聚变实验列表

用于发展聚变能的实验总是会使用专门的装置，这些装置可以根据他们使用的聚变原理和燃料自持方式来进行区分。

主要区分为磁约束和惯性约束两种。在磁约束中，热等离子体膨胀的趋势被等离子体中的电流和外部线圈产生的磁场之间的洛伦兹力抵消。粒子密度范围趋向于-，线性尺寸范围为0.1 m至10m。 粒子和能量约束时间在从几毫秒到超过一秒的范围内，但是配置本身通常通过输入粒子、能量和电流来维持数倍或数千倍的时间。一些理论能够无限期地维持等离子体。

 磁约束 

 环形器 
环形器可以是轴对称的，例如托卡马克和，也可以是不对称的，比如仿星器。通过放弃环形对称性而获得的额外的自由度可能最终可以产生更好的约束，但工程、理论和实验诊断上的成本十分复杂。仿星器通常具有周期性，例如五倍的旋转对称。反场箍缩，尽管具有一些理论上的优势，例如低磁场线圈，还没有证明是成功的。

 托卡马克 
装置名称状态建造时间运行时间地点所属组织最大/最小半径磁场等离子电流备注照片T-1  ?1957-1959莫斯科 库尔恰托夫研究所0.625 m/0.13 m1 T0.04 MA首台托卡马克无框|T-1T-3  ?1962-?莫斯科 库尔恰托夫研究所1 m/0.12 m2.5 T0.06 MAST (Symmetric Tokamak)  Model C1970-1974普林斯顿 普林斯顿等离子体物理实验室1.09 m/0.13 m5.0 T0.13 MA美国首台托卡马克，从Model C仿星器改造而来ORMAK (Oak Ridge tokaMAK)  1971-1976橡树岭 橡树岭国家实验室0.8 m/0.23 m2.5 T0.34 MA等离子体温度首次达到20 MKATC   1971-19721972-1976普林斯顿 普林斯顿等离子体物理实验室0.88 m/0.11 m2 T0.05 MA演示了等离子体压缩无框|Schematic of ATCTFR (Tokamak de Fontenay-aux-Roses)  1973-1984丰特奈-欧罗斯 原子能和替代能源委员会1 m/0.2 m6 T0.49T-10 (Tokamak-10)  1975-?莫斯科 库尔恰托夫研究所1.50 m/0.36 m4 T0.6 MA当时最大的托卡马克装置无框|Model of the T-10PLT (Princeton Large Torus)  1975-1986普林斯顿 普林斯顿等离子体物理实验室1.32 m/0.4 m4 T0.7 MA等离子体电流首次达到1 MA无框|Construction of the Princeton Large TorusASDEX (Axially Symmetric Divertor Experiment)  →HL-2A 1980-1990加兴 Max-Planck-Institut für Plasmaphysik1.65 m/0.4 m2.8 T0.5 MA1982年发现了TEXTOR Progress in Fusion Research - 30 Years of TEXTOR  1976-19801981-2013于利希 于利希研究中心1.75 m/0.47 m2.8 T0.8 MA研究等离子体-壁相互作用TFTR (Tokamak Fusion Test Reactor)  1980-19821982-1997普林斯顿 普林斯顿等离子体物理实验室2.4 m/0.8 m6 T3 MA创造了聚变能输出10.7 MW、等离子体温度510 MK的纪录无框|TFTR plasma vesselJET   1978-19831983-卡尔汉姆 Culham Centre for Fusion Energy2.96 m/0.96 m4 T7 MA创造了聚变能输出16.1 MW的纪录无框|JET in 1991  NOVA-II1983-2004墨西哥城 Instituto Nacional de Investigaciones Nucleares0.23 m/0.06 m1 T0.01 MA研究等离子体-壁相互作用JT-60 (Japan Torus-60)  →JT-60SA 1985-2010那珂市 Japan Atomic Energy Research Institute3.4 m/1.0 m4 T3 MAHigh-beta steady-state operation, highest fusion triple productDIII-D  19861986-聖地牙哥 (加利福尼亞州) General Atomics1.67 m/0.67 m2.2 T3 MA托卡马克优化设计无框|DIII-D vacuum vesselSTOR-M (Saskatchewan Torus-Modified)  1987-萨斯卡通 Plasma Physics Laboratory (Saskatchewan)0.46 m/0.125 m1 T0.06 MA研究等离子体加热和反常运输T-15  →T-15MD 1983-19881988-1995莫斯科 库尔恰托夫研究所2.43 m/0.7 m3.6 T1 MA首台超导托卡马克无框|T-15 coil systemTore Supra  →WEST 1988-2011卡达拉舍 Département de Recherches sur la Fusion Contrôlée2.25 m/0.7 m4.5 T2 MA主动冷却的大型托卡马克ADITYA (tokamak)  1989-甘地讷格尔 Institute for Plasma Research0.75 m/0.25 m1.2 T0.25 MACOMPASS (COMPact ASSembly)  1980-1989-布拉格 Institute of Plasma Physics AS CR0.56 m/0.23 m2.1 T0.32 MA无框|COMPASS plasma chamberFTU   1990-弗拉斯卡蒂 ENEA0.935 m/0.35 m8 T1.6 MASTART   1990-1998卡尔汉姆 Culham Centre for Fusion Energy0.3 m/?0.5 T0.31 MA首台全尺寸球形托卡马克ASDEX Upgrade (Axially Symmetric Divertor Experiment)  1991-加兴 Max-Planck-Institut für Plasmaphysik1.65 m/0.5 m2.6 T1.4 MA无框|ASDEX Upgrade plasma vessel segmentAlcator C-Mod (Alto Campo Toro)  1986-1991-2016剑桥 麻省理工学院0.68 m/0.22 m8 T2 MA创造了等离子体压力2.05 bar的纪录无框|Alcator C-Mod plasma vesselISTTOK (Instituto Superior Técnico TOKamak)  1992-里斯本 Instituto de Plasmas e Fusão Nuclear0.46 m/0.085 m2.8 T0.01 MATCV (Tokamak à Configuration Variable)  1992-洛桑 洛桑联邦理工学院0.88 m/0.25 m1.43 T1.2 MA聚变研究无框|TCV plasma vesselPegasus Toroidal Experiment  ?1996-麦迪逊 威斯康星大学麦迪逊分校0.45 m/0.4 m0.18 T0.3 MA极低长宽比无框|Pegasus Toroidal ExperimentNSTX (National Spherical Torus Experiment)  1999-平原镇Plainsboro Township 普林斯顿等离子体物理实验室0.85 m/0.68 m0.3 T2 MA研究球形托卡马克理论无框|National Spherical Torus ExperimentET (Electric Tokamak)  →ETPD 19981999-2006洛杉矶 加利福尼亚大学洛杉矶分校5 m/1 m0.25 T0.045当时最大的托卡马克装置无框|The Electric Tokamak.jpgCDX-U (Current Drive Experiment-Upgrade)  →LTX 2000-2005普林斯顿 普林斯顿等离子体物理实验室0.3 m/? m0.23 T0.03 MAStudy Lithium in plasma walls无框|CDX-U setupMAST (Mega-Ampere Spherical Tokamak)  →MAST-Upgrade 1997-19991999-2013卡尔汉姆 Culham Centre for Fusion Energy0.9 m/0.6 m0.55 T1.4 MA研究球形托卡马克聚变无框|Plasma in MASTSST-1 (Steady State Superconducting Tokamak)  2001-2005-甘地讷格尔 Institute for Plasma Research1.1 m/0.2 m3 T0.22 MAProduce a 1000s elongated double null divertor plasmaEAST   2003-20062006-合肥 中国科学院合肥物质科学研究院1.85 m/0.4 5m3.5 T0.5 MAH模式等离子体在50 MK时自持超过100 s无框|EAST plasma vesselKSTAR   1998-20072008-大田广域市 National Fusion Research Institute1.8 m/0.5 m3.5 T2 MA全超导托卡马克无框|KSTARLTX (Lithium Tokamak Experiment)  2005-20082008-普林斯顿 普林斯顿等离子体物理实验室0.4 m/? m0.4 T0.4 MAStudy Lithium in plasma walls无框|Lithium Tokamak Experiment plasma vesselQUEST (Spherical Tokamak)  2008-春日市 Kyushu University0.68 m/0.4 m0.25 T0.02 MA研究球形托卡马克中的稳态等离子体Kazakhstan Tokamak for Material testing (KTM)  2000-20102010-库尔恰托夫 National Nuclear Center of the Republic of Kazakhstan0.86 m/0.43 m1 T0.75 MATesting of wall and divertorST25-HTS  2012-20152015-卡尔汉姆 Tokamak Energy Ltd0.25 m/0.125 m0.1 T0.02 MA稳态等离子体无框|ST25-HTS with plasmaWEST (Tungsten Environment in Steady-state Tokamak)  2013-20162016-卡达拉舍 Département de Recherches sur la Fusion Contrôlée2.5 m/0.5 m3.7 T1 MA主动冷却超导托卡马克无框|WEST designST40  2017-20182018-卡尔汉姆 Tokamak Energy Ltd0.4 m/0.3 m3 T2 MA首台球形强场托卡马克无框|ST40 engineering drawingJT-60SA (Japan Torus-60 super, advanced)  2013-2020?2020?那珂 Japan Atomic Energy Research Institute2.96 m/1.18 m2.25 T5.5 MAOptimise plasma configurations for ITER and DEMO with full non-inductive steady-state operation无框|panorama of JT-60SAITER  2013-2025?卡达拉舍 ITER Council6.2 m/2.0 m5.3 T15 MA ?Demonstrate feasibility of fusion on a power-plant scale with 500 MW fusion power无框|Small-scale model of ITERDTT (Divertor Tokamak Test facility)  ?2022?弗拉斯卡蒂 ENEA2.15 m/0.70 m6 T ?6 MA ?Divertor designIGNITOR  ?>2024特羅伊茨克 (車里雅賓斯克州) ENEA1.32 m/0.47 m13 T11 MA ?Compact fustion reactor with self-sustained plasma and 100 MW of planned fusion powerCFETR   2020?2030?中国科学院等离子体物理研究所5.7 m ?5 T ?10 MA ?Bridge gaps between ITER and DEMO, planned fusion power 1000 MWK-DEMO   2037?National Fusion Research Institute6.8 m/2.1 m7 T12 MA ?Prototype for the development of commercial fusion reactors with around 2200 MW of fusion power无框|Engineering drawing of planned KDEMODEMO   2031?2044??9 m/3 m ?6 T ?20 MA ?Prototype for a commercial fusion reactor无框|Schematic of a DEMO nucelar fusion power plant with around 2-4 GW of fusion power

 仿星器 
Device NameStatusConstructionOperationTypeLocationOrganisationMajor/Minor RadiusB-fieldPurposeImageModel A  1952-19531953-?Figure-8普林斯顿 普林斯顿等离子体物理实验室0.3 m/0.02 m0.1 TFirst stellaratorModel B  1953-19541954-1959Figure-8普林斯顿 普林斯顿等离子体物理实验室0.3 m/0.02 m5 TDevelopment of plasma diagnosticsModel B-2  Figure-8普林斯顿 普林斯顿等离子体物理实验室0.3 m/0.02 m5 TModel B-3  1958Figure-8普林斯顿 普林斯顿等离子体物理实验室0.4 m/0.02 m4 TModel B-64  1955Square普林斯顿 普林斯顿等离子体物理实验室? m/0.05 m1.8 TModel B-65  Racetrack普林斯顿 普林斯顿等离子体物理实验室Model B-66  普林斯顿普林斯顿等离子体物理实验室Wendelstein 1-A  1960Racetrack加兴 Max-Planck-Institut für Plasmaphysik0.35 m/0.02 m2 Tℓ=3Wendelstein 1-B  1960Racetrack加兴 Max-Planck-Institut für Plasmaphysik0.35 m/0.02 m2 Tℓ=2Model C  →ST 1957-19621962-1969Racetrack普林斯顿 普林斯顿等离子体物理实验室1.9 m/0.07 m3.5 TFound large plasma losses by Bohm diffusionL-1  19631963-1971Lebedev Lebedev Physical Institute0.6 m/0.05 m1 TSIRIUS  1964-?哈尔科夫 TOR-1  19671967-1973Lebedev Lebedev Physical Institute0.6 m/0.05 m1 TTOR-2  ?1967-1973Lebedev 列别杰夫物理研究所0.63 m/0.036 m2.5 TWendelstein 2-A  1965-19681968-1974Heliotron加兴 Max-Planck-Institut für Plasmaphysik0.5 m/0.05 m0.6 TGood plasma confinement “Munich mystery”无框|Wendelstein 2-AWendelstein 2-B  ?-19701971-?Heliotron加兴 Max-Planck-Institut für Plasmaphysik0.5 m/0.055 m1.25 TDemonstrated similar performance than tokamaks无框|Wendelstein 2-BL-2  ?1975-?Lebedev Lebedev Physical Institute1 m/0.11 m2.0 TWEGA  →HIDRA 1972-19751975-2013Classical stellarator格赖夫斯瓦尔德 Max-Planck-Institut für Plasmaphysik0.72 m/0.15 m1.4 TTest lower hybrid heating无框|WEGAWendelstein 7-A  ?1975-1985Classical stellarator加兴 Max-Planck-Institut für Plasmaphysik2 m/0.1 m3.5 TFirst "pure" stellarator without plasma currentHeliotron-E  ?1980-?Heliotron2.2 m/0.2 m1.9 THeliotron-DR  ?1981-?Heliotron0.9 m/0.07 m0.6 TAuburn Torsatron  ?1984-1990Torsatron奥本 奧本大學0.58 m/0.14 m0.2 T  1982-19881988-2002Modular, advanced stellarator加兴 Max-Planck-Institut für Plasmaphysik2 m/0.13 m2.6 TFirst H-mode in a stellarator in 1992无框|Wendelstein 7-ASCompact Helical System (CHS)  ?1989-?Heliotron土岐 National Institute for Fusion Science1 m/0.2 m1.5 TCompact Auburn Torsatron (CAT)  ?-19901990-2000Torsatron奥本 奧本大學0.53 m/0.11 m0.1 TStudy magnetic flux surfacesH-1NF  1992-Heliac堪培拉 Research School of Physical Sciences and Engineering, Australian National University1.0 m/0.19 m0.5 T无框|H-1NF plasma vesselTJ-K  TJ-IU1994-Torsatron基尔 斯图加特大学0.60 m/0.10 m0.5 TTeachingTJ-II  1991-1997-flexible Heliac马德里 National Fusion Laboratory, Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas (Ciemat)1.5 m/0.28 m1.2 TStudy plasma in flexible configurationLHD (Large Helical Device)  1990-19981998-Heliotron土岐 National Institute for Fusion Science3.5 m/0.6 m3 TDetermine feasibility of a stellarator fusion reactor无框|LHD cross sectionHSX (Helically Symmetric Experiment)  1999-Modular, quasi-helically symmetric麦迪逊 University of Wisconsin–Madison1.2 m/0.15 m1 Tinvestigate plasma transport无框|HSX with clearly visible non-planar coilsHeliotron J (Heliotron J)  2000-Heliotron京都 Institute of Advanced Energy1.2 m/0.1 m1.5 TStudy helical-axis heliotron configurationUragan-2(M)???Heliotron, Torsatron哈尔科夫 National Science Center, Kharkiv Institute of Physics and Technology (NSC KIPT)1.7 m/0.24 m2.4 T?Uragan-3 ()???Torsatron哈尔科夫 National Science Center, Kharkiv Institute of Physics and Technology (NSC KIPT)1.0 m/0.12 m1.3 T?Columbia Non-neutral Torus (CNT)  ?2004-Circular interlocked coils纽约 哥伦比亚大学0.3 m/0.1 m0.2 TStudy of non-neutral plasmasQuasi-poloidal stellarator (QPS)http://qps.fed.ornl.gov/pvr/pdf/qpsentire.pdf  2001-2007 -Modular橡树岭 橡树岭国家实验室0.9 m/0.33 m1.0 TStellarator research无框|Engineering drawing of the QPSNCSX (National Compact Stellarator Experiment)  2004-2008 -Helias普林斯顿 普林斯顿等离子体物理实验室1.4 m/0.32 m1.7 THigh-β stability无框|CAD drawing of NCSXCompact Toroidal Hybrid (CTH)  ?2007?-Torsatron奥本 奧本大學0.75 m/0.2 m0.7 THybrid stellarator/tokamakHIDRA (Hybrid Illinois Device for Research and Applications)  2013-2014 (WEGA)2014-?厄巴纳 (伊利诺伊州)University of Illinois at Urbana - Champaign0.72 m/0.19 m0.5 T仿星器和托卡马克合二为一的装置无框|HIDRA after its reasemmbly in IllinoisUST_2  20132014-modular three period quasi-isodynamic马德里 Charles III University of Madrid0.29 m/0.04 m0.089 T3D printed stellarator无框|UST_2 design conceptWendelstein 7-X  1996-20152015-Helias格赖夫斯瓦尔德 马克斯-普朗克等离子体物理研究所5.5 m/0.53 m3 TSteady-state plasma in fully optimized stellarator无框|Schematic diagram of Wendelstein 7-XSCR-1 (Stellarator of Costa Rica)  2011-20152016-Modular卡塔戈 Instituto Tecnológico de Costa Rica0.14 m/0.042 m0.044 T无框|SCR-1 vacuum vessel drawing


 RFX (Reversed-Field eXperiment), Consorzio RFX, Padova, Italy
 MST (Madison Symmetric Torus), 威斯康星大学麦迪逊分校, United States
 T2R, Royal Institute of Technology, Stockholm, Sweden
 TPE-RX, AIST, Tsukuba, Japan
 KTX (Keda Torus eXperiment) in China (since 2015)

 磁镜 
 Baseball I/Baseball II, 劳伦斯利弗莫尔国家实验室，利弗莫尔，加利福尼亚州。
 , 劳伦斯利弗莫尔国家实验室，利弗莫尔，加利福尼亚州。
 , 劳伦斯利弗莫尔国家实验室，利弗莫尔, 加利福尼亚州。
 , , 阿卡杰姆戈罗多克，俄罗斯。





 C-2 
 C-2U Tri Alpha Energy
 C-3 (under construction?) Tri Alpha Energy
 LSX, 华盛顿大学
 IPA, 华盛顿大学
 HF, 华盛顿大学
 IPA-HF, 华盛顿大学

 Open field lines 

 Plasma pinch 
 Trisops - 2 facing theta-pinch guns

 懸浮偶極 
 懸浮偶極 (LDX), MIT/哥伦比亚大学, United States

 惯性约束 

 激光驱动 

 当前或正在建设的实验设施 

 固态激光器 
 National Ignition Facility (NIF) at LLNL in California, US
 Laser Mégajoule of the Commissariat à l'Énergie Atomique in Bordeaux, France (under construction)
 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
 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.

 气体激光器 
 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, 1 kJ max. output iodine laser at 1.315 micrometre fundamental wavelength

 已拆除实验设施 

 固态激光器 
 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)

 气体激光器 
 "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-箍缩 
 Z Pulsed Power Facility
 ZEBRA device at the University of Nevada's Nevada Terawatt Facility
 Saturn accelerator at Sandia National Laboratory
 MAGPIE at Imperial College London
 COBRA at Cornell University
 PULSOTRON

 惯性静电约束 
 Fusor
 Polywell

 磁化靶聚变 
 FRX-L
 FRCHX
 General Fusion - under development
 LINUS project

参考资料

Category:聚变能