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Progress toward fully noninductive, high beta conditions in DIII-D
Authors
SL Allen
ME Austin
+40 more
KH Burrell
TA Casper
JC Deboo
EJ Doyle
JR Ferron
AM Garofalo
P Gohil
IA Gorelov
CM Greenfield
RJ Groebner
WW Heidbrink
AW Hyatt
RJ Jayakumar
HES John
K Kajiwara
CE Kessel
JE Kinsey
RJ La Haye
LL Lao
AW Leonard
J Lohr
TC Luce
Y Luo
MA Makowski
M Murakami
TH Osborne
TW Petrie
CC Petty
RI Pinsker
PA Politzer
R Prater
TL Rhodes
ACC Sips
GM Staebler
TS Taylor
MA Vanzeeland
MR Wade
G Wang
WP West
L Zeng
Publication date
1 May 2006
Publisher
eScholarship, University of California
Abstract
The DIII-D Advanced Tokamak (AT) program in the DIII-D tokamak [J. L. Luxon, Plasma Physics and Controlled Fusion Research, 1986, Vol. I (International Atomic Energy Agency, Vienna, 1987), p. 159] is aimed at developing a scientific basis for steady-state, high-performance operation in future devices. This requires simultaneously achieving 100% noninductive operation with high self-driven bootstrap current fraction and toroidal beta. Recent progress in this area includes demonstration of 100% noninductive conditions with toroidal beta, ΒT =3.6%, normalized beta, ΒN =3.5, and confinement factor, H89 =2.4 with the plasma current driven completely by bootstrap, neutral beam current drive, and electron cyclotron current drive (ECCD). The equilibrium reconstructions indicate that the noninductive current profile is well aligned, with little inductively driven current remaining anywhere in the plasma. The current balance calculation improved with beam ion redistribution that was supported by recent fast ion diagnostic measurements. The duration of this state is limited by pressure profile evolution, leading to magnetohydrodynamic (MHD) instabilities after about 1 s or half of a current relaxation time (τCR). Stationary conditions are maintained in similar discharges (∼90% noninductive), limited only by the 2 s duration (1 τCR) of the present ECCD systems. By discussing parametric scans in a global parameter and profile databases, the need for low density and high beta are identified to achieve full noninductive operation and good current drive alignment. These experiments achieve the necessary fusion performance and bootstrap fraction to extrapolate to the fusion gain, Q=5 steady-state scenario in the International Thermonuclear Experimental Reactor (ITER) [R. Aymar, Fusion Energy Conference on Controlled Fusion and Plasma Physics, Sorrento, Italy (International Atomic Energy Agency, Vienna, 1987), paper IAEA-CN-77/OV-1]. The modeling tools that have been successfully employed to both plan and interpret the experiment are used to plan future DIII-D experiments with higher power and longer pulse ECCD and fast wave and co- and counterneutral beam injection in a pumped double-null configuration. The models predict our ability to control the current and pressure profiles to reach full noninductivity with increased beta, bootstrap fraction, and duration. The same modeling tools are applied to ITER, predicting favorable prospects for the success of the ITER steady-state scenario. © 2006 American Institute of Physics
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Last time updated on 25/12/2021