The corrosion fatigue behavior of AISI 316L (UNS S31603) stainless ste
el was tested in concentrated aqueous lithium hydroxide solutions at e
levated temperature. Fatigue tests were conducted in a 10 g LiOH/100cc
H2O solution at 95-degrees-C at controlled electrochemical potentials
. Experimental conditions met requirements of the aqueous Li salt blan
ket option for the international and European nuclear fusion reactor p
rograms of the International Thermonuclear Experimental Reactor (ITER)
and Next European Torus (NET). Results indicated 316L stainless steel
was susceptible to corrosion fatigue in a narrow potential range of a
pproximately 100 m V (vs SCE). Tests at lower or higher potentials (e.
g., -80 and 200 m V), however, did not show susceptibility to corrosio
n fatigue cracking. Results were compared with the stress corrosion cr
acking behavior of 316L in the same environment.