The spheromak, as a compact toroidal magnetic fusion device, offers su
bstantial advantages as a fusion reactor concept over larger, more com
plicated, and more costly devices such as the tokamak. The very defini
te advantages associated with the simply closed geometry, minimized ex
ternal coil requirements and the possibility of ohmic ignition in the
spheromak, represent a substantial improvement over conventional magne
tic fusion reactor designs. Furthermore, recent successes in improving
confinement parameters (T-e similar to 400 eV, T-i similar to 1 keV,
n(e) similar to 5 x 10(14) cm(-3), B similar to 1T) have renewed inter
est in advancing this concept to a proof of principle, reactor prototy
pe stage. Herein, the initial work by Fowler et al. (Comments Plasma P
hys. Control. Fusion 16 (1994) 91), indicating the possibility of ohmi
c ignition in spheromaks, is extended to a two fluid model that includ
es direct ion heating. Non-ohmic magnetic dissipation, contributing to
direct ion heating, and confinement scaling are quantified through co
mparison with the latest results from the gun driven Compact Torus Exp
eriment (CTX) spheromak (Phys. Fluids B 2 (1990) 1342). Excellent agre
ement is demonstrated between experimentally measured plasma parameter
s and our model predictions. Extrapolation to ignition experiments and
reactor relevant conditions is discussed, indicating the possibility
of reaching these conditions by gun driven ohmic heating alone and ill
ustrating the merits of direct ion heating. Conservative to pessimisti
c confinement estimates are used throughout so as to ensure that the p
romise offered by this concept does not presume unrealizable improveme
nts in energy containment.