Catastrophic corrosion cracking of Cr-Mn-V aging austenitic steels

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

Analysis of mechanisms inducing corrosion cracking of irradiated austenitic steels and development of a model for prediction of crack initiation

2020 ◽  
Vol 107 ◽  
pp. 104235 ◽  
Author(s):  
Boris Margolin ◽  
Alexander Sorokin ◽  
Natalia Pirogova ◽  
Aki Toivonen ◽  
Faiza Sefta ◽  
...  
Keyword(s):  
Crack Initiation ◽  
Corrosion Cracking ◽  
Austenitic Steels

Acoustic detection of stress-corrosion cracking of nitrogen austenitic steels

2014 ◽  
Vol 115 (6) ◽  
pp. 586-599 ◽  
Author(s):  
Yu. I. Filippov ◽  
V. V. Sagaradze ◽  
V. A. Zavalishin ◽  
N. L. Pecherkina ◽  
N. V. Kataeva ◽  
...  
Keyword(s):  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Corrosion Cracking ◽  
Austenitic Steels ◽  
Acoustic Detection ◽  
Detection Of Stress

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'
Keyword(s):  
Corrosion Cracking ◽  
Intercrystalline Corrosion ◽  
Austenitic Steels

Model of corrosion cracking of irradiated austenitic steels. Part 1. Analysis of damage mechanisms and formulation of the defining

2019 ◽  
pp. 154-177
Author(s):  
B. Z. Margolin ◽  
A. A. Sorokin ◽  
N. E. Pirogova ◽  
V. A. Potapova ◽  
Aki Toivonen ◽  
...  
Keyword(s):  
Low Temperature ◽  
Grain Boundary ◽  
Threshold Stress ◽  
Original Data ◽  
Potential Effect ◽  
Corrosion Cracking ◽  
Austenitic Steels ◽  
Initiation Time ◽  
Microcrack Propagation ◽  
Low Temperature Creep

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 . 

Evaluation of resistance to corrosion cracking of irradiated austenitic chromium-nickel steels by impact bending tests on miniature specimens

2020 ◽  
pp. 200-215
Author(s):  
B. Z. Margolin ◽  
N. E. Pirogova ◽  
A. A. Sorokin ◽  
A. M. Morozov
Keyword(s):  
Grain Boundaries ◽  
Active Zone ◽  
Corrosion Cracking ◽  
Austenitic Steels ◽  
Bending Test ◽  
Neutron Energy Spectrum ◽  
Bending Tests ◽  
Neutron Spectra ◽  
Miniature Specimens ◽  
The Relationship

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.

Probabilistic Failure Analysis of Austenitic Nuclear Pipelines against Stress Corrosion Cracking

2005 ◽  
Vol 219 (7) ◽  
pp. 607-624 ◽  
Author(s):  
C Priya ◽  
K. B. Rao ◽  
M. B. Anoop ◽  
N Lakshmanan ◽  
V Gopika ◽  
...  
Keyword(s):  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Degradation Mechanism ◽  
Failure Criteria ◽  
Initial Crack ◽  
Corrosion Cracking ◽  
Austenitic Steels ◽  
Failure Assessment ◽  
Degree Of Sensitization ◽  
Failure Probabilities

Stress corrosion cracking (SCC) is an important degradation mechanism to be considered for failure assessment of nuclear piping components made of austenitic steels. In this paper, an attempt has been made to compute the failure probabilities of a piping component against SCC with time using Monte Carlo simulation (MCS) technique. The initiation and propagation stages of stress corrosion cracks are modelled using the general methodology recommended in PRAISE modified by using the recommendations given by ASM for more rational modelling of stress field around cracks for estimating their growth with time. Degree of sensitization, applied stress, time to initiation of SCC, initial crack length, and initiation crack growth velocity are considered as random variables. An attempt has been made to study the stochastic propagation of stress corrosion cracks with time, using MCS technique. The trend of the distribution of crack depths at the initial stages obtained from simulation are compared and is found to be in satisfactory agreement with the relevant experimental observations reported in the literature. The failure probabilities are computed using two different failure criteria, namely (a) based on net-section stress and detectable leak rate as recommended in PRAISE and (b) based on R6 approach (using R6-option 1 curve as the failure assessment diagram). The procedure presented in the paper is general and the usefulness of the same is demonstrated through an example problem.

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