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

Title: Advanced ST Plasma Scenario Simulations for NSTX

Abstract

Integrated scenario simulations are done for NSTX [National Spherical Torus Experiment] that address four primary milestones for developing advanced ST configurations: high {beta} and high {beta}{sub N} inductive discharges to study all aspects of ST physics in the high-beta regime; non-inductively sustained discharges for flattop times greater than the skin time to study the various current-drive techniques; non-inductively sustained discharges at high {beta} for flattop times much greater than a skin time which provides the integrated advanced ST target for NSTX; and non-solenoidal start-up and plasma current ramp-up. The simulations done here use the Tokamak Simulation Code (TSC) and are based on a discharge 109070. TRANSP analysis of the discharge provided the thermal diffusivities for electrons and ions, the neutral-beam (NB) deposition profile, and other characteristics. CURRAY is used to calculate the High Harmonic Fast Wave (HHFW) heating depositions and current drive. GENRAY/CQL3D is used to establish the heating and CD [current drive] deposition profiles for electron Bernstein waves (EBW). Analysis of the ideal-MHD stability is done with JSOLVER, BALMSC, and PEST2. The simulations indicate that the integrated advanced ST plasma is reachable, obtaining stable plasmas with {beta} {approx} 40% at {beta}{sub N}'s of 7.7-9, I{sub P} = 1.0 MA,more » and B{sub T} = 0.35 T. The plasma is 100% non-inductive and has a flattop of 4 skin times. The resulting global energy confinement corresponds to a multiplier of H{sub 98(y,2)} = 1.5. The simulations have demonstrated the importance of HHFW heating and CD, EBW off-axis CD, strong plasma shaping, density control, and early heating/H-mode transition for producing and optimizing these plasma configurations.« less

Authors:
; ; ; ; ; ; ; ; ;
Publication Date:
Research Org.:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Org.:
USDOE Office of Science (SC) (US)
OSTI Identifier:
836094
Report Number(s):
PPPL-4017
TRN: US0500493
DOE Contract Number:  
AC02-76CH03073
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 28 Oct 2004
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; CONFINEMENT; DEPOSITION; ELECTRIC CURRENTS; ELECTRONS; HARMONICS; HEATING; PHYSICS; PLASMA; SIMULATION; STABILITY; START-UP; TARGETS; HIGH-BETA PLASMAS; NUMERICAL SIMULATION; SPHERICAL TORUS

Citation Formats

Kessel, C E, Synakowski, E J, Gates, D A, Harvey, R W, Kaye, S M, Mau, T K, Menard, J, Phillips, C K, Taylor, G, Wilson, R, and the NSTX Research Team. Advanced ST Plasma Scenario Simulations for NSTX. United States: N. p., 2004. Web. doi:10.2172/836094.
Kessel, C E, Synakowski, E J, Gates, D A, Harvey, R W, Kaye, S M, Mau, T K, Menard, J, Phillips, C K, Taylor, G, Wilson, R, & the NSTX Research Team. Advanced ST Plasma Scenario Simulations for NSTX. United States. https://doi.org/10.2172/836094
Kessel, C E, Synakowski, E J, Gates, D A, Harvey, R W, Kaye, S M, Mau, T K, Menard, J, Phillips, C K, Taylor, G, Wilson, R, and the NSTX Research Team. 2004. "Advanced ST Plasma Scenario Simulations for NSTX". United States. https://doi.org/10.2172/836094. https://www.osti.gov/servlets/purl/836094.
@article{osti_836094,
title = {Advanced ST Plasma Scenario Simulations for NSTX},
author = {Kessel, C E and Synakowski, E J and Gates, D A and Harvey, R W and Kaye, S M and Mau, T K and Menard, J and Phillips, C K and Taylor, G and Wilson, R and the NSTX Research Team},
abstractNote = {Integrated scenario simulations are done for NSTX [National Spherical Torus Experiment] that address four primary milestones for developing advanced ST configurations: high {beta} and high {beta}{sub N} inductive discharges to study all aspects of ST physics in the high-beta regime; non-inductively sustained discharges for flattop times greater than the skin time to study the various current-drive techniques; non-inductively sustained discharges at high {beta} for flattop times much greater than a skin time which provides the integrated advanced ST target for NSTX; and non-solenoidal start-up and plasma current ramp-up. The simulations done here use the Tokamak Simulation Code (TSC) and are based on a discharge 109070. TRANSP analysis of the discharge provided the thermal diffusivities for electrons and ions, the neutral-beam (NB) deposition profile, and other characteristics. CURRAY is used to calculate the High Harmonic Fast Wave (HHFW) heating depositions and current drive. GENRAY/CQL3D is used to establish the heating and CD [current drive] deposition profiles for electron Bernstein waves (EBW). Analysis of the ideal-MHD stability is done with JSOLVER, BALMSC, and PEST2. The simulations indicate that the integrated advanced ST plasma is reachable, obtaining stable plasmas with {beta} {approx} 40% at {beta}{sub N}'s of 7.7-9, I{sub P} = 1.0 MA, and B{sub T} = 0.35 T. The plasma is 100% non-inductive and has a flattop of 4 skin times. The resulting global energy confinement corresponds to a multiplier of H{sub 98(y,2)} = 1.5. The simulations have demonstrated the importance of HHFW heating and CD, EBW off-axis CD, strong plasma shaping, density control, and early heating/H-mode transition for producing and optimizing these plasma configurations.},
doi = {10.2172/836094},
url = {https://www.osti.gov/biblio/836094}, journal = {},
number = ,
volume = ,
place = {United States},
year = {2004},
month = {10}
}