Plastic deformation processes accompanying stress corrosion crack propagation in irradiated austenitic steels

M. N. Gussev; G. S. Was; J. T. Busby; K. J. Leonard

doi:10.1007/978-3-319-68454-3_78

Plastic deformation processes accompanying stress corrosion crack propagation in irradiated austenitic steels

M. N. Gussev, G. S. Was, J. T. Busby, K. J. Leonard

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

Abstract

During stress corrosion crack propagation, stress values in the crack tip vicinity often exceed material yield stress limit. Plastic deformation processes may accompany and influence cracking. Here, stress corrosion crack propagation and deformation mechanisms were investigated using EBSD analysis. The investigated material was 304L Ti-enriched austenitic stainless steel irradiated to 10.4 dpa at 320°C in the BOR-60 fast reactor. Crack growth tests were conducted in a simulated Normal Water Chemistry (NWC) environment in the temperature range 288–320 °C using compact tension specimens. By analyzing crack trajectory and grain structure in the crack vicinity, it was established that grain orientation with respect to the acting stress direction was not a key factor controlling crack propagation. No crystallographic orientation susceptible to cracking was identified. Also, EBSD analysis revealed strong inhomogeneity in plastic strain distribution along the crack path. Most crack-adjacent grains remained virtually strain-free whereas few grains experienced strong plastic strain. These areas were presumed to be “plastic bridges” or “ductile ligaments.”.

Original language	English
Title of host publication	Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
Editors	Michael Wright, Denise Paraventi, John H. Jackson
Publisher	Springer International Publishing
Pages	1073-1084
Number of pages	12
ISBN (Print)	9783319684536
DOIs	https://doi.org/10.1007/978-3-319-68454-3_78
State	Published - 2018
Event	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017 - Portland, United States Duration: Aug 13 2017 → Aug 17 2017

Publication series

Name	Minerals, Metals and Materials Series
Volume	Part F11
ISSN (Print)	2367-1181
ISSN (Electronic)	2367-1696

Conference

Conference	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017
Country/Territory	United States
City	Portland
Period	08/13/17 → 08/17/17

Funding

This manuscript has been authored by UT-Battelle, LLC, under Contract No. DE-AC05-00OR22725 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/ downloads/doe-public-access-plan).

Keywords

Austenitic steel
Deformation localization
EBSD
Neutron irradiation
Stress corrosion cracking

Access to Document

10.1007/978-3-319-68454-3_78

Cite this

Gussev, M. N., Was, G. S., Busby, J. T., & Leonard, K. J. (2018). Plastic deformation processes accompanying stress corrosion crack propagation in irradiated austenitic steels. In M. Wright, D. Paraventi, & J. H. Jackson (Eds.), Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors (pp. 1073-1084). (Minerals, Metals and Materials Series; Vol. Part F11). Springer International Publishing. https://doi.org/10.1007/978-3-319-68454-3_78

Gussev, M. N. ; Was, G. S. ; Busby, J. T. et al. / Plastic deformation processes accompanying stress corrosion crack propagation in irradiated austenitic steels. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. editor / Michael Wright ; Denise Paraventi ; John H. Jackson. Springer International Publishing, 2018. pp. 1073-1084 (Minerals, Metals and Materials Series).

@inproceedings{b071f15b486a40359ca26e8e8ab315a1,

title = "Plastic deformation processes accompanying stress corrosion crack propagation in irradiated austenitic steels",

abstract = "During stress corrosion crack propagation, stress values in the crack tip vicinity often exceed material yield stress limit. Plastic deformation processes may accompany and influence cracking. Here, stress corrosion crack propagation and deformation mechanisms were investigated using EBSD analysis. The investigated material was 304L Ti-enriched austenitic stainless steel irradiated to 10.4 dpa at 320°C in the BOR-60 fast reactor. Crack growth tests were conducted in a simulated Normal Water Chemistry (NWC) environment in the temperature range 288–320 °C using compact tension specimens. By analyzing crack trajectory and grain structure in the crack vicinity, it was established that grain orientation with respect to the acting stress direction was not a key factor controlling crack propagation. No crystallographic orientation susceptible to cracking was identified. Also, EBSD analysis revealed strong inhomogeneity in plastic strain distribution along the crack path. Most crack-adjacent grains remained virtually strain-free whereas few grains experienced strong plastic strain. These areas were presumed to be “plastic bridges” or “ductile ligaments.”.",

keywords = "Austenitic steel, Deformation localization, EBSD, Neutron irradiation, Stress corrosion cracking",

author = "Gussev, {M. N.} and Was, {G. S.} and Busby, {J. T.} and Leonard, {K. J.}",

note = "Publisher Copyright: {\textcopyright} The Minerals, Metals & Materials Society 2018.; 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017 ; Conference date: 13-08-2017 Through 17-08-2017",

year = "2018",

doi = "10.1007/978-3-319-68454-3_78",

language = "English",

isbn = "9783319684536",

series = "Minerals, Metals and Materials Series",

publisher = "Springer International Publishing",

pages = "1073--1084",

editor = "Michael Wright and Denise Paraventi and Jackson, {John H.}",

booktitle = "Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors",

}

Gussev, MN, Was, GS, Busby, JT & Leonard, KJ 2018, Plastic deformation processes accompanying stress corrosion crack propagation in irradiated austenitic steels. in M Wright, D Paraventi & JH Jackson (eds), Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Minerals, Metals and Materials Series, vol. Part F11, Springer International Publishing, pp. 1073-1084, 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017, Portland, United States, 08/13/17. https://doi.org/10.1007/978-3-319-68454-3_78

Plastic deformation processes accompanying stress corrosion crack propagation in irradiated austenitic steels. / Gussev, M. N.; Was, G. S.; Busby, J. T. et al.
Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. ed. / Michael Wright; Denise Paraventi; John H. Jackson. Springer International Publishing, 2018. p. 1073-1084 (Minerals, Metals and Materials Series; Vol. Part F11).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

TY - GEN

T1 - Plastic deformation processes accompanying stress corrosion crack propagation in irradiated austenitic steels

AU - Gussev, M. N.

AU - Was, G. S.

AU - Busby, J. T.

AU - Leonard, K. J.

N1 - Publisher Copyright: © The Minerals, Metals & Materials Society 2018.

PY - 2018

Y1 - 2018

N2 - During stress corrosion crack propagation, stress values in the crack tip vicinity often exceed material yield stress limit. Plastic deformation processes may accompany and influence cracking. Here, stress corrosion crack propagation and deformation mechanisms were investigated using EBSD analysis. The investigated material was 304L Ti-enriched austenitic stainless steel irradiated to 10.4 dpa at 320°C in the BOR-60 fast reactor. Crack growth tests were conducted in a simulated Normal Water Chemistry (NWC) environment in the temperature range 288–320 °C using compact tension specimens. By analyzing crack trajectory and grain structure in the crack vicinity, it was established that grain orientation with respect to the acting stress direction was not a key factor controlling crack propagation. No crystallographic orientation susceptible to cracking was identified. Also, EBSD analysis revealed strong inhomogeneity in plastic strain distribution along the crack path. Most crack-adjacent grains remained virtually strain-free whereas few grains experienced strong plastic strain. These areas were presumed to be “plastic bridges” or “ductile ligaments.”.

AB - During stress corrosion crack propagation, stress values in the crack tip vicinity often exceed material yield stress limit. Plastic deformation processes may accompany and influence cracking. Here, stress corrosion crack propagation and deformation mechanisms were investigated using EBSD analysis. The investigated material was 304L Ti-enriched austenitic stainless steel irradiated to 10.4 dpa at 320°C in the BOR-60 fast reactor. Crack growth tests were conducted in a simulated Normal Water Chemistry (NWC) environment in the temperature range 288–320 °C using compact tension specimens. By analyzing crack trajectory and grain structure in the crack vicinity, it was established that grain orientation with respect to the acting stress direction was not a key factor controlling crack propagation. No crystallographic orientation susceptible to cracking was identified. Also, EBSD analysis revealed strong inhomogeneity in plastic strain distribution along the crack path. Most crack-adjacent grains remained virtually strain-free whereas few grains experienced strong plastic strain. These areas were presumed to be “plastic bridges” or “ductile ligaments.”.

KW - Austenitic steel

KW - Deformation localization

KW - EBSD

KW - Neutron irradiation

KW - Stress corrosion cracking

UR - http://www.scopus.com/inward/record.url?scp=85042400278&partnerID=8YFLogxK

U2 - 10.1007/978-3-319-68454-3_78

DO - 10.1007/978-3-319-68454-3_78

M3 - Conference contribution

AN - SCOPUS:85042400278

SN - 9783319684536

T3 - Minerals, Metals and Materials Series

SP - 1073

EP - 1084

BT - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors

A2 - Wright, Michael

A2 - Paraventi, Denise

A2 - Jackson, John H.

PB - Springer International Publishing

T2 - 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017

Y2 - 13 August 2017 through 17 August 2017

ER -

Gussev MN, Was GS, Busby JT, Leonard KJ. Plastic deformation processes accompanying stress corrosion crack propagation in irradiated austenitic steels. In Wright M, Paraventi D, Jackson JH, editors, Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Springer International Publishing. 2018. p. 1073-1084. (Minerals, Metals and Materials Series). doi: 10.1007/978-3-319-68454-3_78

Plastic deformation processes accompanying stress corrosion crack propagation in irradiated austenitic steels

Abstract

Publication series

Conference

Funding

Keywords

Access to Document

Other files and links

Fingerprint

Cite this