A study was conducted to define the limitations in system performance that resulted from the selection of either Type 316 stainless steel or an idealized vanadium alloy for a lithium-cooled tokamak fusion reactor system. These studies resulted in a definition of the physical properties for fatigue, creep-fatigue, crack growth and creep rupture that were required to achieve a goal life of 10 MW-yr/m**2. The fatigue and creep-fatigue properties of annealed stainless steel appear marginal while the expected vanadium properties appear quite adequate. The potential benefits of both cold work and irradiation on the fatigue properties of Type 316 stainless steel were identified. The crack growth analysis again showed that the Type 316 stainless steel properties may be in need of improvement. The creep rupture requirements were found to be in line with the limited available data on irradiated stainless steel.