discovering the tokamak layout 1970: Stellarator C reopens as the Symmetric Tokamak in May at PPPL 1971–1980: Texas Turbulent Tokamak, University of Texas at Austin, US 1972: The Adiabatic Toroidal Compressor begins operation at PPPL 1973–1976: Tokamak de Fontenay aux Roses (TFR), near Paris, France 1973–1979: Alcator A, MIT, US 1975: Princeton Large Torus begins operation at PPPL 1978–1987: Alcator C, MIT, US 1978–2013: TEXTOR, in Jülich, Germany 1979–1998: MT-1 Tokamak, Budapest, Hungary (Built at the Kurchatov Institute, Russia, transported to Hungary in 1979, rebuilt as MT-1M in 1991) 1980–1990: Tokoloshe Tokamak, Atomic Energy Board, South Africa 1980–2004: TEXT/TEXT-U, University of Texas at Austin, US 1982–1997: TFTR, Princeton University, US 1983–2000: Novillo Tokamak, at the Instituto Nacional de Investigaciones Nucleares, in Mexico City, Mexico 1984–1992: HL-1 Tokamak, in Chengdu, China 1985–2010: JT-60, in Naka, Ibaraki Prefecture, Japan; (Being upgraded 2015–2018 to Super, Advanced model) 1987–1999: Tokamak de Varennes; Varennes, Canada; operated by Hydro-Québec and used by researchers from Institut de recherche en électricité du Québec (IREQ) and the Institut national de la recherche scientifique (INRS) 1988–2005: T-15, in Kurchatov Institute, Moscow, Russia (formerly Soviet Union); 10 MW 1991–1998: START, in Culham, United Kingdom 1990s–2001: COMPASS, in Culham, United Kingdom 1994–2001: HL-1M Tokamak, in Chengdu, China 1999–2006: UCLA Electric Tokamak, in Los Angeles, US 1999–2014: MAST, in Culham, United Kingdom 1992–2016: Alcator C-Mod, MIT, Cambridge, US Planned ITER, international project in Cadarache, France; 500 MW; construction began in 2010, first plasma expected in 2025. Expected fully operational by 2035. DEMO; 2000 MW, continuous operation, connected to power grid. Planned successor to ITER; construction to begin in 2024 according to preliminary timetable. CFETR, also known as "China Fusion Engineering Test Reactor"; 200 MW; Next generation Chinese fusion reactor, is a new tokamak device. K-DEMO in South Korea; 2200–3000 MW, a net electric generation on the order of 500 MW is planned; construction is targeted by 2037. See also Magnetic mirrors Edge-localized mode, a tokamak plasma instability Stellarator, an alternative design Reversed-field pinch, an alternative design Divertor, used in long pulse tokamaks Ball-pen probe Dimensionless parameters in tokamaks in the article on Plasma scaling Lawson criterion, and triple product, needed for break-even and ignition Fusion power#Records, inc beta, Q ARC fusion reactor, an MIT tokamak design List of plasma (physics) articles Notes References Citations Bibliography External links CCFE – site from the UK fusion research centre CCFE. Int'l Tokamak research – various that