Stress Corrosion Cracking Behavior of Type 304 Stainless Steel Irradiated under Different Neutron Dose Rates at JMTR

Kaji, Yoshiyuki; Kondo, Keietsu; Aoyagi, Yoshiteru; Kato, Yoshiaki; Taguchi, Taketoshi; Takada, Fumiki; Nakano, Junichi; Ugachi, Hirokazu; Tsukada, Takashi; Takakura, Kei; Sakamoto, Hiroshi

doi:10.1007/978-3-319-48760-1_73

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“…It was referred that, to initiate IG cracks, the applied stress was lower than the yield strength, but dislocation channels and MnS inclusions were observed around GB, where the IASCC cracks initiated. It was observed that crystallographic structure of GBs is decisive for IASCC crack propagation, e.g., in a study on the neutron irradiated specimens of type 304 ASS (JMTR, 1 dpa) tested in high temperature water simulating BWR [60]. The intergranular cracks of IASCC propagated mainly along GHAB.…”

Section: Irradiation Assisted Scc Fracturementioning

confidence: 99%

Overview of Intergranular Fracture of Neutron Irradiated Austenitic Stainless Steels

Hojná

2017

Metals

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Austenitic stainless steels are normally ductile and exhibit deep dimples on fracture surfaces. These steels can, however, exhibit brittle intergranular fracture under some circumstances. The occurrence of intergranular fracture in the irradiated steels is briefly reviewed based on limited literature data. The data are sorted according to the irradiation temperature. Intergranular fracture may occur in association with a high irradiation temperature and void swelling. At low irradiation temperature, the steels can exhibit intergranular fracture at low or even at room temperatures during loading in air and in high temperature water (~300 • C). This paper deals with the similarities and differences for IG fractures and discusses the mechanisms involved. The intergranular fracture occurrence at low temperatures might be correlated with decohesion or twinning and strain martensite transformation in local narrow areas around grain boundaries. The possibility of a ductile-to-brittle transition is also discussed. In case of void swelling higher than 3%, quasi-cleavage at low temperature might be expected as a consequence of ductile-to-brittle fracture changes with temperature. Any existence of the change in fracture behavior in the steels of present thermal reactor internals with increasing irradiation dose should be clearly proven or disproven. Further studies to clarify the mechanism are recommended.

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Section: Irradiation Assisted Scc Fracturementioning

confidence: 99%

Overview of Intergranular Fracture of Neutron Irradiated Austenitic Stainless Steels

Hojná

2017

Metals

View full text Add to dashboard Cite

show abstract

Stress Corrosion Cracking Behavior of Type 304 Stainless Steel Irradiated under Different Neutron Dose Rates at JMTR

Cited by 1 publication

References 2 publications

Overview of Intergranular Fracture of Neutron Irradiated Austenitic Stainless Steels

Overview of Intergranular Fracture of Neutron Irradiated Austenitic Stainless Steels

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