Results 231 to 240 of about 26,082 (263)

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

DESIGN OF THE NEUTRAL BEAM INJECTION SYSTEM FOR ASDEX-UPGRADE

1989
For the ASDEX-Upgrade tokamak additional heating by long pulse neutral injection is forseen with a power of 6 MW when injecting hydrogen and 9 MW when injecting deuterium. This paper gives an overview of the injection system with the main emphasis on the mechanical parts.
Stäbler, A., Feist, J., Speth, E., Dunne, J., Götz, S., Heinemann, B., Krauss, A., Kunze, R., Lohnert, H., Sielanko, J., Szyszko, W., Vollmer, O., Wittenbecher, K.   +12 more
openaire   +2 more sources

Calculation of Beam Intensity Distribution for the Neutral Beam Injection in EAST

Plasma Science and Technology, 2011
Theoretical beam intensity distribution is derived for the neutral-beam-injection ion source with a multi-slot extraction in EAST. The beam intensity profile, both along and perpendicular to the injecting direction and the beam power deposition to the inner elements in the neutral beam injector (NBI) are evaluated.
Lizhen Liang, Chundong Hu, Yuanlai Xie, Qiang Guo, Yahong Xie   +4 more
openaire   +1 more source

Electron injection by edge localized neutral beams

Nuclear Fusion, 1990
A negative potential in the edge region of a tokamak plasma may induce a transition from L-mode to H-mode confinement. Such a negative potential may be produced by injection of various atomic species via edge localized neutral beams, with subsequent prompt loss of ions.
T. Ohkawa, R.L. Miller
openaire   +1 more source

Neutral Beam Injection for the Doublet III Device

IEEE Transactions on Plasma Science, 1979
Neutral beam injection into Doublet III has been considered with regard to the calculation of non thermalizing particle orbits and the confinement of such orbits. Injected particle loss, based upon these orbits, toroidal gyro-radius effects, and plasma transparency, is calculated to be on the order of 5 percent for coinjection.
J. H. Kamperschroer, D. K. Bhadra
openaire   +1 more source

Gas heating in the neutralizer of the ITER neutral beam injection systems

Nuclear Fusion, 2006
Indirect heating of the neutralizer gas by the beam has been shown to be responsible for the reduced neutralization efficiency observed in positive ion neutral beam systems. The translational gas temperature can be predicted from the neutralizer plasma density and electron temperature and, in general, a higher gas temperature implies a lower ...
openaire   +1 more source

Perpendicular neutral beam injection into the stellarator W7-AS

Plasma Physics and Controlled Fusion, 2003
The radial electric field Er is of crucial importance for the global confinement properties of a stellarator plasma. In particular, in the long-mean-free-path regime, which is characterized by strongly enhanced neoclassical transport, the ambipolar Er can help to reduce the unfavourably large neoclassical transport coefficients.
J Baldzuhn, A Werner, H Wobig, N Rust, S Klose, W7-AS Team   +5 more
openaire   +1 more source

Optimization of neutral beam injection in the beam plasma neutron source

Nuclear Fusion, 1995
The power efficiency of neutron production in the Beam Plasma Neutron Source (BPNS), proposed as a volumetric 14 MeV neutron source, is maximized at an energy of 110-120 keV for positive ion based (deuteron) neutral beams. Deuterons injected into a triton plasma and tritons into a deuteron plasma are shown to give equal results at the same injection ...
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

NEUTRAL BEAM TRANSMISSION IN AN INJECTION LINE

1976
J.F. Bonnal, J. Druaux, R. Oberson
openaire   +1 more source