Analysis of Mechanisms Inducing Corrosion Cracking of Irradiated Austenitic Steels and Development of a Model for Prediction of Crack Initiation

Boris Margolin, Alexander Sorokin, Natalia Pirogova, Aki Toivonen, Faiza Sefta, Cedric Pokor

Research output: Contribution to journalArticleScientificpeer-review

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 on neutron dose and also to calculate the IASCC initiation time with stresses exceeding the threshold stress.
Original languageEnglish
JournalEngineering Failure Analysis
Publication statusAccepted/In press - 1 Oct 2019
MoE publication typeA1 Journal article-refereed

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Austenitic steel
Stress corrosion cracking
Crack initiation
Irradiation
Light water reactors
Creep
Microcracks
Constitutive equations
Dosimetry
Neutrons
Grain boundaries
Nucleation
austenitic steel
Temperature

Cite this

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title = "Analysis of Mechanisms Inducing Corrosion Cracking of Irradiated Austenitic Steels and Development of a Model for Prediction of Crack Initiation",
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 on neutron dose and also to calculate the IASCC initiation time with stresses exceeding the threshold stress.",
author = "Boris Margolin and Alexander Sorokin and Natalia Pirogova and Aki Toivonen and Faiza Sefta and Cedric Pokor",
year = "2019",
month = "10",
day = "1",
language = "English",
journal = "Engineering Failure Analysis",
issn = "1350-6307",
publisher = "Elsevier",

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Analysis of Mechanisms Inducing Corrosion Cracking of Irradiated Austenitic Steels and Development of a Model for Prediction of Crack Initiation. / Margolin, Boris; Sorokin, Alexander; Pirogova, Natalia; Toivonen, Aki; Sefta, Faiza; Pokor, Cedric.

In: Engineering Failure Analysis, 01.10.2019.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Analysis of Mechanisms Inducing Corrosion Cracking of Irradiated Austenitic Steels and Development of a Model for Prediction of Crack Initiation

AU - Margolin, Boris

AU - Sorokin, Alexander

AU - Pirogova, Natalia

AU - Toivonen, Aki

AU - Sefta, Faiza

AU - Pokor, Cedric

PY - 2019/10/1

Y1 - 2019/10/1

N2 - 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 on neutron dose and also to calculate the IASCC initiation time with stresses exceeding the threshold stress.

AB - 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 on neutron dose and also to calculate the IASCC initiation time with stresses exceeding the threshold stress.

M3 - Article

JO - Engineering Failure Analysis

JF - Engineering Failure Analysis

SN - 1350-6307

ER -