List of fusion experiments
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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 1018 to 1022 m−3 and the linear dimensions in the range of 0.1 to 10 m. The particle and energy confinement times may range from under a millisecond to over a second, but the configuration itself is often maintained through input of particles, energy, and current for times that are hundreds or thousands of times longer. Some concepts are capable of maintaining a plasma indefinitely.
In contrast, with inertial confinement, there is nothing to counteract the expansion of the plasma. The confinement time is simply the time it takes the plasma pressure to overcome the inertia of the particles, hence the name. The densities tend to be in the range of 1031 to 1033 m−3 and the plasma radius in the range of 1 to 100 micrometers. These conditions are obtained by irradiating a millimeter-sized solid pellet with a nanosecond laser or ion pulse. The outer layer of the pellet is ablated, providing a reaction force that compresses the central 10% of the fuel by a factor of 10 or 20 to 103 or 104 times solid density. These microplasmas disperse in a time measured in nanoseconds. For a reactor, a repetition rate of several per second will be needed.
Contents
Magnetic confinement[edit]
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[edit]
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[edit]
| Device Name | Status | Construction | Operation | Location | Organisation | Major/Minor Radius | B-field | Plasma current | Purpose | Image |
|---|---|---|---|---|---|---|---|---|---|---|
| T-1 | Shut down | ? | 1957-1959 | Moscow |
Kurchatov Institute | 0.625 m/0.13 m | 1 T | 0.04 MA | First tokamak | |
| T-3 | Shut down | ? | 1962-? | Moscow |
Kurchatov Institute | 1 m/0.12 m | 2.5 T | 0.06 MA | ||
| ST (Symmetric Tokamak) | Shut down | Model C | 1970-1974 | Princeton |
Princeton Plasma Physics Laboratory | 1.09 m/0.13 m | 5.0 T | 0.13 MA | First American tokamak, converted from Model C stellarator | |
| ORMAK (Oak Ridge tokaMAK) | Shut down | 1971-1976 | Oak Ridge |
Oak Ridge National Laboratory | 0.8 m/0.23 m | 2.5 T | 0.34 MA | First to achieve 20 MK plasma temperature | ||
| ATC (Adiabatic Toroidal Compressor) | Shut down | 1971-1972 | 1972-1976 | Princeton |
Princeton Plasma Physics Laboratory | 0.88 m/0.11 m | 2 T | 0.05 MA | Demonstrate compressional plasma heating | |
| TFR (Tokamak de Fontenay-aux-Roses) | Shut down | 1973-1984 | Fontenay-aux-Roses |
CEA | 1 m/0.2 m | 6 T | 0.49 | |||
| T-10 (Tokamak-10) | Shut down | 1975-? | Moscow |
Kurchatov Institute | 1.50 m/0.36 m | 4 T | 0.6 MA | Largest tokamak of its time | ||
| PLT (Princeton Large Torus) | Shut down | 1975-1986 | Princeton |
Princeton Plasma Physics Laboratory | 1.32 m/0.4 m | 4 T | 0.7 MA | First to achieve 1 MA plasma current | ||
| TEXTOR (Tokamak Experiment for Technology Oriented Research)[1][2] | Shut down | 1976-1980 | 1981-2013 | Jülich |
Forschungszentrum Jülich | 1.75 m/0.47 m | 2.8 T | 0.8 MA | Study plasma-wall interactions | |
| TFTR (Tokamak Fusion Test Reactor)[3] | Shut down | 1980-1982 | 1982-1997 | Princeton |
Princeton Plasma Physics Laboratory | 2.4 m/0.8 m | 6 T | 3 MA | Attempted scientific break-even, reached record fusion power of 10.7 MW and temperature of 510 MK | |
| JET (Joint European Torus)[4] | Operational | 1978-1983 | 1983- | Culham |
Culham Centre for Fusion Energy | 2.96 m/0.96 m | 4 T | 7 MA | Record for fusion output power 16.1 MW | |
| Novillo[5][6] | Shut down | NOVA-II | 1983-2004 | Mexico City |
Instituto Nacional de Investigaciones Nucleares | 0.23 m/0.06 m | 1 T | 0.01 MA | Study plasma-wall interactions | |
| JT-60 (Japan Torus-60)[7] | Recycled →JT-60SA | 1985-2010 | Naka |
Japan Atomic Energy Research Institute | 3.4 m/1.0 m | 4 T | 3 MA | High-beta steady-state operation, highest fusion triple product | ||
| DIII-D[8] | Operational | 1986[9] | 1986- | San Diego |
General Atomics | 1.67 m/0.67 m | 2.2 T | 3 MA | Tokamak Optimization | |
| STOR-M (Saskatchewan Torus-Modified)[10] | Operational | 1987- | Saskatoon |
Plasma Physics Laboratory (Saskatchewan) | 0.46 m/0.125 m | 1 T | 0.06 MA | Study plasma heating and anomalous transport | ||
| T-15 | Recycled →T-15MD | 1983-1988 | 1988-1995 | Moscow |
Kurchatov Institute | 2.43 m/0.7 m | 3.6 T | 1 MA | First superconducting tokamak. | |
| Tore Supra[11] | Recycled →WEST | 1988-2011 | Cadarache |
Département de Recherches sur la Fusion Contrôlée | 2.25 m/0.7 m | 4.5 T | 2 MA | Large superconducting tokamak with active cooling | ||
| ADITYA (tokamak) | Operational | 1989- | Gandhinagar |
Institute for Plasma Research | 0.75 m/0.25 m | 1.2 T | 0.25 MA | |||
| COMPASS (COMPact ASSembly)[12][13] | Operational | 1980- | 1989- | Prague |
Institute of Plasma Physics AS CR | 0.56 m/0.23 m | 2.1 T | 0.32 MA | ||
| FTU (Frascati Tokamak Upgrade) | Operational | 1990- | Frascati |
ENEA | 0.935 m/0.35 m | 8 T | 1.6 MA | |||
| START (Small Tight Aspect Ratio Tokamak)[14] | Shut down | 1990-1998 | Culham |
Culham Centre for Fusion Energy | 0.3 m/? | 0.5 T | 0.31 MA | First full-sized Spherical Tokamak | ||
| ASDEX Upgrade (Axially Symmetric Divertor Experiment) | Operational | ASDEX | 1991- | Garching |
Max-Planck-Institut für Plasmaphysik | 1.65 m/0.5 m | 2.6 T | 1.4 MA | Discovery of the H-mode | |
| Alcator C-Mod (Alto Campo Toro)[15] | Shut down | 1986- | 1991-2016 | Cambridge |
Massachusetts Institute of Technology | 0.68 m/0.22 m | 8 T | 2 MA | record plasma pressure 2.05 bar | |
| ISTTOK (Instituto Superior Técnico TOKamak)[16] | Operational | 1992- | Lisbon |
Instituto de Plasmas e Fusão Nuclear | 0.46 m/0.085 m | 2.8 T | 0.01 MA | |||
| TCV (Tokamak à Configuration Variable)[17] | Operational | 1992- | Lausanne |
École Polytechnique Fédérale de Lausanne | 0.88 m/0.25 m | 1.43 T | 1.2 MA | Confinement studies | ||
| Pegasus Toroidal Experiment[18] | Operational | ? | 1996- | Madison |
University of Wisconsin–Madison | 0.45 m/0.4 m | 0.18 T | 0.3 MA | Extremely low aspect ratio | |
| NSTX (National Spherical Torus Experiment)[19] | Operational | 1999- | Plainsboro Township |
Princeton Plasma Physics Laboratory | 0.85 m/0.68 m | 0.3 T | 2 MA | Study the spherical tokamak concept | ||
| ET (Electric Tokamak) | Recycled →ETPD | 1998 | 1999-2006 | Los Angeles |
UCLA | 5 m/1 m | 0.25 T | 0.045 | Largest tokamak of its time | |
| CDX-U (Current Drive Experiment-Upgrade) | Recycled →LTX | 2000-2005 | Princeton |
Princeton Plasma Physics Laboratory | 0.3 m/? m | 0.23 T | 0.03 MA | Study Lithium in plasma walls | ||
| MAST (Mega-Ampere Spherical Tokamak)[20] | Recycled →MAST-Upgrade | 1997-1999 | 1999-2013 | Culham |
Culham Centre for Fusion Energy | 0.9 m/0.6 m | 0.55 T | 1.4 MA | Investigate spherical tokamak for fusion | |
| SST-1 (Steady State Superconducting Tokamak)[21] | Operational | 2001- | 2005- | Gandhinagar |
Institute for Plasma Research | 1.1 m/0.2 m | 3 T | 0.22 MA | Produce a 1000s elongated double null divertor plasma | |
| EAST (Experimental Advanced Superconducting Tokamak)[22] | Operational | 2003-2006 | 2006- | Hefei |
Hefei Institutes of Physical Science | 1.85 m/0.4 5m | 3.5 T | 0.5 MA | H-Mode plasma for over 100 s at 50 MK | |
| KSTAR (Korea Superconducting Tokamak Advanced Research)[23] | Operational | 1998-2007 | 2008- | Daejeon |
National Fusion Research Institute | 1.8 m/0.5 m | 3.5 T | 2 MA | Tokamak with fully superconducting magnets | |
| LTX (Lithium Tokamak Experiment) | Operational | 2005-2008 | 2008- | Princeton |
Princeton Plasma Physics Laboratory | 0.4 m/? m | 0.4 T | 0.4 MA | Study Lithium in plasma walls | |
| QUEST (Spherical Tokamak)[24] | Operational | 2008- | Kasuga |
Kyushu University | 0.68 m/0.4 m | 0.25 T | 0.02 MA | Study steady state operation of a Spherical Tokamak | ||
| Kazakhstan Tokamak for Material testing (KTM) | Operational | 2000-2010 | 2010- | Kurchatov |
National Nuclear Center of the Republic of Kazakhstan | 0.86 m/0.43 m | 1 T | 0.75 MA | Testing of wall and divertor | |
| ST25-HTS[25] | Operational | 2012-2015 | 2015- | Culham |
Tokamak Energy Ltd | 0.25 m/0.125 m | 0.1 T | 0.02 MA | Steady state plasma | |
| WEST (Tungsten Environment in Steady-state Tokamak) | Operational | 2013-2016 | 2016- | Cadarache |
Département de Recherches sur la Fusion Contrôlée | 2.5 m/0.5 m | 3.7 T | 1 MA | Superconducting tokamak with active cooling | |
| ST40[26] | Operational | 2017-2018 | 2018- | Culham |
Tokamak Energy Ltd | 0.4 m/0.3 m | 3 T | 2 MA | First high field spherical tokamak | |
| JT-60SA (Japan Torus-60 super, advanced)[27] | Under construction | 2013-2020? | 2020? | Naka |
Japan Atomic Energy Research Institute | 2.96 m/1.18 m | 2.25 T | 5.5 MA | Optimise plasma configurations for ITER and DEMO with full non-inductive steady-state operation | |
| ITER[28] | Under construction | 2013- | 2025? | Cadarache |
ITER Council | 6.2 m/2.0 m | 5.3 T | 15 MA ? | Demonstrate feasibility of fusion on a power-plant scale with 500 MW fusion power | |
| DTT (Divertor Tokamak Test facility)[29] | Planned | ? | 2022? | Frascati |
ENEA | 2.15 m/0.70 m | 6 T ? | 6 MA ? | Divertor design | |
| IGNITOR[30] | Planned[31] | ? | >2024 | Troitzk |
ENEA | 1.32 m/0.47 m | 13 T | 11 MA ? | Compact fustion reactor with self-sustained plasma and 100 MW of planned fusion power | |
| CFETR (China Fusion Engineering Test Reactor)[32] | Planned | 2020? | 2030? | Institute of Plasma Physics, Chinese Academy of Sciences | 5.7 m ? | 5 T ? | 10 MA ? | Bridge gaps between ITER and DEMO, planned fusion power 1000 MW | ||
| K-DEMO (Korean fusion demonstration tokamak reactor)[33] | Planned | 2037? | National Fusion Research Institute | 6.8 m/2.1 m | 7 T | 12 MA ? | Prototype for the development of commercial fusion reactors with around 2200 MW of fusion power | |||
| DEMO (DEMOnstration Power Station) | Planned | 2031? | 2044? | ? | 9 m/3 m ? | 6 T ? | 20 MA ? | Prototype for a commercial fusion reactor |
Stellarator[edit]
| Device Name | Status | Construction | Operation | Type | Location | Organisation | Major/Minor Radius | B-field | Purpose | Image |
|---|---|---|---|---|---|---|---|---|---|---|
| Model C | Recycled →ST | 1958-1962 | 1962-1969 | Racetrack | Princeton |
Princeton Plasma Physics Laboratory | 1.9 m/0.07 m | 3.5 T | Found large plasma losses by Bohm diffusion | |
| Wendelstein 2-A | Shut down | 1965-1968 | 1968-1974 | Heliotron | Garching |
Max-Planck-Institut für Plasmaphysik | 0.5 m/0.05 m | 0.6 T | Good plasma confinement “Munich mystery” | |
| Wendelstein 2-B | Shut down | ?-1970 | 1971-? | Heliotron | Garching |
Max-Planck-Institut für Plasmaphysik | 0.5 m/0.05 m | 1.25 T | Demonstrated similar performance than tokamaks | |
| WEGA | Recycled →HIDRA | ? | 1975-2013 | Classical stellarator | Greifswald |
Max-Planck-Institut für Plasmaphysik | 0.72 m/0.15 m | 1.4 T | Test lower hybrid heating | |
| Wendelstein 7-A | Shut down | ? | 1975-1985 | Classical stellarator | Garching |
Max-Planck-Institut für Plasmaphysik | 2 m/0.1 m | 3.5 T | First "pure" stellarator without plasma current | |
| Wendelstein 7-AS | Shut down | 1985-1986 | 1988-2002 | Modular, advanced stellarator | Garching |
Max-Planck-Institut für Plasmaphysik | 2 m/0.13 m | 2.6 T | First H-mode in a stellarator in 1992 | |
| H-1NF[34] | Operational | 1992- | Heliac | Canberra |
Research School of Physical Sciences and Engineering, Australian National University | 1.0 m/0.19 m | 0.5 T | |||
| TJ-K[35] | Operational | TJ-IU | 1994- | Torsatron | Kiel, Stuttgart |
University of Stuttgart | 0.60 m/0.10 m | 0.5 T | Teaching | |
| TJ-II[36] | Operational | 1991- | 1997- | flexible Heliac | Madrid |
National Fusion Laboratory, Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas (Ciemat) | 1.5 m/0.28 m | 1.2 T | Study plasma in flexible configuration | |
| LHD (Large Helical Device)[37] | Operational | 1990-1998 | 1998- | Heliotron | Toki |
National Institute for Fusion Science | 3.5 m/0.6 m | 3 T | Determine feasibility of a stellarator fusion reactor | |
| HSX (Helically Symmetric Experiment) | Operational | 1999- | Modular, quasi-helically symmetric | Madison |
University of Wisconsin–Madison | 1.2 m/0.15 m | 1 T | investigate plasma transport | ||
| Uragan-2(M)[38] | ? | ? | ? | Heliotron, Torsatron | Kharkiv |
National Science Center, Kharkiv Institute of Physics and Technology (NSC KIPT) | 1.7 m/0.24 m | 2.4 T | ? | |
| Uragan-3 (M)[39] | ? | ? | ? | Heliotron, Torsatron | Kharkiv |
National Science Center, Kharkiv Institute of Physics and Technology (NSC KIPT) | 1.0 m/0.12 m | 1.3 T | ? | |
| Columbia Non-neutral Torus (CNT) | Operational | ? | 2004- | Circular interlocked coils | New York City |
Columbia University | 0.3 m/0.1 m | 0.2 T | Study of non-neutral plasmas | |
| Quasi-poloidal stellarator (QPS)[40][41] | Cancelled | 2001-2007 | - | Modular | Oak Ridge |
Oak Ridge National Laboratory | 0.9 m/0.33 m | 1.0 T | Stellarator research | |
| NCSX (National Compact Stellarator Experiment) | Cancelled | 2004-2008 | - | ? | Princeton |
Princeton Plasma Physics Laboratory | 1.4 m/0.32 m | 1.7 T | High-β stability | |
| Compact Toroidal Hybrid (CTH) | Operational | ? | 2007?- | Torsatron | Auburn |
Auburn University | 0.75 m/0.2 m | 0.7 T | Hybrid stellarator/tokamak | |
| HIDRA (Hybrid Illinois Device for Research and Applications)[42] | Operational | 2013-2014 (WEGA) | 2014- | ? | Urbana, IL |
University of Illinois at Urbana - Champaign | 0.72 m/0.19 m | 0.5 T | Stellarator and Tokamak in one device | |
| Wendelstein 7-X[43] | Operational | 1996-2015 | 2015- | Helias | Greifswald |
Max-Planck-Institut für Plasmaphysik | 5.5 m/0.53 m | 3 T | Steady-state plasma in fully optimized stellarator | |
| SCR-1 (Stellarator of Costa Rica) | Operational | 2011-2015 | 2016- | Modular | Cartago |
Instituto Tecnológico de Costa Rica | 0.14 m/0.042 m | 0.044 T |
Reversed field pinch (RFP)[edit]
- RFX (Reversed-Field eXperiment), Consorzio RFX, Padova, Italy[44]
- MST (Madison Symmetric Torus), University of Wisconsin–Madison, United States[45]
- T2R, Royal Institute of Technology, Stockholm, Sweden
- TPE-RX, AIST, Tsukuba, Japan
Magnetic mirror[edit]
- Baseball I/Baseball II Lawrence Livermore National Laboratory, Livermore CA.
- TMX, TMX-U Lawrence Livermore National Laboratory, Livermore CA.
- MFTF Lawrence Livermore National Laboratory, Livermore CA.
- Gas Dynamic Trap at Budker Institute of Nuclear Physics, Akademgorodok, Russia.
Spheromak[edit]
Field-Reversed Configuration (FRC)[edit]
- C-2 Tri Alpha Energy
- C-2U Tri Alpha Energy
- C-3 (under construction?) Tri Alpha Energy
- LSX University of Washington
- IPA University of Washington
- HF University of Washington
- IPA- HF University of Washington
Open field lines[edit]
Plasma pinch[edit]
- Trisops - 2 facing theta-pinch guns
Levitated Dipole[edit]
- Levitated Dipole Experiment (LDX), MIT/Columbia University, United States[46]
Inertial confinement[edit]
Laser-driven[edit]
Current or under construction experimental facilities[edit]
Solid state lasers[edit]
- National Ignition Facility (NIF) at LLNL in California, US[47]
- Laser Mégajoule of the Commissariat à l'Énergie Atomique in Bordeaux, France (under construction)[48]
- OMEGA EL Laser at the Laboratory for Laser Energetics, Rochester, US
- Gekko XII at the Institute for Laser Engineering in Osaka, Japan
- ISKRA-4 and ISKRA-5 Lasers at the Russian Federal Nuclear Center VNIIEF[49]
- Pharos laser, 2 beam 1 kJ/pulse (IR) Nd:Glass laser at the Naval Research Laboratories
- Vulcan laser at the central Laser Facility, Rutherford Appleton Laboratory, 2.6 kJ/pulse (IR) Nd:glass laser
- Trident laser, at LANL; 3 beams total; 2 x 400 J beams, 100 ps – 1 us; 1 beam ~100 J, 600 fs – 2 ns.
Gas lasers[edit]
- NIKE laser at the Naval Research Laboratories, Krypton Fluoride gas laser
- PALS, formerly the "Asterix IV", at the Academy of Sciences of the Czech Republic,[50] 1 kJ max. output iodine laser at 1.315 micrometre fundamental wavelength
Dismantled experimental facilities[edit]
Solid-state lasers[edit]
- 4 pi laser built during the mid 1960s at Lawrence Livermore National Laboratory
- Long path laser built at LLNL in 1972
- The two beam Janus laser built at LLNL in 1975
- The two beam Cyclops laser built at LLNL in 1975
- The two beam Argus laser built at LLNL in 1976
- The 20 beam Shiva laser built at LLNL in 1977
- 24 beam OMEGA laser completed in 1980 at the University of Rochester's Laboratory for Laser Energetics
- The 10 beam Nova laser (dismantled) at LLNL. (First shot taken, December 1984 – final shot taken and dismantled in 1999)
Gas lasers[edit]
- "Single Beam System" or simply "67" after the building number it was housed in, a 1 kJ carbon dioxide laser at Los Alamos National Laboratory
- Gemini laser, 2 beams, 2.5 kJ carbon dioxide laser at LANL
- Helios laser, 8 beam, ~10 kJ carbon dioxide laser at LANL — Media at Wikimedia Commons
- Antares laser at LANL. (40 kJ CO2 laser, largest ever built, production of hot electrons in target plasma due to long wavelength of laser resulted in poor laser/plasma energy coupling)
- Aurora laser 96 beam 1.3 kJ total krypton fluoride (KrF) laser at LANL
- Sprite laser few joules/pulse laser at the Central Laser Facility, Rutherford Appleton Laboratory
Z-Pinch[edit]
- Z Pulsed Power Facility
- ZEBRA device at the University of Nevada's Nevada Terawatt Facility[51]
- Saturn accelerator at Sandia National Laboratory[52]
- MAGPIE at Imperial College London
- COBRA at Cornell University
- PULSOTRON[53]
Inertial electrostatic confinement[edit]
Magnetized target fusion[edit]
- FRX-L
- FRCHX
- General Fusion - under development
- LINUS project
References[edit]
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- ^ Progress in Fusion Research - 30 Years of TEXTOR
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- ^ The Russian-Italian IGNITOR Tokamak Project: Design and status of implementation (2017)
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- ^ Kim, K.; Im, K.; Kim, H. C.; Oh, S.; Park, J. S.; Kwon, S.; Lee, Y. S.; Yeom, J. H.; Lee, C. (2015). "Design concept of K-DEMO for near-term implementation". Nuclear Fusion. 55 (5): 053027. Bibcode:2015NucFu..55e3027K. doi:10.1088/0029-5515/55/5/053027. ISSN 0029-5515.
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- ^ "History | ННЦ ХФТИ". www.kipt.kharkov.ua.
- ^ "QPS Home Page".
- ^ http://qps.fed.ornl.gov/pvr/pdf/qpsentire.pdf
- ^ "HIDRA – Hybrid Illinois Device for Research and Applications | CPMI - Illinois". cpmi.illinois.edu.
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- ^ "University of Nevada, Reno. Nevada Terawatt Facility". archive.is. 2000-09-19.
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- ^ "PULSOTRON". pulsotron.org.