Abstract :
Recent DIII-D tokamak experimental results are summarized, new hardware being implemented to carry out the DIII-D 1990s tokamak research program is described, and their implications for engineering designs for next-generation tokamaks, such as ITER (International Thermonuclear Experimental Reactor), are discussed. DIII-D is presently investigating several new and alternative methods to address key ITER design issues: divertor, disruption, and current profile control. DIII-D is also demonstrating improved tokamak performance regimes such as high beta second stability and high confinement such as VH-mode. On a more basic and broader research front, DIII-D is exploring innovative tokamak engineering and physics concepts, solidifying fundamental plasma physics understanding, and demonstrating essential engineering technologies with the goal of developing a safe and environmentally and commercially attractive fusion reactor concept
Keywords :
fusion reactor theory and design; plasma instability; plasma toroidal confinement; DIII-D; ITER; International Thermonuclear Experimental Reactor; VH-mode; current profile control; design issues; disruption; divertor; engineering designs; fusion reactor concept; high beta second stability; high confinement; next-generation tokamaks; plasma physics; tokamak experimental results; Design engineering; Hardware; Inductors; International collaboration; Physics; Plasma confinement; Power engineering and energy; Radio frequency; Research and development; Tokamaks;
