2005 47th Annual Meeting of the Division of Plasma Physics
Monday–Friday, October 24–28, 2005;
Denver, Colorado
Session UI2: Innovative Confinement Concepts and High Beta
9:30 AM–12:30 PM,
Friday, October 28, 2005
Adam's Mark Hotel
Room: Plaza Ballroom EF
Chair: Jonathan Menard, Princeton Plasma Physics Laboratory
Abstract ID: BAPS.2005.DPP.UI2.4
Abstract: UI2.00004 : Long Pulse High Performance Plasma Scenario Development for the National Spherical Torus Experiment*
11:00 AM–11:30 AM
Preview Abstract
Abstract
Author:
Charles Kessel
(Princeton Plasma Physics Laboratory)
NSTX is targeting long pulse high performance, non-inductive
sustained
operations at low aspect ratio. The modeling of these plasmas
provides a
framework for experimental planning and identifies the tools to
access these
regimes. Here, two scenarios are examined, the first near-term with
t$_{flattop}>\tau _{J}$, and the second, longer term goal obtaining
$\beta \approx $40{\%} for t$_{flattop}>>\tau _{J}$. Simulations
based on NBI-heated plasmas with the free-boundary Tokamak
Simulation Code
(TSC) and TRANSP are made to understand the impact of various
modifications
and identify the requirements for 1) high elongation and
triangularity, 2)
density control to optimize the current drive, 3) rotation/wall
and/or
feedback stabilization to operate above the no-wall limit, 4)
Electron
Bernstein Waves for off-axis heating/current drive (H/CD), and 5)
High
Harmonic Fast Wave for H/CD. Comparison of the profile evolution
with
experiment, including time-resolved kinetic and current profile
measurements, provides the required benchmarking. An integrated
scenario is
constructed using TSC/TRANSP to provide the transport evolution
and (H/CD)
source modeling, supported by RF and stability analyses using
CURRAY,
GENRAY/CQL3D, JSOLVER/BALMSC/PEST2, DCON, and VALEN. Important
factors
include the energy confinement, Z$_{eff}$, early heating/H-mode,
broadening
of the NBI-driven current profile from fast ion MHD, and
maintaining q(0)
and q$_{min}>$1.0. Simulations show that the near-term goal can
be reached
at I$_{P}$=800 kA, B$_{T}$=0.5 T, $\kappa \approx $2.5, $\beta
_{N}\le
$5, $\beta \le $15{\%}, f$_{NI}$=92{\%}, and q(0)$>$1.5 with NBI
H/CD,
density control, and similar global energy confinement to
experiments. The
non-inductive sustained high $\beta $ plasmas can be reached at
I$_{P}$=1.0
MA, B$_{T}$=0.35 T, $\kappa \approx $2.5, $\beta _{N}\le $9, $\beta
\le $43{\%}, f$_{NI}$=100{\%}, and q(0)$>$1.5 with NBI H/CD and
3.0 MW of
EBW H/CD, density control, and 25{\%} higher global energy
confinement than
experiments.
*Work supported by U.S. DoE Contract No. DE-AC02-76CH03073.
To cite this abstract, use the following reference: http://meetings.aps.org/link/BAPS.2005.DPP.UI2.4