SAP2014 - List of Authors (Hu, C.D.)

Paper	Title	Page
WEPH31	Progress of Development of a 4 MW High Power Ion Source for the EAST Neutral Beam Injector	84
	Y.H. Xie, C.D. Hu ASIPP, Hefei, People's Republic of China
	Funding: Supported by the National Magnetic Confinement Fusion Science Program of China (No. 2013GB101000) A 4 MW high Power ion source is developed for the Experimental Advanced Superconducting Tokamak (EAST) neutral beam injector (NBI). The ion source is designed to generate a deuterium beam of 40-70 A with energy of 50-80 keV，the beam duration is 10-100 seconds. The ion source is consists of a magnetic bucket plasma generator with multi-pole cusp-fields and a set of tetrode accelerators with slit-type apertures. The plasma generator has a rectangular shape arc chamber with dimension of 650mm(Length) * 260mm(Width) * 300mm (Depth). There are 40 lines permanent magnets are installed outside of the arc chamber to form axial line-cusp configuration, and 32 pure tungsten filaments installed to supply primary thermo-electrons. The accelerator consists of plasma gird (PG), gradient grid (GG), suppressor grid (SG) and exit grid (EG). Each grid has 64 rails which are made of molybdenum. The beam extraction area is 120mm * 480mm, and has a transparency of 60 %. The ion source is tested on the test bed. The hydrogen beam power of 4MW with beam energy of 80 keV in 1 second and long pulse of 100 seconds with beam energy of 50 keV are achieved on the test stand respectively.

WEPH32	Measurement of Key Parameters for EAST Neutral Beam Injector	87
	Y. Xu, C.D. Hu, L.Z. Liang, S. Liu, Z.M. Liu, P. Sheng, Y.H. Xie ASIPP, Hefei, People's Republic of China
	Funding: Supported by the National Magnetic Confinement Fusion Science Program of China (2013GB101000). Neutral beam injection is recognized as one of the most effective means of plasma heating. The target values of EAST Neutral beam injector (NBI) are beam energy 50-80kev, injection beam total power 2-4 MW, beam pulse width 10-100s. The beam power will deposit on the beam collimator due to the beam divergence and it will cause heat damage to heat load components, or even destroy the entire NBI system. In order to decrease the risk, the key parameters of NBI, such as divergence angle, beam power density distribution, neutralizing efficiency, the beam power deposited on heat load components, should be assessed. In this article, the calculation principles and experimental results are given. The results direct the operation parameter optimization of EAST NBI and lay a solid foundation for realization of plasma heating for EAST.

Paper

Title

Page

Progress of Development of a 4 MW High Power Ion Source for the EAST Neutral Beam Injector

84

Y.H. Xie, C.D. Hu
ASIPP, Hefei, People's Republic of China

Funding: Supported by the National Magnetic Confinement Fusion Science Program of China (No. 2013GB101000)
A 4 MW high Power ion source is developed for the Experimental Advanced Superconducting Tokamak (EAST) neutral beam injector (NBI). The ion source is designed to generate a deuterium beam of 40-70 A with energy of 50-80 keV，the beam duration is 10-100 seconds. The ion source is consists of a magnetic bucket plasma generator with multi-pole cusp-fields and a set of tetrode accelerators with slit-type apertures. The plasma generator has a rectangular shape arc chamber with dimension of 650mm(Length) * 260mm(Width) * 300mm (Depth). There are 40 lines permanent magnets are installed outside of the arc chamber to form axial line-cusp configuration, and 32 pure tungsten filaments installed to supply primary thermo-electrons. The accelerator consists of plasma gird (PG), gradient grid (GG), suppressor grid (SG) and exit grid (EG). Each grid has 64 rails which are made of molybdenum. The beam extraction area is 120mm * 480mm, and has a transparency of 60 %. The ion source is tested on the test bed. The hydrogen beam power of 4MW with beam energy of 80 keV in 1 second and long pulse of 100 seconds with beam energy of 50 keV are achieved on the test stand respectively.

WEPH32

Measurement of Key Parameters for EAST Neutral Beam Injector

87

Y. Xu, C.D. Hu, L.Z. Liang, S. Liu, Z.M. Liu, P. Sheng, Y.H. Xie
ASIPP, Hefei, People's Republic of China

Funding: Supported by the National Magnetic Confinement Fusion Science Program of China (2013GB101000).
Neutral beam injection is recognized as one of the most effective means of plasma heating. The target values of EAST Neutral beam injector (NBI) are beam energy 50-80kev, injection beam total power 2-4 MW, beam pulse width 10-100s. The beam power will deposit on the beam collimator due to the beam divergence and it will cause heat damage to heat load components, or even destroy the entire NBI system. In order to decrease the risk, the key parameters of NBI, such as divergence angle, beam power density distribution, neutralizing efficiency, the beam power deposited on heat load components, should be assessed. In this article, the calculation principles and experimental results are given. The results direct the operation parameter optimization of EAST NBI and lay a solid foundation for realization of plasma heating for EAST.