  The ongoing development of electromagnets based on High Temperature
Superconductors has led to the conceptual exploration of high-magnetic-field
fusion reactors of the tokamak type, operating at on-axis fields above 10 T. In
this work we explore the consequences of the potential future availability of
high-field three-dimensional electromagnets on the physics design point of a
stellarator reactor. We find that, when an increase in the magnetic field
strength $B$ is used to maximally reduce the device linear size $R\sim
B^{-4/3}$ (with otherwise fixed magnetic geometry), the physics design point is
largely independent of the chosen field strength/device size. A similar degree
of optimization is to be imposed on the magnetohydrodynamic, transport and fast
ion confinement properties of the magnetic configuration of that family of
reactor design points. Additionally, we show that the family shares an
invariant operation map of fusion power output as a function of the auxiliary
power and relative density variation. The effects of magnetic field
over-engineering and the $R(B)$ scaling of design points with constant neutron
wall loading are also inspected. In this study we use geometric parameters
characteristic of the helias reactor, but most results apply to other
stellarator configurations
