Corrosion cracking and intercrystalline corrosion of chrome-manganese-nickel austenitic steels

1990 ◽  
Vol 25 (6) ◽  
pp. 607-609 ◽  
Author(s):  
G. V. Chumalo ◽  
R. K. Melekhov ◽  
P. N. Fedyakin ◽  
M. V. Koval'
2020 ◽  
Vol 107 ◽  
pp. 104235 ◽  
Author(s):  
Boris Margolin ◽  
Alexander Sorokin ◽  
Natalia Pirogova ◽  
Aki Toivonen ◽  
Faiza Sefta ◽  
...  

1991 ◽  
Vol 23 (1) ◽  
pp. 60-66 ◽  
Author(s):  
V. A. Zavalishin ◽  
V. V. Sagaradze ◽  
Yu. I. Filippov ◽  
I. I. Kositsyna ◽  
T. P. Vasechkina

2014 ◽  
Vol 115 (6) ◽  
pp. 586-599 ◽  
Author(s):  
Yu. I. Filippov ◽  
V. V. Sagaradze ◽  
V. A. Zavalishin ◽  
N. L. Pecherkina ◽  
N. V. Kataeva ◽  
...  

2019 ◽  
pp. 154-177
Author(s):  
B. Z. Margolin ◽  
A. A. Sorokin ◽  
N. E. Pirogova ◽  
V. A. Potapova ◽  
Aki Toivonen ◽  
...  

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. Conditions for grainboundary microcrack propagation by IASCC mechanism have 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 σIASCC th on neutron dose and also to calculate the IASCC initiation time with stresses exceeding σIASCCth . 


Author(s):  
B. Z. Margolin ◽  
N. E. Pirogova ◽  
A. A. Sorokin ◽  
A. M. Morozov

In this work, we present results of a bending test of miniature specimens made of chromium-nickel stainless austenitic steels of grades 321 (08Kh18N10T), 316 (06Kh16N11M3) and 304 (02Kh18N9) irradiated to various damage doses from 4 to 125 dpa in different energy neutron spectra. Effects of the damage dose and the neutron energy spectrum on the intergranular fracture energy, which determines the strength of grain boundaries, are studied. Two neutron spectra are considered: one characteristic of the active zone of PWR and WWER reactors, and the other is typical for the active zone of fast core reactors. The relationship between the resistance to corrosion cracking of irradiated chromium-nickel steels 321, 316 and 304 and the strength of grain boundaries is considered.


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