In order to investigate the effect of oxide film on the initiation of irradiation assisted stress corrosion (IASCC), UCL (uniaxial constant load) tests of highly irradiated type 304 stainless steel (neutron fluence: 1.4x1026n/m2, E>1MeV) with oxide film by pre-immersion were conducted in high temperature oxygenated pure water. IASCC susceptibilities were not observed even over the IASCC threshold stress level at 463-523 MPa during 2,000 hour tests. Analysis of TTF (times to failure) results in polished specimen of highly irradiated steels also supported the idea that the surface oxide film on irradiated specimens would affect the IASCC initiation mechanism, but not for IGSCC in unirradiated sensitized stainless steel. The mechanism of IASCC behaviour was discussed from the viewpoint of the relationship between chromium depletion at a grain boundary and the surface oxide film.

Subject
Materials, Intergranular stress corrosion cracking, Precipitates, Oxide layers, Oxide films, Irradiation assisted stress corrosion cracking, Stress, Mechanical failure, Surface oxides, Steel, Immersion, Stainless steel, Grain boundary
Keywords:
stainless steel, irradiation-assisted stress corrosion (IASCC), uniaxial constant load (UCL) test, pre-immersion, pre-oxidation, oxide film, surface condition, IGSCC, light water reactor
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1995
Association for Materials Protection and Performance (AMPP)
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