scholarly journals Progress of physics understanding for long pulse high-performance plasmas on EAST towards the steady-state operation of ITER and CFETR

2019 ◽  
Vol 62 (1) ◽  
pp. 014019
Author(s):  
J Huang ◽  
X Gong ◽  
A M Garofalo ◽  
J Qian ◽  
J Chen ◽  
...  
2019 ◽  
Vol 203 ◽  
pp. 04002
Author(s):  
Handong Xu ◽  
Xiaojie Wang ◽  
Jian Zhang ◽  
Fukun Liu ◽  
Yiyun Huang ◽  
...  

A long pulse ECRH system with a goal of 140GHz 4MW 100~1000s has been developed to meet the requirement of steady-state operation on EAST. Gycom gyrotrons are employed in the No.1 and No.3 systems, CPI gyrotrons are used in the No.2 and No.4 systems. The development of the two Gycom gyrotron systems has been finished. The first short pulse EC wave injection has been demonstrated successfully during the EAST 2015 Spring campaign. In the commissioning and operation towards steady-state operation, 0.4MW 100s has been injected to plasma successfully by using the No.1 system, 4.7keV 102s L-mode and 102s H-mode plasma have been achieved on EAST with the help of ECRH. Recently, a longest pulse of 0.55MW 1000s has been obtained based on calorimetric dummy load measurements on the No.3 gyrotron. The No.2 gyrotron also has been installed and partially tested, 500kW 80s has been demonstrated in the dummy load. The remaining No.4 gyrotron will be ready to test in 2018 or 2019. The whole 4MW system will be completed within two years. The 400s fully non-inductive H-mode operation would be expected in the next four years in the condition of fully tungsten diverter on EAST.


2005 ◽  
Vol 337-339 ◽  
pp. 802-807 ◽  
Author(s):  
H. Takenaga ◽  
N. Asakura ◽  
S. Higashijima ◽  
T. Nakano ◽  
H. Kubo ◽  
...  

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.


2001 ◽  
Vol 41 (6) ◽  
pp. 779-790 ◽  
Author(s):  
N Noda ◽  
Y Nakamura ◽  
Y Takeiri ◽  
T Mutoh ◽  
R Kumazawa ◽  
...  

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