Integration of LHCD and IBW heating for high-performance discharges under steady-state operation in the HT-7 tokamak

2003 ◽  
Vol 43 (10) ◽  
pp. 1279-1287 ◽  
Author(s):  
Baonian Wan ◽  
JiangangLi for HT-7 Team
Author(s):  
Songlin Liu ◽  
Fang Ding ◽  
Xiangcun Chen ◽  
Yong Pu ◽  
Jia Li ◽  
...  

EAST can provide better opportunities to contribute development of ITER-relevant plasma physics and engineering because it has ITER-like configuration, and has achieved 10s H-mode plasma, and aims steady-state operation of DD high performance plasma. The impact of Test blanket module (TBM) using RAFM (reduced activation ferritic/martensitic) steels on tokomak plasma is a major concern in ITER operations. In order to assess this effect due to TBM local ripple, an experiment plan of TBM mockup using RAFM steel is being planned on MAPES (Material and Plasma Evaluation System) in EAST. This paper reports experimental consideration on MAPES based on magnetic analysis and ripple calculation at separatrix point. The relevant experiments strategy and plan in EAST are also proposed.


2004 ◽  
Vol 6 (3) ◽  
pp. 2281-2285
Author(s):  
H Tamai ◽  
G Kurita ◽  
M Matsukawa ◽  
K Urata ◽  
S Sakurai ◽  
...  

2006 ◽  
Vol 81 (23-24) ◽  
pp. 2807-2815 ◽  
Author(s):  
C.M. Greenfield ◽  
M. Murakami ◽  
A.M. Garofalo ◽  
E.J. Doyle ◽  
J.R. Ferron ◽  
...  

2009 ◽  
Vol 49 (11) ◽  
pp. 115018 ◽  
Author(s):  
Yong-Su Na ◽  
C.E. Kessel ◽  
J.M. Park ◽  
Sumin Yi ◽  
A. Becoulet ◽  
...  

2021 ◽  
Vol 12 (1) ◽  
Author(s):  
L. Wang ◽  
H. Q. Wang ◽  
S. Ding ◽  
A. M. Garofalo ◽  
X. Z. Gong ◽  
...  

AbstractDivertor detachment offers a promising solution to the challenge of plasma-wall interactions for steady-state operation of fusion reactors. Here, we demonstrate the excellent compatibility of actively controlled full divertor detachment with a high-performance (βN ~ 3, H98 ~ 1.5) core plasma, using high-βp (poloidal beta, βp > 2) scenario characterized by a sustained core internal transport barrier (ITB) and a modest edge transport barrier (ETB) in DIII-D tokamak. The high-βp high-confinement scenario facilitates divertor detachment which, in turn, promotes the development of an even stronger ITB at large radius with a weaker ETB. This self-organized synergy between ITB and ETB, leads to a net gain in energy confinement, in contrast to the net confinement loss caused by divertor detachment in standard H-modes. These results show the potential of integrating excellent core plasma performance with an efficient divertor solution, an essential step towards steady-state operation of reactor-grade plasmas.


2021 ◽  
Author(s):  
Yong-Su Na ◽  
Hyunsun Han ◽  
Sangjin Park ◽  
Jisung Kang ◽  
Young-Ho Lee ◽  
...  

Abstract We report a discovery of a fusion plasma regime suitable for commercial fusion reactor where the ion temperature was sustained above 100 million degree about 20 s for the first time. Nuclear fusion as a promising technology for replacing carbon-dependent energy sources has currently many issues to be resolved to enable its large-scale use as a sustainable energy source. State-of-the-art fusion reactors cannot yet achieve the high levels of fusion performance, high temperature, and absence of instabilities required for steady-state operation for a long period of time on the order of hundreds of seconds. This is a pressing challenge within the field, as the development of methods that would enable such capabilities is essential for the successful construction of commercial fusion reactor. Here, a new plasma confinement regime called fast ion roled enhancement (FIRE) mode is presented. This mode is realized at Korea Superconducting Tokamak Advanced Research (KSTAR) and subsequently characterized to show that it meets most of the requirements for fusion reactor commercialization. Through a comparison to other well-known plasma confinement regimes, the favourable properties of FIRE mode are further elucidated and concluded that the novelty lies in the high fraction of fast ions, which acts to stabilize turbulence and achieve steady-state operation for up to 20 s by self-organization. We propose this mode as a promising path towards commercial fusion reactors.


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