Results 271 to 280 of about 154,916 (330)

Physics and engineering design of 400 keV H- accelerator for negative ion based neutral beam injection system in China.

Review of Scientific Instruments, 2019
A research project of the China Fusion Engineering Test Reactor (CFETR) Negative ion-based Neutral Beam Injection (NNBI) prototype has been started in China.
Jianglong Wei, Chundong Hu, Yahong Xie, Yuming Gu, L. Liang, Caichao Jiang, Yuanlai Xie   +6 more
semanticscholar   +1 more source

Neutral beam injection simulation of EAST

Fusion Engineering and Design, 2011
Abstract EAST (Experimental Advanced Superconducting Tokamak) is a fully superconducting tokamak with single/double null divertor configuration. The NBI (Neutral Beam Inject) system of EAST has two deuterium beam lines, in which beam power is 4 MW and energy is 80 keV. Neutral beam heating in EAST tokamak is simulated using NUBEAM code.
Bin Wu, Jinfang Wang, Jibo Li, Ji Wang, Chundong Hu   +4 more
openaire   +1 more source

Comprehensive research facility for negative ion source neutral beam injection at CRAFT: design and first operation

Plasma Science and Technology
Neutral beam injection (NBI) has been proven as a reliable heating and current drive method for fusion plasma. For the high-energy NBI system (particle energy > 150 keV) of large-scale fusion devices, the negative ion source neutral beam injection (NNBI)
Jianglong Wei, Yahong Xie, Yuanlai Xie, Caichao Jiang, Yuanzhe Z. Zhao, Yongjian Xu, Yuming Gu, W. Yi, Wei Liu, Lvyang Bu, Dezhi Yan, Zhimin Liu, Sheng Liu, Junjun Pan, Shiyong Chen, Ling Yu, Q. Cui, Shihua Song, Yuqing Chen, Ji Wang, Ling Liu, Shengmin Pan, Bin Guo, Zhigang Zhu, Na Wang, Junwei Xie, Yuwen Yang, Tengsai Zhu, Lixin Yang, Yufan Li, Ning Tang, Qianxu Wang, Hui-hui Hong, Bo Liu, Yuqian Li, Yang Lee, Yuming Gu, Xufeng Peng, Shanhu Liu, Yong Wu, Xiancai Meng, Chundong Hu, L. Liang   +42 more
semanticscholar   +1 more source

TFTR neutral beam injected power measurement

Review of Scientific Instruments, 1989
Energy flow within TFTR neutral beamlines is measured with a waterflow calorimetry system capable of simultaneously measuring the energy deposited within four heating beamlines (three ion sources each), or of measuring the energy deposited in a separate neutral beam test stand.
J. H. Kamperschroer, L. R. Grisham, L. E. Dudek, G. M. Gammel, G. A. Johnson, H. W. Kugel, L. Lagin, T. E. O’Connor, P. A. Shah, P. Sichta, T. N. Stevenson, A. von Halle, M. D. Williams, R. Bastasz   +13 more
openaire   +1 more source

Numerical study of neutral beam injection prompt loss at KSTAR poloidal limiters

Physics of Plasmas, 2019
We use a newly developed simulation tool to numerically study fast-ion loading on plasma-facing components (PFCs) at the Korea Superconducting Tokamak Advanced Research facility in the high-poloidal-β plasma operation regime.
T. Rhee, K. Shinohara, Hyun-Seok Kim, J. Kwon, Y. Jeon, Junghee Kim, S. Hahn, J. Kwak, Sonjong Wang, B. Park, B. Na   +10 more
semanticscholar   +1 more source

The MAST neutral beam injection system

Fusion Engineering and Design, 2001
Two neutral beam injectors will provide both plasma heating and current drive on the MAST tokamak using beamlines on loan from Oak Ridge National Laboratory. Progress is reported regarding the following engineering challenges in achieving beam energies up to 70 keV and pulse lengths up to 5 s: design of carbon fibre composite, hypervapotron and ...
M.P.S Nightingale, G.W Crawford, S.J Gee, D.J Hurford, D Martin, M.R Simmonds, R.T.C Smith, C.C Tsai, S.E.V Warder   +8 more
openaire   +1 more source

Impurity control by neutral-beam injection

Nuclear Fusion, 1979
A recently developed generalization of neoclassical theory is applied to study the use of neutral-beam injection to drive impurities out of a tokamak plasma. The theory accounts for the direct momentum exchange between beam and plasma, which has been studied previously, and also for the effects of the beam in altering the first-order particle flows and
W.M. Stacey, D.J. Sigmar
openaire   +1 more source

Long pulse neutral beam injection

Nuclear Fusion, 2003
Long pulse operation has an important impact on the design and utilization of a neutral beam injection system. This paper, first describes briefly the injectors designed for ITER FEAT as they are the first to be designed for long pulse operation under conditions approaching those that will be experienced in future machines.
openaire   +1 more source

Plasma Heating by Neutral Beam Injection

Fusion Technology, 2000
The additional heating of plasmas by injection of fast neutrals - or Neutral Beam Injection (NBI) - is reviewed. First, the limitations of ohmic heating in tokamaks and the other motivations for using additional heating in fusion machines are discussed.
openaire   +1 more source

Negative ion based neutral beam injection

Nuclear Fusion, 2006
It is widely recognized that neutral beam injection (NBI), i.e. the injection of high energy, high power, beams of H or D atoms, is a flexible and reliable system that has been the main heating system on a large variety of fusion devices, and NBI has been chosen as one of the three heating schemes of the International Tokomak Reactor (ITER).
openaire   +1 more source