Advanced Control Scenario of High-Performance Steady-State Operation for JT-60 Superconducting Tokamak

2004 ◽  
Vol 6 (3) ◽  
pp. 2281-2285
Author(s):  
H Tamai ◽  
G Kurita ◽  
M Matsukawa ◽  
K Urata ◽  
S Sakurai ◽  
...  
2001 ◽  
Vol 41 (10) ◽  
pp. 1483-1493 ◽  
Author(s):  
H. Zushi ◽  
S. Itoh ◽  
K. Nakamura ◽  
M. Sakamoto ◽  
K. Hanada ◽  
...  

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.


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.


1999 ◽  
Vol 39 (9Y) ◽  
pp. 1257-1270 ◽  
Author(s):  
S Itoh ◽  
K.N Sato ◽  
K Nakamura ◽  
H Zushi ◽  
M Sakamoto ◽  
...  

1992 ◽  
Vol 124 (1) ◽  
pp. 99-108 ◽  
Author(s):  
N. Yoshida ◽  
A. Nagao ◽  
K. Tokunaga ◽  
K. Tawara ◽  
T. Muroga ◽  
...  

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