REVIEW ON THE DEVELOPMENT OF ITER LIKE DIVERTOR PLASMA FACING COMPONENT
Department of mechanical engineering, L .D. College of engineering, Ahmedabad, India
ABSTRACT
Development of plasma facing component of divertor for the world's largest experimental tokamak nuclear fusion reactor. Reviewer has studied different plasma facing components and also highlighted the development process of plasma facing component. Divertor is one of the key component of fusion reactor and its function is to extract heat and helium ash. At the beginning, CFC is selected as a lower portion of OVT(outer vertical target ) and IVT(Inner vertical target) for its superior thermal shock resistance and high thermal conductivity and tungsten(W) is selected as an armor material for Dome, flat plate and upper region of OVT and IVT. Design and development of monoblock is describe and different techniques for joining the heat sink and cooling tube were discussed. Fishing scale are provided for edge protection of Monoblock. Development of small, medium and full scale plasma facing component with actively cooling system. Full set of divertor is ready and provided to ITER. More R&D work is require on full W divertor component.
