  It is found that the X-Divertor (XD) configuration [1-3] can be made with the
conventional PF coil set on ITER[4], where all PF coils are outside the TF
coils. Desirable configurations are possible where the PF currents are below
the present maximum design limits on ITER, and where the baseline divertor
cassette is used. It is possible that the XD could be used to assist in
high-power operation on ITER, but some further issues need examination. Note
that the increased major radius of the Super X-Divertor (SXD) [5-8] is not a
feature of the XD geometry. In addition, we present an XD configuration for
K-DEMO [9], to demonstrate that it is also possible to attain the XD
configuration in advanced tokamak reactors with all PF coils outside the TF
coils. The results given here for the XD are far more encouraging than recent
calculations by Lackner and Zohm [10] for the Snowflake [11,12], where the
required high PF currents represent a major technological challenge. The
magnetic field structure in the outboard divertor SOL [13] in the recently
created XD configurations reproduces what was presented in the earlier XD
papers [1-3]. Consequently, the same advantages accrue, but no close-in PF
coils are employed.
