TY - JOUR
T1 - Improved high-performance fully non-inductive discharge by optimizing the fast-ion confinement on EAST
AU - EAST Team
AU - Huang, J.
AU - Qian, J.P.
AU - Garofalo, A.M.
AU - Gong, X.Z.
AU - Wu, C.R.
AU - Chang, J.F.
AU - Zhang, J.
AU - Du, H.F.
AU - Wu, M.Q.
AU - Hao, B.L.
AU - Yu, L.M.
AU - Zhang, X.M.
AU - Madsen, B.
AU - Salewski, Mirko
AU - Liang, L.Z.
AU - Li, J.
AU - Ding, S.Y.
AU - Zhong, G.Q.
AU - Chen, J.L.
AU - Zhu, X.
AU - Zeng, L.
AU - Li, E.Z.
AU - Zhang, B.
AU - Xu, Z.
AU - Su, J.X.
AU - Gao, W.
AU - Chen, Y.J.
AU - Li, Y.Y.
AU - Liu, H.
AU - Lyu, B.
AU - Zang, Q.
AU - Wan, B.
PY - 2020
Y1 - 2020
N2 - The attainment of long-pulse, high-performance, fully non-inductive plasma is one of the major scientific objectives of EAST, using the ITER-like tungsten upper divertor. Understanding and optimizing the fast-ion behaviors is the critical issue to extending the performance of EAST. Recently, using both neutral beam injection (NBI) and radio frequency (RF; low hybrid, electron cyclotron, and ion cyclotron) heating, fully non-inductive high-βP scenarios with extension of fusion performance at high density and low rotation have been achieved, with βP up to 2.5, βN up to 2.0, H98y 2 > 1.1, and bootstrap current fraction (f BS) up to 50%. For previous long-pulse H-mode plasma at medium density, when NBI is added into RF plasma, βP is increased from 1.2 to 2.0 compared with RF-only discharges. In fact, f BS for both discharges is nearly the same, at ~22%. Analysis shows that the increase in βp is mostly due to fast ions which do not contribute significantly to the neoclassical bootstrap current. Thus, to obtain high-performance plasmas with improved bootstrap current fraction, key parameters (e.g. density, beam energy, etc.) must be further optimized. Experimental results show that high density improves bootstrap fraction also by reducing fast-ion slowing-down time and loss. The lower beam energy also mitigates fast-ion loss, which is better for heating and CD performance. The extension of high-performance, fully non-inductive experiments on EAST at high density and zero/low NBI torque can potentially offer unique contributions towards ITER and CFETR.
AB - The attainment of long-pulse, high-performance, fully non-inductive plasma is one of the major scientific objectives of EAST, using the ITER-like tungsten upper divertor. Understanding and optimizing the fast-ion behaviors is the critical issue to extending the performance of EAST. Recently, using both neutral beam injection (NBI) and radio frequency (RF; low hybrid, electron cyclotron, and ion cyclotron) heating, fully non-inductive high-βP scenarios with extension of fusion performance at high density and low rotation have been achieved, with βP up to 2.5, βN up to 2.0, H98y 2 > 1.1, and bootstrap current fraction (f BS) up to 50%. For previous long-pulse H-mode plasma at medium density, when NBI is added into RF plasma, βP is increased from 1.2 to 2.0 compared with RF-only discharges. In fact, f BS for both discharges is nearly the same, at ~22%. Analysis shows that the increase in βp is mostly due to fast ions which do not contribute significantly to the neoclassical bootstrap current. Thus, to obtain high-performance plasmas with improved bootstrap current fraction, key parameters (e.g. density, beam energy, etc.) must be further optimized. Experimental results show that high density improves bootstrap fraction also by reducing fast-ion slowing-down time and loss. The lower beam energy also mitigates fast-ion loss, which is better for heating and CD performance. The extension of high-performance, fully non-inductive experiments on EAST at high density and zero/low NBI torque can potentially offer unique contributions towards ITER and CFETR.
KW - Magnetic fusion
KW - Fully non-inductive tokamak
KW - Fast-ion behavior
KW - Neutral beam
U2 - 10.1088/1741-4326/ab443a
DO - 10.1088/1741-4326/ab443a
M3 - Journal article
SN - 0029-5515
VL - 60
JO - Nuclear Fusion
JF - Nuclear Fusion
IS - 1
M1 - 016002
ER -