REVIEW ON THE DEVELOPMENT OF ITER LIKE DIVERTOR PLASMA FACING COMPONENT

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.