A new approach to the problem of blanket replacement in Tokamak fusion reactors

A new technical blanket concept for Tokamak fusion reactors is proposed which should facilitate the problem of first-wall replacement. It is based on a quadrilateral shape of both the blanket and shield cross-sections. Whereas the shield remains fixed in place, simple blanket elements can be assembled and disassembled along straigth transfer lines that only slightly interfere with the main magnet coils and their support structure. Only four remote handling machines are needed, which operate outside the main magnet coils. Slight modifications also allow this concept to be applied to reactors incorporating a poloidal divertor. Of the main implications of this concept, the effect on the size of the toroidal field coils is investigated. An optimum configuration having economic characteristics which compare very well with current conceptual designs is found