They occurred during the standard O regime, The retarding field analyzer (RFA) is one of the only widely accepted diagnostics for measuring the ion tem‐perature Ti in the tokamak scrape‐off layer. The Soviet machine was a doughnut-shaped magnetic confinement device called a tokamak. M Kočan 1, J P Gunn 1, J-Y Pascal 1, G Bonhomme 2, C Fenzi 1, E Gauthier 1 and J-L Segui 1. The heat exhausted during plasma discharges is stored in a closed cooling circuit operating at a full flow rate of 1100 m 3 /h. The RFA measurements in Tore Supra are found to be well reproducible. The research is working towards producing significantly more energy than is put in. The retarding field analyzer (RFA) is one of the only widely accepted diagnostics for measuring the ion tem‐perature Ti in the tokamak scrape‐off layer. One of the first and main result is related to the Over the exploitation period of Tore Supra, the cooling loop has been modified and updated [2]. Finding the elusive E×B staircase in magnetized plasmas. (1)Association EURATOM-CEA sur la Fusion, CEA/DSM/DRFC, CEA Cadarache, 13108 Saint Paul lez Durance, France. normal Tore Supra plasma operation) fully stripped at high electron temperatures, prevailing in the core of the fusion plasma • heavy impurities (Fe, Cr, Cu, Ni etc. INIS Repository Search provides online access to one of the world's largest collections on the peaceful uses of nuclear science and technology. TORE SUPRA Numerical Flow Model for Controlled Fusion 16-20 April 2007 1 Association Euratom-CEA THERMOHYDRAULICS FOR COOLING OF TOKAMAK SUPERCONDUCTING MAGNETS Nicollet S. , Duchateau J.L., Lacroix, B. During noninductively driven discharges in the Tore Supra tokamak, steady sinusoidal oscillations of the central electron temperature, lasting as long as 2 min, have been observed for the first time. Particle transport has been studied in the Tore Supra tokamak by using modulated ion cyclotron resonance heating to generate perturbations of density and temperature. normally in small quantity during plasma operation) partly stripped and are produced by erosion from the metallic components inside the vacuum vessel [8]. Two experimental campaigns (2001 and 2002) have been carried out with the tokamak Tore Supra since the complete upgrade of all plasma facing components. Dif-Pradalier, G; Hornung, G; Ghendrih, Ph; Sarazin, Y; Clairet, F; Vermare, L; Diamond, P H; Abiteboul, J . OSTI.GOV Journal Article: Giant Oscillations of Electron Temperature during Steady-State Operation on Tore Supra The most plausibl … TORE SUPRA Association EURATOM-CEA From physics to design (Conceptual design) Cassette body HT7 Tore Supra JET . The ion-to-electron temperature ratio τ decreases with increasing density. Measurements . An overview of the outstanding RFA. RFA and TP were separated toroidally by 120°. Reseach on controled nuclear fusion and the physic of high temperature plasma in the USSR, L.A. Artsimovitch Plasma Physics, 1965, Vol.7 pp 477 to 489 : Details of Tokamak principles . Once that goal is attained, a portion of the resultant energy will be used. Tore Supra 1 2 3 4 For the first time, a reversal of the particle convective velocity and a strong increase in the turbulent particle flux have been clearly observed. Plasma temperature 10^8 K (100 million . An overview of the outstanding RFA performance over ten years of operation in Tore Supra tokamak is given and the validation of Ti measurements is addressed. NUCLEAR FUSION Theoretical and numerical studies of wave-packet propagation in tokamak plasmas (2012) Z. X. Lu et al. Eo (upper scale) for typical Tore Supra parameters (a = 0.78 m, R = 2.36 m. Bo = 3.9 T, neo = 3 x 1019 nr3) and several values of the central temperature Teo- A temperature profile of the type Te(r) = Teo(l - r 2/a2)P is assumed, and P is also varied, keeping all die odier parameters Having no helical structure, they cannot be ascribed to any known MHD instability. Pulse duration (a), number of UFOs per discharge (b) and disruption frequency (c) versus discharge number. An overview of the outstanding RFA performance over ten years of operation in Tore Supra tokamak is given and the validation of Ti measurements is addressed. The most plausibl … Plasma in the Tore Supra Tokamak, France. With its circular cross-section, Tore-Supra plasma is vertically stable : this fast movement is thus purely horizontal, toward in high field side inner wall (figure 1). Deuterium plasmas with a current of 1 MA, having quasi-stationary conditions for one minute, were obtained in TORE SUPRA, a large superconducting tokamak. MAIN ASPECTS OF TORE SUPRA SUPERCONDUCTING SYSTEM | PAGE 12 At the bath temperature(1.8K),at1400Aand9Tthe conductor satisfies stability requirements of two kinds: • In case of a plasma current disruption, the conductor is subject to field variations in the range of 0.6 T with an associated time constant due to the steel casings of about 10-20 ms. Guimarães-Filho et al. Researchers there were able to achieve temperature levels and plasma confinement times—two of the main criteria to achieving fusion—that had never been attained before. The International Nuclear Information System is operated by the IAEA in collaboration with over 150 members. WEST is an upgrade of the Tore Supra tokamak to test ITER like divertor elements over very long pulses. For the studies of MHD instabilities affected by tungsten impurities, two microwave imaging diagnostics have been developed to obtain density and temperature fluctuation maps. X. Garbet, J. Payan, C. Laviron, P. Devynck, S.K. Download Download PDF. Having no helical structure, they cannot be ascribed to any known MHD instability. Tore Supra, which began operating in 1988, was the first large tokamak to integrate all the technologies required to produce long pulse duration plasmas: superconducting magnet and cryogenic system, actively cooled plasma facing components and pressurized water loop, powerful heating and current drive systems, pump limiters and real-time protection and control capabilities. Tore Supra in an X-point divertor configuration while extending its long pulse capability, in order to test the ITER divertor. During a disruption, the sudden loss of the temperature destroys this balance, and the plasma is pushed inward on a time scale too short for any power supply reaction. Having no helical structure, they cannot be ascribed to any known MHD instability. The plasma current was partially noninductively driven by a 2.5 MW, 62 s lower hybrid wave pulse, resulting in a high central electron temperature (5.5 keV) for a plasma with a central electron density of 3.5 × 10<SUP>19</SUP> m<SUP>-3</SUP> plasma. The selected technical solutions are described successively for the cryogenic satellites, the distribution lines and the refrigeration plant. Abstract The retarding field analyzer (RFA) is one of the only widely accepted diagnostics for measuring the ion tem-perature Ti in the tokamak scrape-off layer. The central frequency of the yttrium iron garnet . Physical Review Letters, 2009. Study of Advanced Tokamak Performance using the International Tokamak Physics Database A.C.C. Central ion temperature is related to the edge ion temperature (T i0 ~ C T i,ped.). Edge ion-to-electron temperature ratio in the Tore Supra tokamak. On Tore Supra tokamak, a 32-channel heterodyne ECE radiometer has been upgraded to include two channels for temperature fluctuation measurements. Both ion and electron temperatures in the scrape-off layer (SOL) of the Tore Supra tokamak were measured by a retarding field analyzer during an ohmic density scan. Made available by U.S. Department of Energy Office of Scientific and Technical Information . Measurements of core electron temperature and density fluctuations in DIII-D and comparison to nonlinear gyrokinetic simulations. Variation of density fluctuation amplitudes with increasing line-averaged density measured in (a) Tore Supra tokamak and (b) W7-AS stellarator [54 54. Tore Supra is a large tokamak with a plasma of circular cross-section whose LCFS is defined by its intersection with the bottom toroidal pump limiter. Jeff Candy. The use of classical or specially developed . Electron fishbones in FTU and Tore Supra tokamaks (2012) Z.O. The cryogenic system of the TORE SUPRA tokamak is presented here in its final design. Lower hybrid current drive in the Tore Supra tokamak Emelie Nilsson Department of Applied Physics Chalmers University of Technology Abstract To control and extract energy from nuclear fusion reactions, a mixture of deuterium and tritium gases must be heated to temperatures on the order of 100 million degrees, whilst maintaining a su ciently . A major breakthrough occurred in 1968 in the Soviet Union. The most plausible explanation of this new phenomenon is that the plasma current density and the electron . Plasma in the Tore Supra Tokamak, France. It was operated at a pressure up to 4 MPa and a temperature in the range 100-230°C. Association EURATOM-CEA, CEA/ DSM/ DRFC, CEA-Cadarache, F-13108 Saint Paul lez Durance, France Sips1, . The toroidal pumped limiter (TPL) allows reliable steady state operation at significant injected power (up to 8.5 MW peak, 4.3 minutes at 3 MW). During noninductively driven discharges in the Tore Supra tokamak, steady sinusoidal oscillations of the central electron temperature, lasting as long as 2 min, have been observed for the first time. During noninductively driven discharges in the Tore Supra tokamak, steady sinusoidal oscillations of the central electron temperature, lasting as long as 2 min, have been observed for the first time. The AIA inside Tore Supra, during an inspection in ultra-vacuum and at 120 C. keep the embedded electronic temperature below 60 C. The tests of deployment in Tore Supra, under ultra-high vacuum Figure 4. Plasma temperature 10^8 K (100 million kelvin), plasma density 1 bar. SOL Ti and Te were measured by a RFA ( [ 23] and references therein). PHYSICS OF . The RFA measurements in Tore Supra are found to be well reproducible. Answer (1 of 2): So far, the fusion has produced less energy than it takes to create the heat and pressure required to fuse the particles. The core reflectometer was refurbished and now measures the core density profiles in few microseconds. The Japanese JT-60 achieved the highest value of fusion triple product—density, temperature, confinement time—of any device to date. Tore-Supra Tokamak (Ip = 1.5 MA, Bt = 4 T) has been constructed with a steady-state magnetic field using super-conducting magnets and water-cooled plasma facing components (PFCs) for high . SOL T i was found to be higher than T e by a factor of 4-7. Turbulence in the TORE SUPRA Tokamak: Measurements and Validation of Nonlinear Simulations. A cryogenic power of ≈300 W at 1.75 K and 1000 W at 4.0 K is needed. Eo (upper scale) for typical Tore Supra parameters (a = 0.78 m, R = 2.36 m. Bo = 3.9 T, neo = 3 x 1019 nr3) and several values of the central temperature Teo- A temperature profile of the type Te(r) = Teo(l - r 2/a2)P is assumed, and P is also varied, keeping all die odier parameters Edge ion-to-electron temperature ratio in the Tore Supra tokamak MKoˇcan 1, J P Gunn , J-Y Pascal1, G Bonhomme2, C Fenzi , E Gauthier 1and J-L Segui 1 CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France 2 Nancy-Universite, BP 239, 54506 Vandœuvre-l´ `es-Nancy Cedex, France E-mail: martin.kocan@cea.fr Received 29 July 2008, in final form 2 . Published 6 November 2008 • 2008 IOP Publishing Ltd Plasma Physics and Controlled Fusion, Volume 50, Number 12 Fusion 32 (1992) 2147. During fully noninductively driven discharges in the Tore Supra tokamak, large spontaneous oscillations of the core electron temperature (DeltaTe/Te>50%) have been observed for the first time. . Over the past twenty-four years, Tore Supra has explored the physics of long-duration plasma pulses, reaching a record of 6.5 minutes in December 2003. For comparison, Te was measured simultaneously by a tunnel probe (TP) [ 24 ]. . The superconducting TF system of TORE SUPRA is a key unique component to achieve this goal and extend the plasma duration from 6 minutes 30 s achieved in 2003 to 1000 s , accumulating relevant particle Saha, et al., Turbulence and energy confinement in TORE SUPRA ohmic discharges, Nucl. Made available by U.S. Department of Energy Office of Scientific and Technical Information . Confinement of advanced scenarios . WEST, Tungsten (chemical symbol "W") Environment in Steady-state Tokamak, (formerly Tore Supra) is a French tokamak that originally began operating as Tore Supra after the discontinuation of TFR (Tokamak of Fontenay-aux-Roses) and of Petula (in Grenoble).The original name came from the words torus and superconductor, as Tore Supra was for a long time the only tokamak of this size with . Edge ion-to-electron temperature ratio in the Tore Supra tokamak MKoˇcan 1, J P Gunn , J-Y Pascal1, G Bonhomme2, C Fenzi , E Gauthier 1and J-L Segui 1 CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France 2 Nancy-Universite, BP 239, 54506 Vandœuvre-l´ `es-Nancy Cedex, France E-mail: martin.kocan@cea.fr Received 29 July 2008, in final form 2 . The mechanical structure ( ~120 000 kg) is cooled to ~4.5 K. Around the coils, a radiation shield (-~20000 kg) is cooled to ~80 k. Power balance in a divertor tokamak • frad . 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