Plasma heat and particle exhaust in divertor of thermonuclear reactor

Based on the steady development of the research at three large tokamaks in the world, the construction of the thermonuclear fusion experimental reactor (ITER) is planned, and the conceptual design activity was finished in 1990. In 1992, the engineering design activity was started in Japan, Germany and USA. About 1200 man-year engages in the EDA for six years, and the budget is expected to be 750 million dollars. For realizing the ITER, the control of heat and particle exhaust is very important. The magnetic divertor accomplishes the role of discharging helium ash and circulating fuel particles. As the physical and chemical processes in the divertor, plasma-surface interaction, the transport of impurities in divertor plasma and the discharge of helium ash are explained. Various divertor concepts have been devised to decrease the thermal load on divertor plates, such as gas divertor, ergodic magnetic limiter and others, and their principles are shown. The basic research on various physical and chemical processes in the composite system of divertor plasma and divertor plate can be carried out by using the linear divertor simulation testing equipment that generates high heat flux plasma. (K.I.)