A modular blanket has been proposed for a fusion experimental reactor,
such as ITER, to enhance its maintainability as well as improve its f
ablicability. The blanket module is connected to a strong back plate v
ia support legs protruded From both of the module and the back plate.
A welding approach has been investigated for the joining of the suppor
t leg that is 70 mm thick to withstand electromagnetic forces and with
limited welding/cutting heads working space of 100 mm x 150 mm adjace
nt to the support leg. After comparison of several methods, e.g. NGTIG
, NGMIG and iodine laser, NGTIG has been selected as a reference for w
elding and plasma cutting for cutting. Iodine laser has been chosen as
an alternative for both of welding and cutting. Through preliminary d
esign studies, the possibility of small welding/cutting heads includin
g their driving systems available to the limited space has been shown.
Maintenance route for in-situ module replacement with temporary fixtu
re jigs has been also investigated.