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Integrated operation of steady-state long-pulse H-mode in Experimental Advanced Superconducting Tokamak.

Authors :
X. Gong
A.M. Garofalo
J. Huang
J. Qian
C.T. Holcomb
A. Ekedah
R. Maingi
E. Li
L. Zeng
B. Zhang
J. Chen
M. Wu
H. Du
M. Li
X. Zhu
Y. Sun
G. Xu
Q. Zang
L. Wang
L. Zhang
Source :
Nuclear Fusion; Aug2019, Vol. 59 Issue 8, p1-1, 1p
Publication Year :
2019

Abstract

Recent Experimental Advanced Superconducting Tokamak (EAST) experiments have successfully demonstrated a long-pulse steady-state scenario with improved plasma performance through integrated operation since the last IAEA FEC in 2016. A discharge with a duration over 100 s using pure radio frequency (RF) power heating and current drive has been obtained with the required characteristics for future long-pulse tokamak reactors such as good energy confinement quality (H<subscript>98y2</subscript> ~ 1.1) with electron internal transport barrier inside ρ  <  0.4, small ELMs (frequency ~100–200 Hz), and good control of impurity and heat exhaust with the tungsten divertor. The optimization of X-point, plasma shape, the outer gap and local gas puffing near the low hybrid wave (LHW) antenna were integrated with global parameters of B<subscript>T</subscript> and line-averaged electron density for higher current drive efficiency of LHW and on-axis deposition of electron cyclotron heating in the long-pulse operation. More recently, a high β<subscript>P</subscript> RF-only discharge (β<subscript>P</subscript> ~ 1.9 and β<subscript>N</subscript> ~ 1.5, /n<subscript>GW</subscript> ~ 0.80, f <subscript>bs</subscript> ~ 45% at q<subscript>95</subscript> ~ 6.8) was successfully maintained over 24 s with improved hardware capabilities, demonstrating performance levels needed for the China Fusion Engineering Test Reactor steady-state operation. A higher energy confinement is observed at higher β<subscript>P</subscript> and with favorable toroidal field direction. Towards the next goal (⩾400 s long-pulse H-mode operations with ~50% bootstrap current fraction) on EAST, an integrated control of the current density profile, pressure profile and radiated divertor will be addressed in the near future. [ABSTRACT FROM AUTHOR]

Details

Language :
English
ISSN :
00295515
Volume :
59
Issue :
8
Database :
Complementary Index
Journal :
Nuclear Fusion
Publication Type :
Academic Journal
Accession number :
137462246
Full Text :
https://doi.org/10.1088/1741-4326/ab1c7b