Theoretical Estimation of Crack Growth Rates in Type 304 Stainless Steel in Boiling-Water Reactor Coolant Environments

D. D. Macdonald; P. C. Lu; M. Urquidi-Macdonald; T. K. Yeh

Theoretical Estimation of Crack Growth Rates in Type 304 Stainless Steel in Boiling-Water Reactor Coolant Environments

D. D. Macdonald
, P. C. Lu
, M. Urquidi-Macdonald
, T. K. Yeh

King Fahd University of Petroleum & Minerals

Research output: Contribution to journal › Article › peer-review

25 Scopus citations

Abstract

The coupled-environment fracture model (CEFM) for intergranular stress corrosion cracking (IGSCC) of sensitized type 304 (UNS S30400) stainless steel (SS) in light-water reactor (LWR) heat-transport circuits was extended by incorporating steel corrosion, hydrogen (H²) oxidation, and hydrogen peroxide (H₂O₂ reduction In addition to oxygen (O₂) reduction as charge-transfer reactions occurring on the external surfaces. A theoretical fracture mechanics approach was incorporated to estimate the crack-tip strain rate, and a void nucleation model was included to account for ductile failure at very negative potentials. In the CEFM, coupling between the Internal and external environments and the need to conserve charge are the key physical and mathematical constraints that determine the rate of crack advance. The model provides rational explanations for the effects of O₂, H₂O₂, H₂, conductivity, stress intensity, and flow velocity on the crack growth rate (CGR) In sensitized type 304 SS In simulated LWR Invessel environments. The CEFM was proposed as the basis of a deterministic method for estimating component lifetimes in LWR heat-transport circuits.

Original language	English
Pages (from-to)	768-785
Number of pages	18
Journal	Material und Organismen
Volume	52
Issue number	10
State	Published - 1996

Keywords

Boiling-water reactors
Coupled-environment fracture model
High-temperature water
Hydrogen peroxide
Irradiation-assisted stress corrosion cracking
Nuclear reactors
Queous solutions
Stress corrosion cracking
Type 304 stainless steel

ASJC Scopus subject areas

General Agricultural and Biological Sciences

Cite this

@article{33447f0b4e0d4a788e0a26d569c7726a,

title = "Theoretical Estimation of Crack Growth Rates in Type 304 Stainless Steel in Boiling-Water Reactor Coolant Environments",

abstract = "The coupled-environment fracture model (CEFM) for intergranular stress corrosion cracking (IGSCC) of sensitized type 304 (UNS S30400) stainless steel (SS) in light-water reactor (LWR) heat-transport circuits was extended by incorporating steel corrosion, hydrogen (H2) oxidation, and hydrogen peroxide (H2O2 reduction In addition to oxygen (O2) reduction as charge-transfer reactions occurring on the external surfaces. A theoretical fracture mechanics approach was incorporated to estimate the crack-tip strain rate, and a void nucleation model was included to account for ductile failure at very negative potentials. In the CEFM, coupling between the Internal and external environments and the need to conserve charge are the key physical and mathematical constraints that determine the rate of crack advance. The model provides rational explanations for the effects of O2, H2O2, H2, conductivity, stress intensity, and flow velocity on the crack growth rate (CGR) In sensitized type 304 SS In simulated LWR Invessel environments. The CEFM was proposed as the basis of a deterministic method for estimating component lifetimes in LWR heat-transport circuits.",

keywords = "Boiling-water reactors, Coupled-environment fracture model, High-temperature water, Hydrogen peroxide, Irradiation-assisted stress corrosion cracking, Nuclear reactors, Queous solutions, Stress corrosion cracking, Type 304 stainless steel",

author = "Macdonald, \{D. D.\} and Lu, \{P. C.\} and M. Urquidi-Macdonald and Yeh, \{T. K.\}",

year = "1996",

language = "English",

volume = "52",

pages = "768--785",

journal = "Material und Organismen",

issn = "0025-5270",

publisher = "Duncker und Humblot GmbH",

number = "10",

}

TY - JOUR

T1 - Theoretical Estimation of Crack Growth Rates in Type 304 Stainless Steel in Boiling-Water Reactor Coolant Environments

AU - Macdonald, D. D.

AU - Lu, P. C.

AU - Urquidi-Macdonald, M.

AU - Yeh, T. K.

PY - 1996

Y1 - 1996

N2 - The coupled-environment fracture model (CEFM) for intergranular stress corrosion cracking (IGSCC) of sensitized type 304 (UNS S30400) stainless steel (SS) in light-water reactor (LWR) heat-transport circuits was extended by incorporating steel corrosion, hydrogen (H2) oxidation, and hydrogen peroxide (H2O2 reduction In addition to oxygen (O2) reduction as charge-transfer reactions occurring on the external surfaces. A theoretical fracture mechanics approach was incorporated to estimate the crack-tip strain rate, and a void nucleation model was included to account for ductile failure at very negative potentials. In the CEFM, coupling between the Internal and external environments and the need to conserve charge are the key physical and mathematical constraints that determine the rate of crack advance. The model provides rational explanations for the effects of O2, H2O2, H2, conductivity, stress intensity, and flow velocity on the crack growth rate (CGR) In sensitized type 304 SS In simulated LWR Invessel environments. The CEFM was proposed as the basis of a deterministic method for estimating component lifetimes in LWR heat-transport circuits.

AB - The coupled-environment fracture model (CEFM) for intergranular stress corrosion cracking (IGSCC) of sensitized type 304 (UNS S30400) stainless steel (SS) in light-water reactor (LWR) heat-transport circuits was extended by incorporating steel corrosion, hydrogen (H2) oxidation, and hydrogen peroxide (H2O2 reduction In addition to oxygen (O2) reduction as charge-transfer reactions occurring on the external surfaces. A theoretical fracture mechanics approach was incorporated to estimate the crack-tip strain rate, and a void nucleation model was included to account for ductile failure at very negative potentials. In the CEFM, coupling between the Internal and external environments and the need to conserve charge are the key physical and mathematical constraints that determine the rate of crack advance. The model provides rational explanations for the effects of O2, H2O2, H2, conductivity, stress intensity, and flow velocity on the crack growth rate (CGR) In sensitized type 304 SS In simulated LWR Invessel environments. The CEFM was proposed as the basis of a deterministic method for estimating component lifetimes in LWR heat-transport circuits.

KW - Boiling-water reactors

KW - Coupled-environment fracture model

KW - High-temperature water

KW - Hydrogen peroxide

KW - Irradiation-assisted stress corrosion cracking

KW - Nuclear reactors

KW - Queous solutions

KW - Stress corrosion cracking

KW - Type 304 stainless steel

UR - https://www.scopus.com/pages/publications/1842533256

M3 - Article

AN - SCOPUS:1842533256

SN - 0025-5270

VL - 52

SP - 768

EP - 785

JO - Material und Organismen

JF - Material und Organismen

IS - 10

ER -

Theoretical Estimation of Crack Growth Rates in Type 304 Stainless Steel in Boiling-Water Reactor Coolant Environments

Abstract

Keywords

ASJC Scopus subject areas

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