Stainless steels exposed to radiation and hot water may fail by irradiation
-assisted stress corrosion cracking. Cracking is especially evident in aust
enitic stainless steels exposed to light-water reactor irradiation and oxid
izing water chemistry at temperatures near 288 degrees C. Neutron doses gre
ater than one displacement per atom are typically required to induce observ
ed cracking susceptibility. Thee evidence of a threshold dose suggests that
radiation-induced material changes promote irradiation-assisted stress cor
rosion cracking, not radiation effects on water chemistry. Radiation-induce
d chromium depletion is considered the primary material change impacting th
is cracking. Impurity influences on solute segregation are apparent and may
influence specific alloy susceptibility. Synergistic chemical/mechanical c
reep contributions to the intergranular failure mode are not important for
light-water reactor conditions.