Progress towards Steady State on NSTX
Abstract
In order to reduce recirculating power fraction to acceptable levels, the spherical torus concept relies on the simultaneous achievement of high toroidal {beta} and high bootstrap fraction in steady state. In the last year, as a result of plasma control system improvements, the achievable plasma elongation on the National Spherical Torus Experiment (NSTX) has been raised from {kappa} {approx} 2.1 to {kappa} {approx} 2.6--approximately a 25% increase. This increase in elongation has lead to a doubling increase in the toroidal {beta} for long-pulse discharges. The increase in {beta} is associated with an increase in plasma current at nearly fixed poloidal {beta}, which enables higher {beta}{sub t} with nearly constant bootstrap fraction. As a result, for the first time in a spherical torus, a discharge with a plasma current of 1 MA has been sustained for 1 second. Data is presented from NSTX correlating the increase in performance with increased plasma shaping capability. In addition to improved shaping, H-modes induced during the current ramp phase of the plasma discharge have been used to reduce flux consumption during and to delay the onset of MHD instabilities. A modeled integrated scenario, which has 100% non-inductive current drive with very high toroidal {beta}, willmore »
- Authors:
- Publication Date:
- Research Org.:
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC) (US)
- OSTI Identifier:
- 836619
- Report Number(s):
- PPPL-4044
TRN: US0501127
- DOE Contract Number:
- AC02-76CH03073
- Resource Type:
- Technical Report
- Resource Relation:
- Other Information: Supercedes report DE00836619; PBD: 24 Jan 2005; PBD: 24 Jan 2005
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; CONTROL SYSTEMS; ELECTRIC CURRENTS; ELECTRONS; ELONGATION; HARMONICS; HEATING; NON-INDUCTIVE CURRENT DRIVE; PERFORMANCE; PLASMA; SHAPE; BOOTSTRAP CURRENT; SPHERICAL TORUS; STEADY-STATE FUSION RESEARCH
Citation Formats
Gates, D A, Kessel, C, Menard, J, Taylor, G, Wilson, J R, and co-authors, plus 94. Progress towards Steady State on NSTX. United States: N. p., 2005.
Web. doi:10.2172/836619.
Gates, D A, Kessel, C, Menard, J, Taylor, G, Wilson, J R, & co-authors, plus 94. Progress towards Steady State on NSTX. United States. https://doi.org/10.2172/836619
Gates, D A, Kessel, C, Menard, J, Taylor, G, Wilson, J R, and co-authors, plus 94. 2005.
"Progress towards Steady State on NSTX". United States. https://doi.org/10.2172/836619. https://www.osti.gov/servlets/purl/836619.
@article{osti_836619,
title = {Progress towards Steady State on NSTX},
author = {Gates, D A and Kessel, C and Menard, J and Taylor, G and Wilson, J R and co-authors, plus 94},
abstractNote = {In order to reduce recirculating power fraction to acceptable levels, the spherical torus concept relies on the simultaneous achievement of high toroidal {beta} and high bootstrap fraction in steady state. In the last year, as a result of plasma control system improvements, the achievable plasma elongation on the National Spherical Torus Experiment (NSTX) has been raised from {kappa} {approx} 2.1 to {kappa} {approx} 2.6--approximately a 25% increase. This increase in elongation has lead to a doubling increase in the toroidal {beta} for long-pulse discharges. The increase in {beta} is associated with an increase in plasma current at nearly fixed poloidal {beta}, which enables higher {beta}{sub t} with nearly constant bootstrap fraction. As a result, for the first time in a spherical torus, a discharge with a plasma current of 1 MA has been sustained for 1 second. Data is presented from NSTX correlating the increase in performance with increased plasma shaping capability. In addition to improved shaping, H-modes induced during the current ramp phase of the plasma discharge have been used to reduce flux consumption during and to delay the onset of MHD instabilities. A modeled integrated scenario, which has 100% non-inductive current drive with very high toroidal {beta}, will also be presented. The NSTX poloidal field coils are currently being modified to produce the plasma shape which is required for this scenario, which requires high triangularity ({delta} {approx} 0.8) at elevated elongation ({kappa} {approx} 2.5). The other main requirement for steady state on NSTX is the ability to drive a fraction of the total plasma current with radio-frequency waves. The results of High Harmonic Fast Wave heating and current drive studies as well as electron Bernstein Wave emission studies will be presented.},
doi = {10.2172/836619},
url = {https://www.osti.gov/biblio/836619},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jan 24 00:00:00 EST 2005},
month = {Mon Jan 24 00:00:00 EST 2005}
}