Injection performance prediction of the upgraded neutral beam on EAST

被引:9
作者
Wang, Ji [1 ]
Chen, Yuqing [1 ]
Wu, Bin [1 ]
Yang, Zhen [1 ]
Hu, Chundong [1 ]
Xie, Yuanlai [1 ]
Xie, Yahong [1 ]
Zhong, Guoqiang [1 ]
He, Liang [1 ]
Wang, Fudi [1 ]
机构
[1] Chinese AcAd Sci, Inst Plasma Phys, Hefei, Peoples R China
基金
中国国家自然科学基金;
关键词
Neutral beam; Plasma heating; Power losses; Neutron rate; Current drive; CURRENT DRIVE; TRANSPORT;
D O I
10.1016/j.fusengdes.2021.112277
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The neutral beams(NB) on EAST are being upgraded according to the scheme that the beamline located on Port F will be moved to Port D and adjusted clockwise injection to counterclockwise injection(top view), while the beamline on Port A is unchanged with counterclockwise injection. The two beamlines are modified to counterclockwise injection consistent with the direction of plasma current (co-IP) instead of the primarily balancedinjection (co-IP and counter-IP). The two coming co-IP beamlines are expected to play important roles in plasma heating, neutron emission and current drive in EAST operating scenarios. The injection performances after the beam upgrade are predicted by the simulation codes ONETWO/NUBEAM and TRANSP/NUBEAM to model the discharges on EAST. After the beamlines are upgraded, the bulk ions are heated to a high temperature above 3.2 keV, which is much higher than that in the previous experiments. The orbit loss drops sharply by 83 % and the external charge exchange loss drops by 50 % after the beamline upgrade. The neutron rate induced by the upgraded beamline is greatly enhanced to the order of 1014/s with co-IP injection as opposed to the balancedinjection, and it is also heightened with the increases of plasma density and beam power. The simulation results show that it leads to a significant improvement of the beam-driven current and provides a practical condition for EAST to carry out long pulse and steady-state experiments. The assessment on the injection capabilities of the upgraded neutral beams is an important guiding reference to the subsequent EAST experiments.
引用
收藏
页数:6
相关论文
共 26 条
[1]   Conceptual design of a neutral beam heating & current drive system for DTT [J].
Agostinetti, P. ;
Bolzonella, T. ;
Gobbin, M. ;
Sonato, P. ;
Spizzo, G. ;
Vallar, M. ;
Vincenzi, P. .
FUSION ENGINEERING AND DESIGN, 2019, 146 :441-446
[2]  
Chaohui Yu, 2019, arXiv
[3]   Study of fast-ion losses in experiments on neutral beam injection on the Globus-M spherical tokamak [J].
Chernyshev, F. V. ;
Afanasyev, V. I. ;
Gusev, V. K. ;
Ivanov, A. E. ;
Kurskiev, G. S. ;
Melnik, A. D. ;
Minaev, V. B. ;
Mironov, M. I. ;
Nesenevich, V. G. ;
Patrov, M. I. ;
Petrov, M. P. ;
Petrov, S. Ya. ;
Petrov, Yu. V. ;
Sakharov, N. V. ;
Tolstyakov, S. Yu. .
PLASMA PHYSICS REPORTS, 2011, 37 (07) :553-571
[4]   Fast-ion transport and neutral beam current drive in ASDEX upgrade [J].
Geiger, B. ;
Weiland, M. ;
Jacobsen, A. S. ;
Rittich, D. ;
Dux, R. ;
Fischer, R. ;
Hopf, C. ;
Maraschek, M. ;
McDermott, R. M. ;
Nielsen, S. K. ;
Odstrcil, T. ;
Reich, M. ;
Ryter, F. ;
Salewski, M. ;
Schneider, P. A. ;
Tardini, G. .
NUCLEAR FUSION, 2015, 55 (08)
[5]   Helium neutral beam injection into ASDEX Upgrade [J].
Hopf, C. ;
Rittich, D. ;
Schaeffler, J. ;
Thalhammer, J. .
FUSION ENGINEERING AND DESIGN, 2017, 123 :281-284
[6]   ITER R&D: Auxiliary systems: Neutral beam heating and current drive system [J].
Inoue, T ;
Hemsworth, R ;
Kulygin, V ;
Okumura, Y .
FUSION ENGINEERING AND DESIGN, 2001, 55 (2-3) :291-301
[7]   Neutral beam heating on the TCV tokamak [J].
Karpushov, Alexander N. ;
Chavan, Rene ;
Coda, Stefano ;
Davydenko, Vladimir I. ;
Dolizy, Frederic ;
Dranitchnikov, Aleksandr N. ;
Duval, Basil P. ;
Ivanov, Alexander A. ;
Fasel, Damien ;
Fasoli, Ambrogio ;
Kolmogorov, Vyacheslav V. ;
Lavanchy, Pierre ;
Llobet, Xavier ;
Marletaz, Blaise ;
Marmillod, Philippe ;
Martin, Yves ;
Merle, Antoine ;
Perez, Albert ;
Sauter, Olivier ;
Siravo, Ugo ;
Shikhovtsev, Igor V. ;
Sorokin, Aleksey V. ;
Toussaint, Matthieu .
FUSION ENGINEERING AND DESIGN, 2017, 123 :468-472
[8]   Plasma heating by neutral beam injection [J].
Koch, R .
FUSION SCIENCE AND TECHNOLOGY, 2006, 49 (2T) :167-176
[9]   Fast-ion velocity-space tomography using slowing-down regularization in EAST plasmas with co- and counter-current neutral beam injection [J].
Madsen, B. ;
Huang, J. ;
Salewski, M. ;
Jarleblad, H. ;
Hansen, P. C. ;
Stagner, L. ;
Su, J. ;
Chang, J. F. ;
Fu, J. ;
Wang, J. F. ;
Liang, L. Z. ;
Zhong, G. Q. ;
Li, Y. Y. ;
Lyu, B. ;
Liu, H. Q. ;
Zang, Q. ;
Luo, Z. P. ;
Nocente, M. ;
Moseev, D. ;
Fan, T. S. ;
Zhang, Y. M. ;
Yang, D. ;
Sun, J. Q. ;
Liao, L. Y. .
PLASMA PHYSICS AND CONTROLLED FUSION, 2020, 62 (11)
[10]  
Owen L.W., 2010, NUCL FUSION, P50