagicon San Diego General Atomics Template:Val/Template:Val Template:Val Template:Val
Petula-B Shut down ? 1974–1986 Template:Flagicon Grenoble CEA Template:Val/Template:Val Template:Val Template:Val
T-10 (Tokamak-10)[2] Operational 1975– Template:Flagicon Moscow Kurchatov Institute Template:Val/Template:Val Template:Val Template:Val Largest tokamak of its time Model of the T-10
T-11 (Tokamak-11) Shut down ? 1975–1984 Template:Flagicon Moscow Kurchatov Institute Template:Val/Template:Val Template:Val
PLT (Princeton Large Torus) Shut down 1972–1975 1975–1986 Template:Flagicon Princeton Princeton Plasma Physics Laboratory Template:Val/Template:Val Template:Val Template:Val First to achieve Template:Val plasma current Construction of the Princeton Large Torus
Divertor Injection Tokamak Experiment (DITE) Shut down 1975–1989 Template:Flagicon Culham United Kingdom Atomic Energy Authority Template:Val/Template:Val Template:Val Template:Val
JIPP T-II Shut down ? 1976 Template:Flagicon Nagoya Nagoya University Template:Val/Template:Val Template:Val Template:Val
TNT-A Shut down ? 1976 Template:Flagicon Tokyo Tokyo University Template:Val/Template:Val Template:Val Template:Val
T-8 (Tokamak-8)[2] Shut down ? 1976–? Template:Flagicon Moscow Kurchatov Institute Template:Val/Template:Val Template:Val Template:Val First D-shaped tokamak
Microtor[4] Shut down ? 1976–1983? Template:Flagicon Los Angeles UCLA Template:Val/Template:Val Template:Val Template:Val Plasma impurity control and diagnostic development
Macrotor[4] Shut down ? 1970s–80s Template:Flagicon Los Angeles UCLA Template:Val/Template:Val Template:Val Template:Val Understanding plasma rotation driven by radial current
TUMAN-3[2] Operational ? 1977–
(1990–, 3M)
Template:Flagicon Saint Petersburg Ioffe Institute Template:Val/Template:Val Template:Val Template:Val Study adiabatic compression, RF and NB heating, H-mode and parametric instability
Thor[5] Shut down ? Template:Flagicon Milano University of Milano Template:Val/Template:Val Template:Val Template:Val
FT (Frascati Tokamak) Shut down 1978 Template:Flagicon Frascati ENEA Template:Val/Template:Val Template:Val Template:Val
PDX (Poloidal Divertor Experiment) Shut down ? 1978–1983 Template:Flagicon Princeton Princeton Plasma Physics Laboratory Template:Val/Template:Val Template:Val Template:Val
ISX-B Shut down ? 1978–1984 Template:Flagicon Oak Ridge Oak Ridge National Laboratory Template:Val/Template:Val Template:Val Template:Val Attempt high-beta operation
Doublet III Shut down 1978–1985 Template:Flagicon San Diego General Atomics Template:Val/Template:Val Template:Val Template:Val
T-12 (Tokamak-12) Shut down ? 1978–1985 Template:Flagicon Moscow Kurchatov Institute Template:Val/Template:Val Template:Val Template:Val
Alcator C (Alto Campo Toro) Shut down ? 1978–1986 Template:Flagicon Cambridge Massachusetts Institute of Technology Template:Val/Template:Val Template:Val Template:Val
Script error: No such module "anchor".T-7 (Tokamak-7)[2] Template:CRecurringHT-7[6] ? 1979–1985 Template:Flagicon Moscow Kurchatov Institute Template:Val/Template:Val Template:Val Template:Val First tokamak with superconducting toroidal field coils
ASDEX (Axially Symmetric Divertor Experiment)[7] Template:CRecurringHL-2A 1973–1980 1980–1990 Template:Flagicon Garching Max-Planck-Institut für Plasmaphysik Template:Val/Template:Val Template:Val Template:Val Discovery of the H-mode in 1982
FT-2[2] Operational ? 1980– Template:Flagicon Saint Petersburg Ioffe Institute Template:Val/Template:Val Template:Val Template:Val H-mode physics, LH heating
TEXTOR (Tokamak Experiment for Technology Oriented Research)[8][9] Shut down 1976–1980 1981–2013 Template:Flagicon Jülich Forschungszentrum Jülich Template:Val/Template:Val Template:Val Template:Val Study plasma-wall interactions
TFTR (Tokamak Fusion Test Reactor)[10] Shut down 1980–1982 1982–1997 Template:Flagicon Princeton Princeton Plasma Physics Laboratory Template:Val/Template:Val Template:Val Template:Val Attempted scientific break-even, reached record fusion power of Template:Val and temperature of Template:Val TFTR plasma vessel
Tokamak de Varennes (TdeV) Shut down ? 1983–1997 Template:Flagicon Montreal National Research Council Canada Template:Val/Template:Val Template:Val Template:Val [11]
JFT-2M (JAERI Fusion Torus 2M) Shut down ? 1983–2004 Template:Flagicon Naka Japan Atomic Energy Research Institute Template:Val/Template:Val Template:Val Template:Val
JET (Joint European Torus)[12] Shut down 1978–1983 1983–2023 Template:Flagicon Culham United Kingdom Atomic Energy Authority Template:Val/Template:Val Template:Val Template:Val Records for fusion output power Template:Val (1997), fusion energy Template:Val (2023) JET in 1991
Novillo[13][14] Shut down NOVA-II 1983–2004 Template:Flagicon Mexico City Instituto Nacional de Investigaciones Nucleares Template:Val/Template:Val Template:Val Template:Val Study plasma-wall interactions
JT-60 (Japan Torus-60)[15] Template:CRecurringJT-60U 1985–1989 Template:Flagicon Naka Japan Atomic Energy Research Institute Template:Val/Template:Val Template:Val Template:Val High-beta steady-state operation, highest fusion triple product JT-60 vacuum vessel
CCT (Continuous Current Tokamak) Shut down ? 1986–199? Template:Flagicon Los Angeles UCLA Template:Val/Template:Val Template:Val Template:Val H-mode studies
DIII-D[16] Operational 1986[17] 1986– Template:Flagicon San Diego General Atomics Template:Val/Template:Val Template:Val Template:Val Tokamak Optimization DIII-D vacuum vessel
STOR-M (Saskatchewan Torus-Modified)[18] Operational 1987– Template:Flagicon Saskatoon Plasma Physics Laboratory (Saskatchewan) Template:Val/Template:Val Template:Val Template:Val Study plasma heating and anomalous transport
T-15[2] Template:CRecurringT-15MD 1983–1988 1988–1995 Template:Flagicon Moscow Kurchatov Institute Template:Val/Template:Val Template:Val Template:Val First superconducting tokamak, pulse duration Template:Val T-15 on a stamp
Tore Supra[19] Template:CRecurringWEST 1988–2011 Template:Flagicon Cadarache Département de Recherches sur la Fusion Contrôlée Template:Val/Template:Val Template:Val Template:Val Large superconducting tokamak with active cooling
ADITYA (tokamak) Operational 1989– Template:Flagicon Gandhinagar Institute for Plasma Research Template:Val/Template:Val Template:Val Template:Val
COMPASS (COMPact ASSembly)[20][21] Operational 1980– 1989– Template:Flagicon Prague Institute of Plasma Physics, Czech Academy of Sciences Template:Val/Template:Val Template:Val Template:Val Plasma physics studies for ITER COMPASS plasma chamber
FTU (Frascati Tokamak Upgrade) Operational 1990– Template:Flagicon Frascati ENEA Template:Val/Template:Val Template:Val Template:Val
START (Small Tight Aspect Ratio Tokamak)[22] Template:CRecurringProto-Sphera 1990–1998 Template:Flagicon Culham United Kingdom Atomic Energy Authority Template:Val/? Template:Val Template:Val First full-sized Spherical Tokamak
Script error: No such module "anchor".JT-60U (Japan Torus-60 Upgrade) Shut down 1989–1991 1991–2008 Template:Flagicon Naka Japan Atomic Energy Research Institute Template:Val/Template:Val Template:Val Template:Val investigate energy confinement near the breakeven condition
ASDEX Upgrade (Axially Symmetric Divertor Experiment) Operational 1991– Template:Flagicon Garching Max-Planck-Institut für Plasmaphysik Template:Val/Template:Val Template:Val Template:Val ASDEX Upgrade plasma vessel segment
Alcator C-Mod (Alto Campo Toro)[23] Shut down 1986– 1991–2016 Template:Flagicon Cambridge Massachusetts Institute of Technology Template:Val/Template:Val Template:Val Template:Val Record plasma pressure Template:Val Alcator C-Mod plasma vessel
ISTTOK (Instituto Superior Técnico TOKamak)[24] Operational 1992– Template:Flagicon Lisbon Instituto de Plasmas e Fusão Nuclear Template:Val/Template:Val Template:Val Template:Val
TCV (Tokamak à Configuration Variable)[25] Operational 1992– Template:Flagicon Lausanne École Polytechnique Fédérale de Lausanne Template:Val/Template:Val Template:Val Template:Val Confinement studies TCV plasma vessel
HBT-EP (High Beta Tokamak-Extended Pulse) Operational 1993– Template:Flagicon New York City Columbia University Plasma Physics Laboratory Template:Val/Template:Val Template:Val Template:Val High-Beta tokamak HBT-EP sketch
Script error: No such module "anchor".HT-7 (Hefei Tokamak-7) Shut down 1991–1994 (T-7) 1995–2013 Template:Flagicon Hefei Hefei Institutes of Physical Science Template:Val/Template:Val Template:Val Template:Val China's first superconducting tokamak
Pegasus Toroidal Experiment[26] Operational ? 1996– Template:Flagicon Madison University of Wisconsin–Madison Template:Val/Template:Val Template:Val Template:Val Extremely low aspect ratio Pegasus Toroidal Experiment
NSTX (National Spherical Torus Experiment)[27] Operational 1999– Template:Flagicon Plainsboro Township Princeton Plasma Physics Laboratory Template:Val/Template:Val Template:Val Template:Val Study the spherical tokamak concept National Spherical Torus Experiment
Globus-M (UNU Globus-M)[28] Operational 1999– Template:Flagicon Saint Petersburg Ioffe Institute Template:Val/Template:Val Template:Val Template:Val Study the spherical tokamak concept
ET (Electric Tokamak) Template:CRecurringETPD 1998 1999–2006 Template:Flagicon Los Angeles UCLA Template:Val/Template:Val Template:Val Template:Val Largest tokamak of its time The Electric Tokamak.jpg
TCABR (Tokamak Chauffage Alfvén Brésilien) Operational 1980–1999 1999– Template:Flagicon Lausanne,
Template:Flagicon Sao Paulo
University of Sao Paulo Template:Val / Template:Val Template:Val Template:Val Most important tokamak in the southern hemisphere File:TCABR lab.jpg
CDX-U (Current Drive Experiment-Upgrade) Template:CRecurringLTX 2000–2005 Template:Flagicon Princeton Princeton Plasma Physics Laboratory Template:Val/? Template:Val Template:Val Study Lithium in plasma walls CDX-U setup
MAST (Mega-Ampere Spherical Tokamak)[29] Template:CRecurringMAST-Upgrade 1997–1999 2000–2013 Template:Flagicon Culham United Kingdom Atomic Energy Authority Template:Val/Template:Val Template:Val Template:Val Investigate spherical tokamak for fusion Plasma in MAST
Script error: No such module "anchor".HL-2A (Huan-Liuqi-2A) Operational 2000–2002 2002–2018 Template:Flagicon Chengdu Southwestern Institute of Physics Template:Val/Template:Val Template:Val Template:Val H-mode physics, ELM mitigation
SST-1 (Steady State Superconducting Tokamak)[30] Operational 2001– 2005– Template:Flagicon Gandhinagar Institute for Plasma Research Template:Val/Template:Val Template:Val Template:Val Produce a Template:Val elongated double null divertor plasma
EAST (Experimental Advanced Superconducting Tokamak)[31] Operational 2000–2005 2006– Template:Flagicon Hefei Hefei Institutes of Physical Science Template:Val/Template:Val Template:Val Template:Val Superheated plasma for over Template:Val and Template:Val at Template:Val[32][33] Drawing of EAST
J-TEXT (Joint TEXT) Operational TEXT (Texas EXperimental Tokamak) 2007– Template:Flagicon Wuhan Huazhong University of Science and Technology Template:Val/Template:Val Template:Val Template:Val Develop plasma control
KSTAR (Korea Superconducting Tokamak Advanced Research)[34] Operational 1998–2007 2008– Template:Flagicon Daejeon National Fusion Research Institute Template:Val/Template:Val Template:Val Template:Val Tokamak with fully superconducting magnets, Template:Val-long operation at Template:Val[35] KSTAR
Script error: No such module "anchor".LTX (Lithium Tokamak Experiment) Operational 2005–2008 2008– Template:Flagicon Princeton Princeton Plasma Physics Laboratory Template:Val/? Template:Val Template:Val Study Lithium in plasma walls Lithium Tokamak Experiment plasma vessel
QUEST (Q-shu University Experiment with Steady-State Spherical Tokamak)[36][37] Operational 2008– Template:Flagicon Kasuga Kyushu University Template:Val/Template:Val Template:Val Template:Val Study steady state operation of a Spherical Tokamak QUEST
Kazakhstan Tokamak for Material testing (KTM) Operational 2000–2010 2010– Template:Flagicon Kurchatov National Nuclear Center of the Republic of Kazakhstan Template:Val/Template:Val Template:Val Template:Val Testing of wall and divertor
ST25-HTS[38] Operational 2012–2015 2015– Template:Flagicon Culham Tokamak Energy Ltd Template:Val/Template:Val Template:Val Template:Val Steady state plasma ST25-HTS with plasma
Script error: No such module "anchor".WEST (Tungsten Environment in Steady-state Tokamak) Operational 2013–2016 2016– Template:Flagicon Cadarache Département de Recherches sur la Fusion Contrôlée Template:Val/Template:Val Template:Val Template:Val Superconducting tokamak with active cooling WEST chamber
ST40[39] Operational 2017–2018 2018– Template:Flagicon Didcot Tokamak Energy Ltd Template:Val/Template:Val Template:Val Template:Val First high field spherical tokamak, reached Template:Val plasma ST40 engineering drawing
Script error: No such module "anchor".MAST-U (Mega-Ampere Spherical Tokamak Upgrade)[40] Operational 2013–2019 2020– Template:Flagicon Culham United Kingdom Atomic Energy Authority Template:Val/Template:Val Template:Val Template:Val Test new exhaust concepts for a spherical tokamak
HL-3 / HL-2M (Huan-Liuqi-2M)[41] Operational 2018–2019 2020– Template:Flagicon Leshan Southwestern Institute of Physics Template:Val/Template:Val Template:Val Template:Val Elongated plasma with Template:Val HL-2M
Script error: No such module "anchor".JT-60SA (Japan Torus-60 super, advanced)[42] Operational 2013–2020 2021– Template:Flagicon Naka Japan Atomic Energy Research Institute Template:Val/Template:Val Template:Val Template:Val Optimise plasma configurations for ITER and DEMO with full non-inductive steady-state operation JT-60SA
Script error: No such module "anchor".T-15MD Operational 2010–2020 2021– Template:Flagicon Moscow Kurchatov Institute Template:Val/Template:Val Template:Val Template:Val Hybrid fusion/fission reactor T-15MD coil system
IGNITOR[43] Template:BLACK 2022[44] - - Template:Flagicon Troitzk ENEA Template:Val/Template:Val Template:Val Template:Val Compact fusion reactor with self-sustained plasma and Template:Val of planned fusion power
HH70 (HongHuang 70)[45][46] Operational 2022–2024 2024– Template:FlagiconShanghai Energy Singularity Template:Val/Template:Val Template:Val REBCO High-temperature superconducting coils
SPARC[47][48][49][50][51] Under construction 2021– 2026? Template:Flagicon Devens, MA Commonwealth Fusion Systems and MIT Plasma Science and Fusion Center Template:Val/Template:Val Template:Val Template:Val Compact, high-field tokamak with ReBCO coils and Template:Val planned fusion power Artist's impression of SPARC
ITER[52] Under construction 2013–2034? 2034? Template:Flagicon Cadarache ITER Council Template:Val/Template:Val Template:Val Template:Val ? Demonstrate feasibility of fusion on a power-plant scale with Template:Val fusion power Small-scale model of ITER
DTT (Divertor Tokamak Test facility)[53][54][55] Template:Planned 2022–2029? 2029? Template:Flagicon Frascati ENEA Template:Val/Template:Val Template:Val ? Template:Val ? Superconducting tokamak to study power exhaust
SST-2 (Steady State Tokamak-2)[56] Template:Planned 2027? Template:Flagicon Gujarat Institute for Plasma Research Template:Val/Template:Val Template:Val Template:Val Full-fledged fusion reactor with tritium breeding and up to 500 MW output
CFETR (China Fusion Engineering Test Reactor)[57] Template:Planned ≥2024 2030? Template:Flagicon Institute of Plasma Physics, Chinese Academy of Sciences Template:Val/Template:Val ? Template:Val ? Template:Val ? Bridge gaps between ITER and DEMO, planned fusion power Template:Val
ST-F1 (Spherical Tokamak - Fusion 1)[58] Template:Planned 2027? Template:Flagicon Didcot Tokamak Energy Ltd Template:Val/Template:Val ? Template:Val Template:Val Spherical tokamak with Q=3 and hundreds of MW planned electrical output (no longer mentioned by company as of 2024)
STX (ST80-HTS) Template:Planned 2026? 2030? Template:Flagicon Culham Tokamak Energy Ltd Spherical tokamak capable of 15min-pulsed operation[59][60]
ST-E1 Template:Planned 2030s? Template:Flagicon Culham Tokamak Energy Ltd Spherical tokamak with Template:Val planned net electric output[61]
STEP (Spherical Tokamak for Energy Production) Template:Planned 2032-2040 2040 D-D
Mid 2040s DT Campaign
Template:Flagicon West Burton, Nottinghamshire United Kingdom Atomic Energy Authority Template:Val/Template:Val ? ? Template:Val ? Spherical tokamak with Template:Val planned electrical output[62]
JA-DEMO Template:Planned 2030? 2050? Template:Flagicon ? Template:Val/Template:Val[63] Template:Val Template:Val Prototype for development of Commercial Fusion Reactors Template:Val Fusion output.[64]
K-DEMO (Korean fusion demonstration tokamak reactor)[65] Template:Planned 2037? Template:Flagicon National Fusion Research Institute Template:Val/Template:Val Template:Val Template:Val ? Prototype for the development of commercial fusion reactors with around Template:Val of fusion power Engineering drawing of planned KDEMO
DEMO (DEMOnstration Power Station) Template:Planned 2040? 2050? ? Template:Val/Template:Val ? Template:Val ? Template:Val ? Prototype for a commercial fusion reactor Artist's conception of DEMO

Stellarator

Device name Status Construction Operation Type Location Organisation Major/minor radius B-field Purpose Image
Model A Shut down 1952–1953 1953–? Figure-8 Template:Flagicon Princeton Princeton Plasma Physics Laboratory Template:Val/Template:Val Template:Val First stellarator, table-top device
Model B Shut down 1953–1954 1954–1959 Figure-8 Template:Flagicon Princeton Princeton Plasma Physics Laboratory Template:Val/Template:Val Template:Val Development of plasma diagnostics
Model B-1 Shut down ?–1959 Figure-8 Template:Flagicon Princeton Princeton Plasma Physics Laboratory Template:Val/Template:Val Template:Val Yielded Template:Val plasma temperatures, showed cooling by X-ray radiation from impurities
Model B-2 Shut down 1957 Figure-8 Template:Flagicon Princeton Princeton Plasma Physics Laboratory Template:Val/Template:Val Template:Val Electron temperatures up to Template:Val
Model B-3 Shut down 1957 1958– Figure-8 Template:Flagicon Princeton Princeton Plasma Physics Laboratory Template:Val/Template:Val Template:Val Last figure-8 device, confinement studies of ohmically heated plasma
Model B-64 Shut down 1955 1955 Square Template:Flagicon Princeton Princeton Plasma Physics Laboratory ? m/Template:Val Template:Val
Model B-65 Shut down 1957 1957 Racetrack Template:Flagicon Princeton Princeton Plasma Physics Laboratory
Model B-66 Shut down 1958 1958–? Racetrack Template:Flagicon Princeton Princeton Plasma Physics Laboratory
Wendelstein 1-A Shut down 1960 Racetrack Template:Flagicon Garching Max-Planck-Institut für Plasmaphysik Template:Val/Template:Val Template:Val ℓ=3 showed that stellarators can overcome Bohm diffusion, "Munich mystery"
Wendelstein 1-B Shut down 1960 Racetrack Template:Flagicon Garching Max-Planck-Institut für Plasmaphysik Template:Val/Template:Val Template:Val ℓ=2
Script error: No such module "anchor".Model C Template:CRecurringST 1957–1961 1961–1969 Racetrack Template:Flagicon Princeton Princeton Plasma Physics Laboratory Template:Val/Template:Val Template:Val Suffered from large plasma losses by Bohm diffusion through "pump-out"
L-1 Shut down 1963 1963–1971 round Template:Flagicon Moscow Lebedev Physical Institute Template:Val/Template:Val Template:Val First Soviet stellarator, overcame Bohm diffusion
SIRIUS Shut down 1964–? Racetrack Template:Flagicon Kharkiv Kharkiv Institute of Physics and Technology (KIPT)
TOR-1 Shut down 1967 1967–1973 Template:Flagicon Moscow Lebedev Physical Institute Template:Val/Template:Val Template:Val
TOR-2 Shut down ? 1967–1973 Template:Flagicon Moscow Lebedev Physical Institute Template:Val/Template:Val Template:Val
Uragan-1 Shut down 1960–1967 1967–? Racetrack Template:Flagicon Kharkiv National Science Center, Kharkiv Institute of Physics and Technology (NSC KIPT) Template:Val/Template:Val Template:Val Overcame Bohm-diffusion by a factor of 30
CLASP (Closed Line And Single Particle)[66] Shut down ? 1967–? Template:Flagicon Culham United Kingdom Atomic Energy Authority Template:Val/Template:Val Template:Val Study confinement of electrons in a high-shear stellarator
TWIST[66] Shut down ? 1967–? Template:Flagicon Culham United Kingdom Atomic Energy Authority Template:Val/Template:Val Template:Val Study turbulent heating
Proto-CLEO[66] Shut down ? 1968–? single-turn helical winding inside toroidal field conductors Template:Flagicon Culham,
Template:Flagicon Madison
United Kingdom Atomic Energy Authority Template:Val/Template:Val Template:Val confirmed plasma confinement times of neoclassical theory
TORSO[66] Shut down ? 1972–? Ultimate torsatron Template:Flagicon Culham United Kingdom Atomic Energy Authority Template:Val/Template:Val Template:Val
CLEO[66] Shut down ? 1974–? Template:Flagicon Culham United Kingdom Atomic Energy Authority Template:Val/Template:Val Template:Val Study of particle transport and beta limits, reached similar performance as tokamaks
Wendelstein 2-A Shut down 1965–1968 1968–1974 Heliotron Template:Flagicon Garching Max-Planck-Institut für Plasmaphysik Template:Val/Template:Val Template:Val Good plasma confinement Wendelstein 2-A
Saturn[67] Shut down 1970 1970–? Torsatron Template:Flagicon Kharkiv Kharkiv Institute of Physics and Technology Template:Val/Template:Val Template:Val first Torsatron, ℓ=3, m=8 field periods, base for several torsatrons at KIPT
Wendelstein 2-B Shut down ?–1970 1971–? Heliotron Template:Flagicon Garching Max-Planck-Institut für Plasmaphysik Template:Val/Template:Val Template:Val Demonstrated similar performance as tokamaks Wendelstein 2-B
Vint-20[68] Shut down 1972 1973–? Torsatron Template:Flagicon Kharkiv Kharkiv Institute of Physics and Technology Template:Val/Template:Val Template:Val single-pole ℓ=1, m=13 field periods
L-2 Shut down ? 1975–? Template:Flagicon Moscow Lebedev Physical Institute Template:Val/Template:Val Template:Val
WEGA (Wendelstein Experiment in Greifswald für die Ausbildung) Template:CRecurringHIDRA 1972–1975 1975–2013 Classical stellarator Template:Flagicon Greifswald Max-Planck-Institut für Plasmaphysik Template:Val/Template:Val Template:Val Test lower hybrid heating WEGA
Wendelstein 7-A Shut down ? 1975–1985 Classical stellarator Template:Flagicon Garching Max-Planck-Institut für Plasmaphysik Template:Val/Template:Val Template:Val First "pure" stellarator without plasma current, solved stellarator heating problem
Heliotron-E Shut down ? 1980–? Heliotron Template:Flagicon Template:Val/Template:Val Template:Val
Heliotron-DR Shut down ? 1981–? Heliotron Template:Flagicon Template:Val/Template:Val Template:Val
Uragan-3 (Template:Interlanguage link multi)[69] Operational ? 1982–?[70]
M: 1990–
Torsatron Template:Flagicon Kharkiv National Science Center, Kharkiv Institute of Physics and Technology (NSC KIPT) Template:Val/Template:Val Template:Val ?
Auburn Torsatron (AT) Shut down ? 1984–1990 Torsatron Template:Flagicon Auburn Auburn University Template:Val/Template:Val Template:Val Auburn Torsatron
Wendelstein 7-AS Shut down 1982–1988 1988–2002 Modular, advanced stellarator Template:Flagicon Garching Max-Planck-Institut für Plasmaphysik Template:Val/Template:Val Template:Val First computer-optimized stellarator, first H-mode in a stellarator in 1992 Wendelstein 7-AS
Advanced Toroidal Facility (ATF) Shut down 1984–1988[71] 1988–1994 Torsatron Template:Flagicon Oak Ridge Oak Ridge National Laboratory Template:Val/Template:Val Template:Val First large American stellarator after Tokamak stampede, high-beta operation, >1h plasma operation Advanced Toroidal Facility
Compact Helical System (CHS) Shut down ? 1989–? Heliotron Template:Flagicon Toki National Institute for Fusion Science Template:Val/Template:Val Template:Val
Compact Auburn Torsatron (CAT) Shut down ?–1990 1990–2000 Torsatron Template:Flagicon Auburn Auburn University Template:Val/Template:Val Template:Val Study magnetic flux surfaces Compact Auburn Torsatron
H-1 (Heliac-1)[72] Operational 1992– Heliac Template:Flagicon Canberra,
Template:Flagicon
Research School of Physical Sciences and Engineering, Australian National University Template:Val/Template:Val Template:Val shipped to China in 2017 H-1NF plasma vessel
TJ-K (Tokamak de la Junta Kiel)[73] Operational TJ-IU (1999) 1994– Torsatron Template:Flagicon Kiel, Stuttgart University of Stuttgart Template:Val/Template:Val Template:Val One helical and two vertical coil sets; Teaching; moved from Kiel to Stuttgart in 2005
TJ-II (Tokamak de la Junta II)[74] Operational 1991–1996 1997– flexible Heliac Template:Flagicon Madrid National Fusion Laboratory, Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas Template:Val/Template:Val Template:Val Study plasma in flexible configuration CAD drawing of TJ-II
LHD (Large Helical Device)[75] Operational 1990–1998 1998– Heliotron Template:Flagicon Toki National Institute for Fusion Science Template:Val/Template:Val Template:Val Demonstrated long-term operation of large superconducting coils LHD cross section
HSX (Helically Symmetric Experiment)[76] Operational 1999– Modular, quasi-helically symmetric Template:Flagicon Madison University of Wisconsin–Madison Template:Val/Template:Val Template:Val Investigate plasma transport in quasi-helically-symmetric field, similar to tokamaks HSX with clearly visible non-planar coils
Heliotron J[77] Operational 2000– Heliotron Template:Flagicon Kyoto Institute of Advanced Energy Template:Val/Template:Val Template:Val Study helical-axis heliotron configuration
Columbia Non-neutral Torus (CNT) Operational ? 2004– Circular interlocked coils Template:Flagicon New York City Columbia University Template:Val/Template:Val Template:Val Study of non-neutral (mostly electron) plasmas
Uragan-2(M)[69] Operational 1988–2006 2006–[78] Heliotron, Torsatron Template:Flagicon Kharkiv National Science Center, Kharkiv Institute of Physics and Technology (NSC KIPT) Template:Val/Template:Val Template:Val ℓ=2 Torsatron
Quasi-poloidal stellarator (QPS)[79][80] Template:BLACK 2001–2007 Modular Template:Flagicon Oak Ridge Oak Ridge National Laboratory Template:Val/Template:Val Template:Val Stellarator research Engineering drawing of the QPS
NCSX (National Compact Stellarator Experiment) Template:BLACK 2004–2008 Helias Template:Flagicon Princeton Princeton Plasma Physics Laboratory Template:Val/Template:Val Template:Val High-β stability CAD drawing of NCSX
Compact Toroidal Hybrid (CTH) Operational ? 2007?– Torsatron Template:Flagicon Auburn Auburn University Template:Val/Template:Val Template:Val Hybrid stellarator/tokamak CTH
Script error: No such module "anchor".HIDRA (Hybrid Illinois Device for Research and Applications)[81] Operational 2013–2014 (WEGA) 2014– ? Template:Flagicon Urbana, IL University of Illinois Template:Val/Template:Val Template:Val Stellarator and tokamak in one device, capable of long pulse steady-state operation; study plasma-wall interactions HIDRA after its reassembly in Illinois
UST_2[82] Operational 2013 2014– modular three period quasi-isodynamic Template:Flagicon Madrid Charles III University of Madrid Template:Val/Template:Val Template:Val 3D-printed stellarator UST_2 design concept
Wendelstein 7-X[83] Operational 1996–2022 2015– Helias Template:Flagicon Greifswald Max-Planck-Institut für Plasmaphysik Template:Val/Template:Val Template:Val Steady-state plasma in large fully optimized stellarator Schematic diagram of Wendelstein 7-X
SCR-1 (Stellarator of Costa Rica) Operational 2011–2015 2016– Modular Template:Flagicon Cartago Costa Rica Institute of Technology Template:Val/Template:Val Template:Val SCR-1 vacuum vessel drawing
MUSE[84] Operational 2022–2023 2023– Quasiaxi-symmetrical Template:Flagicon Princeton Princeton Plasma Physics Laboratory Template:Val/Template:Val Template:Val First stellarator with permanent magnets MUSE
CFQS (Chinese First Quasi-Axisymmetric Stellarator)[85] Under construction 2017– Helias Template:Flagicon Chengdu Southwest Jiaotong University, National Institute for Fusion Science in Japan Template:Val/Template:Val Template:Val m=2 quasi-axisymmetric stellarator, modular CFQS coils and field
EFPP (European Fusion Power Plant)[86] Template:Planned 2030 ? 2045 ? Helias Template:Flagicon Gauss Fusion 7–Template:Val ? Fusion power plant with 2–Template:Val output

Magnetic mirror

Toroidal Z-pinch

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

Reversed field pinch (RFP)

Spheromak

Field-reversed configuration (FRC)

Other toroidal machines

  • TMP (Tor s Magnitnym Polem, torus with magnetic field): A porcelain torus with major radius Template:Val, minor radius Template:Val, toroidal field of Template:Val and plasma current Template:Val, predecessor to the first tokamak (1955, USSR)

Open field lines

Plasma pinch

Levitated dipole

Inertial confinement

Script error: No such module "Labelled list hatnote".

Laser-driven

Device name Status Construction Operation Description Peak laser power Pulse energy Fusion yield Location Organisation Image
4 pi laser Shut down 196? Semiconductor laser Template:Val Template:Val Template:Flagicon Livermore LLNL
Long path laser Shut down 1972 1972 First ICF laser with neodymium doped glass (Nd:glass) as lasing medium Template:Val Template:Val Template:Flagicon Livermore LLNL
Single Beam System (SBS) "67" Shut down 1971-1973 1973 Single-beam CO2 laser[92] Template:Val Template:Val Template:Flagicon Los Alamos LANL
Double Bounce Illumination System (DBIS) Shut down 1972-1974 1974-1990 First private laser fusion effort, YAG laser, neutron yield Template:Val to Template:Val neutrons Template:Val data-sort-value="Template:Val"| ≈Template:Val Template:Flagicon Ann Arbor, Michigan KMS Fusion File:Double Bounce System KMS Fusion 1974.png
MERLIN (Medium Energy Rod Laser Incorporating Neodymium), N78 laser Shut down 1972-1975 1975-? Nd:glass laser Template:Val Template:Val Template:Flagicon RAF Aldermaston AWE File:MERLIN target chamber.jpg
Cyclops laser Shut down 1975 1975 Single-beam Nd:glass laser, prototype for Shiva[93] Template:Val Template:Val Template:Flagicon Livermore LLNL File:Cyclops laser 1975.jpg
Janus laser Shut down 1974-1975 1975 Two-beam Nd:glass laser demonstrated laser compression and thermonuclear burn of deuterium–tritium Template:Val Template:Val Template:Flagicon Livermore LLNL File:Janus laser 1975.jpg
Gemini laser, Dual-Beam Module (DBM) Shut down ≤ 1975 1976 Two-beam CO2 laser, tests for Helios Template:Val Template:Val Template:Flagicon Los Alamos LANL
Argus laser Shut down 1976 1976-1981 Two-beam Nd:glass laser, advanced the study of laser-target interaction and paved the way for Shiva Template:Val Template:Val data-sort-value="Template:Val"| ≈Template:Val Template:Flagicon Livermore LLNL File:Argus laser 1976.jpg
Vulcan laser (Versicolor Ultima Lux Coherens pro Academica Nostra)[94] Operational 1976-1977 1977- 8-beam Nd:glass laser, highest-intensity focussed laser in the world in 2005[95] Template:Val Template:Val Template:Flagicon Didcot RAL File:Green Lase.JPG
Script error: No such module "anchor".Shiva laser Shut down 1977 1977-1981 20-beam Nd:glass laser; proof-of-concept for Nova; fusion yield of 1011 neutrons; found that its infrared wavelength of 1062 nm was too long to achieve ignition Template:Val Template:Val data-sort-value="Template:Val"| ≈Template:Val Template:Flagicon Livermore LLNL File:Shiva laser target chamber.jpg
Script error: No such module "anchor".Helios laser, Eight-Beam System (EBS) Shut down 1975-1978 1978 8-beam CO2 laser; Media at Wikimedia Commons Template:Val Template:Val Template:Flagicon Los Alamos LANL File:U.S. Department of Energy - Science - 282 005 003 (16388751641).jpg
HELEN (High Energy Laser Embodying Neodymium) Shut down 1976-1979 1979-2009 Two-beam Nd:glass laser Template:Val Template:Val Template:Flagicon Didcot RAL File:HELEN laser.jpg
ISKRA-4 Operational -1979 1979- 8-beam iodine gas laser, prototype for ISKRA-5[96] Template:Val Template:Val Template:Val Template:Flagicon Sarov RFNC-VNIIEF
Sprite laser[94] Shut down 1981-1983 1983-1995 First high-power Krypton fluoride laser used for target irradiation, λ=Template:Val Template:Val Template:Val Template:Flagicon Didcot RAL File:Sprite e-beam pumped amplifier cell 1982.jpg
Gekko XII Operational 1983- 12-beam, Nd:glass laser Template:Val Template:Val Template:Flagicon Osaka Institute for Laser Engineering
Novette laser Shut down 1981-1983 1983-1984 Nd:glass laser to validate the Nova design, first X-ray laser[97] Template:Val Template:Val Template:FlagiconLivermore LLNL File:U.S. Department of Energy - Science - 281 004 001 (16315143010).jpg
Antares laser, High Energy Gas Laser Facility (HEGLF) Shut down 1983[98] 24-beam largest CO2 laser ever built. Missed goal of scientific fusion breakeven, because production of hot electrons in target plasma due to long 10.6 μm wavelength of laser resulted in poor laser/plasma energy coupling[97] Template:Val Template:Val Template:Flagicon Los Alamos LANL
PHAROS laser Operational 198? Two-beam Nd:glass laser Template:Val Template:Val Template:Flagicon Washington D.C. NRL
Script error: No such module "anchor".Nova laser Shut down 1984-1999 10-beam NIR and frequency-tripled 351 nm UV laser; fusion yield of 1013 neutrons; attempted ignition, but failed due to fluid instability of targets; led to construction of NIF Template:Val Template:Val Template:Val Template:FlagiconLivermore LLNL
Script error: No such module "anchor".ISKRA-5 Operational -1989 12-beam iodine gas laser, fusion yield 1010 to 1011 neutrons[96] Template:Val Template:Val Template:Val Template:Flagicon Sarov RFNC-VNIIEF
Aurora laser Shut down ≤ 1988-1989 1990 96-beam Krypton fluoride laser data-sort-value="Template:Val"| ≈Template:Val Template:Val Template:Flagicon Los Alamos LANL
Shenguang-I Shut down 1990 2-beam Nd:glass laser, λ=Template:Val[99] Template:Val Template:Val[100] Template:Country data China Joint Laboratory of High Power Laser and Physics
PALS, formerly "Asterix IV" Operational -1991 1991- Iodine gas laser, λ=Template:Val Template:Val Template:Val Template:Flagicon Garching,
Template:Flagicon Prague
MPQ, CAS File:Prague asterix laser system.jpeg
Trident laser Operational 198?-1992 1992-2017 3-beam Nd:glass laser; 2 x 400 J beams, 100 ps – 1 us; 1 beam ~100 J, 600 fs – 2 ns Template:Val Template:Val Template:Flagicon Los Alamos LANL File:Alfoil.jpg
Nike laser Operational ≤ 1991-1994 1994- 56-beam, most-capable Krypton fluoride laser for laser target interactions[101][102] Template:Val Template:Val Template:Flagicon Washington, D.C. NRL File:Nike laser amplifier.jpg
OMEGA laser Operational ?-1995 1995- 60-beam UV frequency-tripled Nd:glass laser, fusion yield 1014 neutrons Template:Val Template:Val Template:Val Template:Flagicon Rochester LLE
Electra Operational Krypton fluoride laser, 5 Hz operation with 90,000+ shots continuous Template:Val Template:Val Template:Flagicon Washington D.C. NRL File:Electra Laser System NRL 2013.png
LULI2000 Operational ? 2003- 6-beam Nd:glass laser, λ=Template:Val, λ=Template:Val, λ=Template:Val Template:Val Template:Val Template:Flagicon Palaiseau École polytechnique
OMEGA EP Operational 2008- 60-beam UV Template:Val Template:Val Template:Flagicon Rochester LLE
Script error: No such module "anchor".National Ignition Facility (NIF) Operational 1997-2009 2010- 192-beam Nd:glass laser, achieved scientific breakeven with fusion gain of 1.5 and Template:Val neutrons[103] Template:Val Template:Val Template:Val Template:Flagicon Livermore LLNL File:NIF target chamber construction.jpg
Orion Operational 2006-2010 2010- 10-beams, λ=Template:Val Template:Val Template:Val Template:Flagicon RAF Aldermaston AWE File:Orion target chamber.jpg
Laser Mégajoule (LMJ) Operational 1999-2014 2014- Second-largest laser fusion facility, 10 out of 22 beam lines operational in 2022[104] Template:Val Template:Val Template:Flagicon Bordeaux CEA [1]
Laser for Fast Ignition Experiments (LFEX) Operational 2003-2015 2015- High-contrast heating laser for FIREX, λ=Template:Val Template:Val Template:Val Template:Val Template:Flagicon Osaka Institute for Laser Engineering
HiPER (High Power Laser Energy Research Facility) Template:BLACK 2007-2015 - Pan-European project to demonstrate the technical and economic viability of laser fusion for the production of energy[105] data-sort-value="Template:Val"| (Template:Val) data-sort-value="Template:Val"|(Template:Val) data-sort-value="Template:Val"|(Template:Val) Template:Flagicon File:High Power Laser Energy Research Facility drawing.jpg
Laser Inertial Fusion Energy (LIFE) Template:BLACK 2008-2013 - Effort to develop a fusion power plant succeeding NIF data-sort-value="Template:Val"| (Template:Val) data-sort-value="Template:Val"| (Template:Val) Template:Flagicon Livermore LLNL File:LIFE fusion chamber.jpg
ISKRA-6 Template:Planned ? ? 128 beam Nd:glass laser Template:Val? Template:Val? Template:Flagicon Sarov RFNC-VNIIEF

Z-pinch

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Inertial electrostatic confinement

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Magnetized target fusion

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References

Template:Reflist

See also

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