The separation between the last closed flux surface of a plasma and the external coils that magnetically confine it
is a limiting factor in the construction of fusion-capable plasma devices. This plasma-coil separation must be large
enough so that components such as a breeding blanket and neutron shielding can fit between the plasma and the coils.
Plasma-coil separation affects reactor size, engineering complexity, and particle loss due to field ripple. For some
plasmas it can be difficult to produce the desired flux surface shaping with distant coils, and for other plasmas it
is infeasible altogether. Here, we seek to understand the underlying physics that limits plasma-coil separation and
explain why some configurations require close external coils. In this paper, we explore the hypothesis that the limiting
plasma-coil separation is set by the shortest scale length of the magnetic field as expressed by the ∇B tensor. We tested
this hypothesis on a database of > 40 stellarator and tokamak configurations. Within this database, the coil-to-plasma
distance compared to the minor radius varies by over an order of magnitude. The magnetic scale length is well correlated
to the coil-to-plasma distance of actual coil designs generated using the REGCOIL method [Landreman, Nucl. Fusion 57,
046003 (2017)]. Additionally, this correlation reveals a general trend that larger plasma-coil separation is possible with a
small number of field periods.