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

Takuya GOTO, Junichi MIYAZAWA, Hitoshi TAMURA, Teruya TANAKA, Nagato YANAGI, Akio SAGARA and the FFHR Design Group

National Institute for Fusion Science, Toki 509-5292, Japan

(Received 30 November 2015 / Accepted 9 February 2016 / Published 17 May 2016)

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.

Copyright (c) 2016 The Japan Society of Plasma Science and Nuclear Fusion Research

Keywords

helical reactor, breeder blanket, maintenance, toroidal segmentation

DOI: 10.1585/pfr.11.2405047

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References

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