Journal
PLASMA PHYSICS AND CONTROLLED FUSION
Volume 62, Issue 1, Pages -Publisher
IOP PUBLISHING LTD
DOI: 10.1088/1361-6587/ab56a5
Keywords
tokamak; steady state; long pulse; high bootstrap current
Categories
Funding
- National Natural Science Foundation of China [11975276]
- National Magnetic Confinement Fusion Science Program of China [2015GB110005, 2015GB102000, 2015GB103000]
Ask authors/readers for more resources
Recently, the first ever 100 s long, steady-state H-mode discharge with good control of impurities, core and edge MHD stabilities, and heat exhaust was demonstrated in the Experimental Advanced Superconducting Tokamak (EAST) using the ITER-like (International Tokamak Experimental Reactor) tungsten upper divertor. Using both radio frequency (RF) power and neutral beam injection (NBI) heating, EAST has demonstrated fully non-inductive scenarios with an extension of fusion performance at high density and low rotation: beta(P) similar to 2.5, beta(N) similar to 2.0, H-98,H-y2 similar to 1.2, bootstrap current fraction f(BS) similar to 50% at q(95) similar to 6.8. With pure RF power heating, plasmas have been maintained for up to 21 s (over 40 times the current relaxation time) with zero loop voltage and small edge localized modes (ELMs) at high density (n(e)/n(GW) similar to 0.6-0.8), beta(P) similar to 2.0, beta(N) similar to 1.6, and f(BS) similar to 47%. Experimental investigations show how plasma current profiles, turbulent transport and radiation properties selfconsistently evolve toward fusion relevant steady state conditions. Modeling and physics experiments have confirmed the synergistic effects between electron cyclotron heating (ECH) and low hybrid wave (LHW), where ECH enhances the heating and current drive from LHW injection, enabling fully noninductive operation at higher density. Small/no ELMs facilitate the RF power coupling in the H-mode phase and reduce divertor erosion. A low tungsten concentration was observed at high beta(P) with a hollow profile in the core. Reduction of the peak divertor heat flux with f(rad) of up to 40% was compatible with the high beta(P) scenario by using active radiation feedback control. With features such as dominant electron heating, zero/low NBI torque and an ITER-like tungsten divertor, fully noninductive high-performance experiments on EAST offer unique contributions towards the succesful operation of ITER and CFETR (the Chinese Fusion Engineering Testing Reactor).
Authors
I am an author on this paper
Click your name to claim this paper and add it to your profile.
Reviews
Recommended
No Data Available