Abstract
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.
Original language | English |
---|---|
Article number | 104235 |
Journal | Engineering Failure Analysis |
Volume | 107 |
Early online date | 14 Oct 2019 |
DOIs | |
Publication status | Published - Jan 2020 |
MoE publication type | A1 Journal article-refereed |
Keywords
- Austenitic steels
- Constant load tests
- Constitutive equations
- Creep
- Damage dose
- Grain boundary sliding
- Intergranular fracture
- Irradiation assisted stress corrosion cracking
- Localized deformation
- Microcrack
- Neutron irradiation
- Passive film
- RPV internals
- Slow strain rate tests