L-to-H power threshold comparisons between NBI and rf heated plasmas in the National Spherical Torus Experiment

نویسندگان

  • T. M. Biewer
  • R. Maingi
  • H. Meyer
  • R. E. Bell
  • C. Bush
  • S. Kaye
  • S. Kubota
  • B. LeBlanc
  • K. Williams
  • S. Zweben
چکیده

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

Long Pulse High Performance Plasma Scenario Development for NSTX

The National Spherical Torus Experiment (NSTX) [Ono, M., et al., Nucl. Fusion, 44, (2004), 452.] is targeting long pulse high performance, non-inductive sustained operations at low aspect ratio, and the demonstration of non-solenoidal startup and current rampup. The modeling of these plasmas provides a framework for experimental planning and identifies the tools to access these regimes. Simulat...

متن کامل

Divertor Heat Flux Mitigation in High-Performance H-mode Plasmas in the National Spherical Torus Experiment

Experiments conducted in high-performance 1.0-1.2 MA 6 MW NBI-heated H-mode plasmas with a high flux expansion radiative divertor in NSTX demonstrate that significant divertor peak heat flux reduction and access to detachment may be facilitated naturally in a highly-shaped spherical torus (ST) configuration. Improved plasma performance with high βp = 15− 25 %, a high bootstrap current fraction ...

متن کامل

Studies of improved electron confinement in low density L-mode National Spherical Torus Experiment discharges

Electron transport is rapid in most National Spherical Torus Experiment, M. Ono et al., Nucl. Fusion 40, 557 2000 beam heated plasmas. A regime of improved electron confinement is nevertheless observed in low density L-mode “low-confinement” discharges heated by early beam injection. Experiments were performed in this regime to study the role of the current profile on thermal transport. Variati...

متن کامل

National Spherical Torus Experiment Liquid Lithium Divertor

Recent NSTX high power divertor experiments have shown significant and recurring benefits of solid lithium coatings on PFC’s to the performance of divertor plasmas in both Land Hmode confinement regimes heated by high-power neutral beams. The next step in this work is installation of a liquid lithium divertor (LLD) to achieve density control for inductionless current drive capability (e.g., abo...

متن کامل

Predictive simulations of ITER including neutral beam driven toroidal rotation

discharges are carried out for the 15 MA high confinement mode ͑H-mode͒ scenario using PTRANSP, the predictive version of the TRANSP code. The thermal and toroidal momentum transport equations are evolved using turbulent and neoclassical transport models. A predictive model is used to compute the temperature and width of the H-mode pedestal. The ITER simulations are carried out for neutral beam i...

متن کامل

ذخیره در منابع من


  با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

عنوان ژورنال:

دوره   شماره 

صفحات  -

تاریخ انتشار 2006