skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Solenoid-free startup experiments in DIII-D

Journal Article · · Nuclear Fusion
 [1];  [2];  [3];  [1];  [1];  [1];  [1];  [4];  [1];  [1];  [1];  [4];  [1];  [1];  [3];  [3];  [3];  [5];  [5];  [5] more »;  [6];  [7];  [8];  [8] « less
  1. General Atomics, San Diego
  2. EURATOM CCFE Fus Assoc, Culham Sci Ctr, Abingdon, Oxon, England
  3. Princeton Plasma Physics Laboratory (PPPL)
  4. General Atomics
  5. National Fusion Research Institute, Daejon, South Korea
  6. University of California, San Diego
  7. ORNL
  8. Oak Ridge National Laboratory (ORNL)

A series of DIII-D experiments was performed to investigate the potential for initiating plasma current using only poloidal field coils located outside the DIII-D central solenoid, i.e. 'solenoid-free'. Plasma current to 166 kA was achieved using 2-3MW of electron cyclotron (EC) heating and was limited by coil and power supply constraints. Flux conversion to plasma current was similar to standard DIII-D startup with some degradation at higher plasma current associated with stray fields and vertical stability issues. In preliminary solenoid-free experiments, neutral beam (NB) current drive (CD) levels were small and attributed to reduced CD efficiency associated with low electron temperature produced by the low current, low confinement plasma. Lack of plasma radial position control also contributed to a reduction of NBCD. Similarly, ECCD was small owing to low plasma temperature and outside EC launch which is required in the solenoid-free scenario. Synergistic experiments were carried out using standard solenoid initiated plasmas in order to study noninductive CD in limited, Lmode plasmas, typical of that generated by solenoid-free startup. While substantial noninductive current can be driven, self-sustaining levels of noninductive current have not yet been achieved with our present six-source co-injection NB system combined with EC and fast wave systems. At low plasma current and high levels of localized EC heating, substantial MHD is generated and this was seen to severely limit plasma performance. Although further optimization is possible in the limited plasma regime, full noninductive, steady-state operation may require diverted plasma with H-mode quality confinement. Discharges obtained during the solenoid-free campaign are compared with results of previous DIII-D campaigns aimed at achieving a steady state, noninductive CD solution.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Science (SC)
DOE Contract Number:
DE-AC05-00OR22725
OSTI ID:
1036678
Journal Information:
Nuclear Fusion, Vol. 51, Issue 6; ISSN 0029--5515
Country of Publication:
United States
Language:
English

Similar Records

Noninductive Current Drive and Steady-State Operation in JT-60U
Journal Article · Sun Sep 15 00:00:00 EDT 2002 · Fusion Science and Technology · OSTI ID:1036678

Non-Inductive Current Drive Modeling Extending Advanced Tokamak Operation to Steady State
Conference · Tue Jun 06 00:00:00 EDT 2000 · OSTI ID:1036678

Progress toward fully noninductive, high beta conditions in DIII-D
Journal Article · Mon May 15 00:00:00 EDT 2006 · Physics of Plasmas · OSTI ID:1036678