Proposal for the Method of Maintaining Breeder Blankets in the LHD-Type Helical Fusion Reactor FFHR

Abstract

A maintenance method for the breeder blanket of the LHD-type helical reactor FFHR was considered. A simple segmentation in a plane with a constant toroidal angle was proposed by utilizing the flexible arrangement capacity of the coolant path in the blanket module with a molten salt tritium breeder. Moreover, it was found that all blanket modules can be extracted by a combination of uniaxial movements and poloidal rotation without cutting of the coolant pipes inside the vacuum vessel.