Joint plus conductor thermal-hydraulic experiment and analysis on the Full Size Joint Sample using MITHRANDIR 2.1
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Two full-size conductor samples using advanced Nb3Sn strands were tested in the SULTAN facility in 2005-2006 within (I,B,T) ranges close to the ITER operating conditions (B-MAX similar to 12 T, T similar to 5 K). Each sample includes two conductor legs, co ...
Results are presented from the JET Trace Tritium Experimental (TTE) campaign using minority tritium (T) plasmas (n(T)/n(D) < 3%). Thermal tritium particle transport coefficients (D-T, nu(T)) are found to exceed neo-classical values in all regimes, except i ...
Metallic mirrors will be essential components of all optical spectroscopy and imaging systems for plasma diagnosis that will be used at the next-step magnetic fusion experiment, International Thermonuclear Experimental Reactor (ITER). Any change of the mir ...
Compact optimized stellarators offer novel solutions for confining high-beta plasmas and developing magnetic confinement fusion. The three-dimensional plasma shape can be designed to enhance the magnetohydrodynamic (MHD) stability without feedback or nearb ...
The spectrum of turbulent density fluctuations at long poloidal wavelengths in the edge plasma of the DIII-D tokamak peaks at nonzero radial wave number. The associated electric-potential fluctuations cause sheared E~×B flows primarily in the poloidal dire ...
Prototype conductors for the ITER magnets have been tested extensively in the SULTAN facility at CRPP in the last decade. The in-depth characterization of the high current carrying conductors provided a valuable feedback in the design, with performance opt ...
The preparative experimental and analysis work as well as the code development for testing the ITER (International Thermonuclear Experimental Reactor) TFMC, one of the large projects of the ITER research and development programme, is described. The expecte ...
The ITER toroidal field model coil (TFMC) has been tested in the TOSKA facility of FzK. The racetrack coil, which uses a circular Nb3Sn cable-in-conduit conductor, is equipped with external resistive heaters for the evaluation of the current sharing temper ...
In the International Thermonuclear Experimental Reactor (ITER) toroidal field model coil (TFMC) the experimental evaluation of the superconducting critical properties will only be possible by heating the helium upstream of the inner joint. In this coil onl ...
The ITER toroidal field model coil (TFMC) was designed, constructed and tested by the European Home Team in the framework of the ITER research and development program of the Engineering Design Activities (EDA). The project was performed under the leadershi ...