G.L. Jackson et al 2009 Nucl. Fusion 49 115027 doi:10.1088/0029-5515/49/11/115027
G.L. Jackson1,4, T.A. Casper2, T.C. Luce1, D.A. Humphreys1, J.R. Ferron1, A.W. Hyatt1, J.A. Leuer1, T.W. Petrie1, F. Turco3 and W.P. West1
Show affiliationsDIII-D experiments have investigated ITER startup scenarios, including an initial phase where the plasma was limited on low field side poloidal bumper limiters. In addition, li feedback control has been tested with the goal of producing discharges in ITER within the capabilities of the poloidal field coil set and favourable to the intended mode of operations in the subsequent constant current (flattop) phase. These discharges have been modelled using the Corsica free boundary equilibrium code. High performance hybrid scenario discharges (βN = 2.8, H98,y2 = 1.4) and ITER H-mode baseline discharges (βN > 1.6, H98,y2 = 1–1.2) have been obtained experimentally in an ITER similar shape after the ITER-relevant startup. Studies have been initiated to develop a reliable scenario for exiting the burn phase and ramping down the plasma current in ITER without disruptions.
Issue 11 (November 2009)
Received 30 March 2009, accepted for publication 16 September 2009
Published 21 October 2009
G.L. Jackson et al 2009 Nucl. Fusion 49 115027
Özlem Yeşiltaş 2009 Phys. Scr. 80 055003
Hans C Fogedby and Alberto Imparato 2009 J. Phys. A: Math. Theor. 42 475004
H Egger and A Leitão 2009 Inverse Problems 25 115014
Wang Wei et al 2009 Chinese Phys. Lett. 26 114202
P Landeros et al 2009 J. Phys. D: Appl. Phys. 42 225002
Y Y Guo et al 2009 J. Phys.: Condens. Matter 21 485901
K Kato et al 2009 J. Phys.: Conf. Ser. 190 012170
R Sordan et al 2008 Nanotechnology 19 335201
Yong Jiang et al 2009 J. Phys.: Conf. Ser. 190 012100