[en] The Spheromak has no external toroidal coil topologically linking the plasma and has many advantages from the view-point of simplifying reactor engineering. Among global MHD modes expected in Spheromak tilting instabilities are peculiar to Spheromak and compact torus configurations. Rosenbluth and Bussac first pointed out the tilting-stability criterion for elongated spheromak, and the author has recently extended their approach to the internal-tilting-mode stability of the arbitrary shaped spheromak. The work described here is to check external mode criterion for arbitrary shaped spheromak and to find the optimum spheromak configuration stable against both internal and external tilting instabilities