LHD is a fusion experimental device with pool-cooled superconducting h
elical coils. The transverse component of the magnetic field in the he
lical coils becomes zero near Ore core of the coil and becomes higher
toward the edge. On the contrary, load per unit length on each discont
inuous insulator between the conductors becomes the largest at the cor
e region of the coil. By changing wetted surface fraction of the condu
ctors according to the strength of the field, the cryogenic stability
of the coil can be enhanced without enlarging the maximum compressive
stress on the insulators.