Extension of operational limits on EAST

Gao, Xiang; Li, Jiangang; Wan, Baonian; Zhao, Junyu; Hu, Liqun; Liu, Haiqing; Jie, Yinxian; Xu, Qianfan; Wu, Zhenwei; Yang, Yu; Gong, Xianzu; Shen, Biao; Hu, Jiansheng; Shi, Yuejiang; Ling, Bili; Wang, Jun; Sajjad, Saeeda; Zang, Qing; Gao, Wei; Zhang, Tao; Yu, Yaowei; Yang, Yilin; Han, Xiaofeng; Shi, Nan; Ming, Tingfeng; Ti, Ang; Zhang, Wenyang; Xu, Guosheng; Chen, Junling; Luo, Guang-Nan; Zhang, Xiaodong; Mao, Jiangyu; Wan, Y. X.

doi:10.1088/0029-5515/47/9/037

Cited by 23 publications

(14 citation statements)

References 26 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…EAST is a non-circular, steady-state experimental device with a major radius R = 1.75 m, a minor radius a = 0.4 m, an aspect ratio of 4.25 and a plasma facing surface area of about 60 m 2 [29]. The mission of EAST is to establish a scientific and technological basis for the next generation of tokamak reactors.…”

Section: Methodsmentioning

confidence: 99%

Mitigation of plasma–material interactions via passive Li efflux from the surface of a flowing liquid lithium limiter in EAST

Zuo

Maingi

et al. 2017

Nucl. Fusion

View full text Add to dashboard Cite

A new flowing liquid Li limiter (FLiLi) based on the concept of a thin flowing film has been successfully designed and tested in the EAST device in 2014. A bright Li radiative mantle at the plasma edge was observed during discharges using FLiLi, resulting from passive Li injection and transport in the scrape-off layer (SOL) plasma. Li particle efflux from the FLiLi surface into the plasma was estimated at >5 × 10 20 atom s −1 , due to surface evaporation and sputtering, and accompanied with a few small Li droplets ~1 mm diameter that were ejected from FLiLi. The Li efflux from FLiLi was ionized by the SOL plasma and formed a Li radiation band that originated from the FLiLi surface, and then spread toroidally by SOL plasma flow. The Li radiative mantle appeared to partly isolate the plasma from the wall, reducing impurity release from the wall materials, and possibly leading to a modest improvement in confinement. In addition, strong Li radiation reduced the particle and heat fluxes impacting onto the divertor plate, with certain similarities to heat flux reduction and detachment onset via low-Z impurity injection.

show abstract

Section: Methodsmentioning

confidence: 99%

Mitigation of plasma–material interactions via passive Li efflux from the surface of a flowing liquid lithium limiter in EAST

Zuo

Maingi

et al. 2017

Nucl. Fusion

View full text Add to dashboard Cite

show abstract

“…The EAST device is a superconducting tokamak with toroidal divertor configuration, which has a major radius R=1.85 m and a minor radius a=0.45 m. One of the EAST research objectives is to develop an advanced tokamak to operate in high performance regime and to explore a scientific and reliable basis for a future fusion reactor [1,2] . The plasma will be heated with ion cyclotron resonance heating (ICRH) and lower hybrid wave current drive, but also by exploiting electron cyclotron resonance heating (ECRH) at an optimized magnetic field of B=2.5 T [3] and neutral beam injection heating (NBI) in EAST.…”

Section: Introductionmentioning

confidence: 99%

Optimization Study of ICRF Hydrogen Minority Heating in a Deuterium Plasma of EAST

Zhang

Fangwei

2015

Plasma Sci. Technol.

View full text Add to dashboard Cite

The full wave TORIC code and the Kinetic Fokker-Planck SSFPQL code are combined to perform self-consistent simulations of the ICRF heating in the EAST 2D magnetic configuration. The combined package is applied to the ICRF hydrogen minority heating in a deuterium plasma with the hydrogen concentration up to 10%. The fast wave propagation and absorption properties, power partitions among the plasma species and the RF driven energetic tails have been analyzed. Meanwhile, in order to optimize the ICRF heating, changing the resonance locations has also been considered in EAST plasmas.

show abstract

“…The mission of EAST is to study the issues involved in steady-state advanced tokamak scheme [1] , such as current drive and plasma heating. A neutral beam injection (NBI) system is indispensable.…”

Section: Introductionmentioning

confidence: 99%

Calculation of Beam Intensity Distribution for the Neutral Beam Injection in EAST

Liang

Hu²,

Xie³

et al. 2011

Plasma Sci. Technol.

View full text Add to dashboard Cite

Theoretical beam intensity distribution is derived for the neutral-beam-injection ion source with a multi-slot extraction in EAST. The beam intensity profile, both along and perpendicular to the injecting direction and the beam power deposition to the inner elements in the neutral beam injector (NBI) are evaluated. The results indicate that the transverse beam intensity is much higher than the longitudinal one. This study could provide information for the design of vacuum system, structure of inner elements and cooling system of the neutral beam injector in EAST.

show abstract

Extension of operational limits on EAST

Cited by 23 publications

References 26 publications

Mitigation of plasma–material interactions via passive Li efflux from the surface of a flowing liquid lithium limiter in EAST

Mitigation of plasma–material interactions via passive Li efflux from the surface of a flowing liquid lithium limiter in EAST

Optimization Study of ICRF Hydrogen Minority Heating in a Deuterium Plasma of EAST

Calculation of Beam Intensity Distribution for the Neutral Beam Injection in EAST

Contact Info

Product

Resources

About