Title :
Neutral beams for ITER
Author :
Hemsworth, R.S. ; Feist, H.D. ; Hanada, M. ; Heinemann, B. ; Inoue, T. ; Kussel, E. ; Krylov, A. ; Lotte, P. ; Miyamoto, K. ; Miyamoto, N. ; Murdoch, D. ; Nagase, A. ; Ohara, Y. ; Okumura, Y. ; Pamela, J. ; Panasenkov, A. ; Shibata, K. ; Tanii, M. ; Watso
Author_Institution :
Joint Central Team, ITER, Naka, Japan
fDate :
30 Sep-5 Oct 1995
Abstract :
Neutral Beam Injection (NBI) is a candidate heating and current drive system for the International Tokamak Experimental Reactor (ITER). This paper describes the system which is presently being designed in Europe, Japan and Russia, with coordination by the Joint Central Team of ITER at Naka, Japan. The proposed system consists of three negative ion based neutral injectors, delivering a total of 50 MW of 1 MeV D0 to the ITER plasma for pulse lengths of >1000 s
Keywords :
Tokamak devices; fusion reactor design; fusion reactors; ion beams; plasma beam injection heating; plasma toroidal confinement; 1 MeV; 1000 s; 50 MW; D; ITER; International Tokamak Experimental Reactor; NBI; current drive system; heating system; negative ion based neutral injectors; neutral beam injection; Ducts; Fusion reactors; Heating; Ignition; Ion sources; Particle beam injection; Plasma temperature; Region 8; Thermal force; Toroidal magnetic fields;
Conference_Titel :
Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium
Conference_Location :
Champaign, IL
Print_ISBN :
0-7803-2969-4
DOI :
10.1109/FUSION.1995.534218
