研究報告17 - 1 解説 - Review
LHDから核融合炉へ
From LHD to Fusion Reactor
相良 昭男
核融合科学研究所
〒509-52 土岐市下石町字西山322-6
Akio SAGARA
National Institute for Fusion Science 322-6 Orishicho, Toki 509-52
(Received January 5, 1998; accepted March 9, 1998)
Abstract
Research and development of helical systems
have been persistently continued. New large devices using superconducting
magnets, LHD in Japan and W-7X in Germany, are under construction. These
aggressive programs accelerate several design studies of helical-type reactors,
because of the main advantage of current-less steady operation, as promising
alternatives for Demo reactors.
A reference design of Force Free Helical
Reactor (FTHR) is presented to discuss Demo relevant engineering issues
in the concept definition phase. The main feature of FTHR is force-free-like
configuration of helical coils, which makes it possible to simplify the
coil supporting structure and to use high magnetic field instead of high
plasma beta. The other feature is the selection of molten-salt Flibe as
a self-cooling tritium breeder from the main reason of safety. Collaboration
works based on the LHD project have made great progress in the reactor
studies by focusing on engineering aspects of the high magnetic field and
Flibe system design.