Analysis of mechanisms inducing corrosion cracking of irradiated austenitic steels and development of a model for prediction of crack initiation
Autor: | Cédric Pokor, N. E. Pirogova, Boris Margolin, Faiza Sefta, Aki Toivonen, A. A. Sorokin |
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Jazyk: | angličtina |
Rok vydání: | 2020 |
Předmět: |
Materials science
Localized deformation Constitutive equation Passive film 020101 civil engineering Damage dose 02 engineering and technology Microcrack 0201 civil engineering Corrosion RPV internals 0203 mechanical engineering General Materials Science Constitutive equations Stress corrosion cracking Grain boundary sliding Grain Boundary Sliding Austenitic steels Austenite Neutron irradiation Metallurgy General Engineering Slow strain rate tests Creep Intergranular fracture Constant load tests Cracking 020303 mechanical engineering & transports Irradiation assisted stress corrosion cracking |
Zdroj: | Margolin, B, Sorokin, A, Pirogova, N, Toivonen, A, Sefta, F & Pokor, C 2020, ' Analysis of mechanisms inducing corrosion cracking of irradiated austenitic steels and development of a model for prediction of crack initiation ', Engineering Failure Analysis, vol. 107, 104235 . https://doi.org/10.1016/j.engfailanal.2019.104235 |
ISSN: | 1873-1961 1350-6307 |
DOI: | 10.1016/j.engfailanal.2019.104235 |
Popis: | The austenitic steels used for RPV internals of light water reactors (LWR) are considered. Mechanisms having a potential effect on irradiation assisted stress corrosion cracking (IASCC) of austenitic steels in the LWR environment have been analyzed. Based on the analysis and generalization of reference and original data on IASCC, an IASCC initiation criterion has been formulated. The nature of low-temperature creep of irradiated austenitic steels has been considered, constitutive equations have been derived. Relying on the formulated criterion of grain-boundary microcrack nucleation and the derived creep equations, an IASCC initiation model has been developed. The model allows one to predict the dependence of the threshold stress σth IASCC on neutron dose and also to calculate the IASCC initiation time with stresses exceeding σth IASCC. |
Databáze: | OpenAIRE |
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