Confinement cosistent with Lmode but We is small fraction NSTX约束一致的模式但我们是小部分NSTX.pptVIP

National Spherical Torus ExperimentFacility / Diagnostic Overview Operational and Physics Advances Have Led to Significant Progress Towards Goal of High-bT, Non-Inductive Operation tIp flattop ~ 3.5tskin tW flattop ~ 10 tE bT20%, bN5, tE/tE,L1.5 for ~10 tE IBS/Ip = 0.5, IBeam/Ip = 0.1 Research Topics to Achieve Long-Pulse, High Performance Plasmas Are Identified Enhanced shaping improves ballooning stability Mode, rotation and error field control allows high beta NBI and bootstrap sustain most of current HHFW heating contributes to bootstrap EBW provides off-axis current stabilizes tearing modes Particle and wall control maintains proper density Improved Plasma Control System Opened Operating Window During 2004 Campaign Reduced latency improved vertical control at high-k, high-bT High k scattering measurements will be developed in FY’ 05 Initial system will allow range of k measurements in select locations (2 - 20 cm-1) Access to ETG possible! Major installation this opening. Multiple Roles of HHFW ~ 100 kA of off-axis CD needed to sustain b ~ 40% in NSTX Cannot use ECCD in NSTX since wpe/wce ~ 3-10 Modeling indicates that EBWCD can provide needed current EBWCD may also assist startup and stabilize NTMs 4 MW, 28 GHz EBWCD system planned for NSTX ~ 750 kW EBW power delivered to plasma -- Use EBWCD to locally drive 30-40 kA If 1 MW system is successful increase RF power to 4 MW with addition of three more gyrotrons, transmission lines launchers by -- Provide 3 MW of EBW power in the plasma Generate 100 kA Supersonic gas jet penetrates well through a thick scrape-off layer * Supported by Columbia U Comp-X General Atomics INEL Johns Hopkins U LANL LLNL Lodestar MIT Nova Photonics NYU ORNL PPPL PSI SNL UC Davis UC Irvine UCLA UCSD U Maryland U New Mexico U Rochester U Washington U Wisconsin Culham Sci Ctr Hiroshima U HIST Kyushu Tokai U Niigata U Tsukuba U U Tokyo JAERI Ioffe Inst TRINITI KBSI KAIST ENEA, Fra