Stress corrosion crack growth behavior of cold worked austenitic stainless steel in high temperature water

M. Tsubota; Y. Katayama; Yoshiaki Saito

Stress corrosion crack growth behavior of cold worked austenitic stainless steel in high temperature water

M. Tsubota, Y. Katayama, Yoshiaki Saito

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

Abstract

Crack propagation testing of type 316L stainless steel, with different hardness levels, in high temperature water has been performed, and the relationship between SCC growth rate (da/dt) and hardness (Hv) discussed. Intergranular crack propagation was observed in both solution treated material and cold worked materials. Highly cold worked material showed a higher crack propagation rate. Using the strain distribution near the crack tip and the SCC susceptible plastic zone size, where the hardness was higher than the critical Vickers hardness for SCC susceptibility (Hvc), the crack propagation rate for low carbon stainless steel, under the fixed environment, could be described as da/dt=A·K²/(Hvc-Hv₀)², where K is the stress intensity factor, Hvc is the critical hardness for SCC (defined as a Vickers hardness of 300), and HV₀ is the Vickers hardness of the base material.

Original language	English
Title of host publication	Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Pages	109-115
Number of pages	7
Publication status	Published - 2005 Dec 1
Externally published	Yes
Event	12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors - Salt Lake City, UT, United States Duration: 2005 Aug 14 → 2005 Aug 18

Other

Other	12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Country/Territory	United States
City	Salt Lake City, UT
Period	05/8/14 → 05/8/18

Keywords

BWR
Crack Growth Rate
Hardness
Stainless Steel
Stress Corrosion Cracking

ASJC Scopus subject areas

Engineering(all)

Cite this

Stress corrosion crack growth behavior of cold worked austenitic stainless steel in high temperature water. / Tsubota, M.; Katayama, Y.; Saito, Yoshiaki.

Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. 2005. p. 109-115.

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

Tsubota, M, Katayama, Y & Saito, Y 2005, Stress corrosion crack growth behavior of cold worked austenitic stainless steel in high temperature water. in Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. pp. 109-115, 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Salt Lake City, UT, United States, 05/8/14.

@inproceedings{d290cf48336843ffb83073e75e3ae4fa,

title = "Stress corrosion crack growth behavior of cold worked austenitic stainless steel in high temperature water",

abstract = "Crack propagation testing of type 316L stainless steel, with different hardness levels, in high temperature water has been performed, and the relationship between SCC growth rate (da/dt) and hardness (Hv) discussed. Intergranular crack propagation was observed in both solution treated material and cold worked materials. Highly cold worked material showed a higher crack propagation rate. Using the strain distribution near the crack tip and the SCC susceptible plastic zone size, where the hardness was higher than the critical Vickers hardness for SCC susceptibility (Hvc), the crack propagation rate for low carbon stainless steel, under the fixed environment, could be described as da/dt=A·K2/(Hvc-Hv0)2, where K is the stress intensity factor, Hvc is the critical hardness for SCC (defined as a Vickers hardness of 300), and HV0 is the Vickers hardness of the base material.",

keywords = "BWR, Crack Growth Rate, Hardness, Stainless Steel, Stress Corrosion Cracking",

author = "M. Tsubota and Y. Katayama and Yoshiaki Saito",

year = "2005",

month = dec,

day = "1",

language = "English",

isbn = "9780873395953",

pages = "109--115",

booktitle = "Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors",

note = "12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ; Conference date: 14-08-2005 Through 18-08-2005",

}

TY - GEN

T1 - Stress corrosion crack growth behavior of cold worked austenitic stainless steel in high temperature water

AU - Tsubota, M.

AU - Katayama, Y.

AU - Saito, Yoshiaki

PY - 2005/12/1

Y1 - 2005/12/1

N2 - Crack propagation testing of type 316L stainless steel, with different hardness levels, in high temperature water has been performed, and the relationship between SCC growth rate (da/dt) and hardness (Hv) discussed. Intergranular crack propagation was observed in both solution treated material and cold worked materials. Highly cold worked material showed a higher crack propagation rate. Using the strain distribution near the crack tip and the SCC susceptible plastic zone size, where the hardness was higher than the critical Vickers hardness for SCC susceptibility (Hvc), the crack propagation rate for low carbon stainless steel, under the fixed environment, could be described as da/dt=A·K2/(Hvc-Hv0)2, where K is the stress intensity factor, Hvc is the critical hardness for SCC (defined as a Vickers hardness of 300), and HV0 is the Vickers hardness of the base material.

AB - Crack propagation testing of type 316L stainless steel, with different hardness levels, in high temperature water has been performed, and the relationship between SCC growth rate (da/dt) and hardness (Hv) discussed. Intergranular crack propagation was observed in both solution treated material and cold worked materials. Highly cold worked material showed a higher crack propagation rate. Using the strain distribution near the crack tip and the SCC susceptible plastic zone size, where the hardness was higher than the critical Vickers hardness for SCC susceptibility (Hvc), the crack propagation rate for low carbon stainless steel, under the fixed environment, could be described as da/dt=A·K2/(Hvc-Hv0)2, where K is the stress intensity factor, Hvc is the critical hardness for SCC (defined as a Vickers hardness of 300), and HV0 is the Vickers hardness of the base material.

KW - BWR

KW - Crack Growth Rate

KW - Hardness

KW - Stainless Steel

KW - Stress Corrosion Cracking

UR - http://www.scopus.com/inward/record.url?scp=33745198669&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=33745198669&partnerID=8YFLogxK

M3 - Conference contribution

AN - SCOPUS:33745198669

SN - 9780873395953

SP - 109

EP - 115

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

T2 - 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors

Y2 - 14 August 2005 through 18 August 2005

ER -

Stress corrosion crack growth behavior of cold worked austenitic stainless steel in high temperature water

Abstract

Other

Keywords

ASJC Scopus subject areas

Other files and links

Fingerprint

Cite this