As from frequent observations Stress Corrosion Cracking (SCC) of nuclear reactor
components may be initiated and its propagation also controlled by local pitting and
crevice corrosion. Deterministic modeling of local corrosion including incubation times
for crevice corrosion and related anodic acidification should therefore provide a basis
for component lifetime predictions. Based on previous work for room temperature (RT),
the crevice corrosion at 288°C of nickel as an important base element in respective
high alloyed nuclear materials is modeled by coupling anodic polarization with
formation of nickel oxide and chloride calculated from the water-hydrogen-nickelchloride
heterogeneous phase equilibrium diagram. As a boundary condition, hydrogen
treatment of irradiation subjected cooling water for reduction of corrosion potentials
and mitigation of SCC in Boiling Water Reactors (BWR) is included.