PWSCC initiation of alloy 600: Effect of long-term thermal aging and triaxial stress

Seung Chang Yoo; Kyoung Joon Choi; Seunghyun Kim; Ji Soo Kim; Byoung Ho Choi; Yun Jae Kim; Jong Sung Kim; Ji Hyun Kim

doi:10.1007/978-3-319-67244-1_18

PWSCC initiation of alloy 600: Effect of long-term thermal aging and triaxial stress

Seung Chang Yoo, Kyoung Joon Choi, Seunghyun Kim, Ji Soo Kim, Byoung Ho Choi, Yun Jae Kim, Jong Sung Kim, Ji Hyun Kim

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

Abstract

Thermally aged nickel based Alloy 600 was investigated to evaluate the effects of long-term thermal aging and triaxial stress on primary water stress corrosion crack initiation behavior. Long-term thermal aging was simulated by heat treatment at 400, °C, a temperature that does not cause excessive formation of second phases that cannot form in nuclear power plant service conditions. Triaxial stress was applied by a round notch in the gauge length of some test specimen; other specimens were smooth. Slow strain rate tests (SSRT) monitored by the direct current potential drop method were conducted to evaluate stress corrosion crack initiation susceptibility of the thermally aged specimens in the primary water environment. For smooth specimens (which experience uniaxial stress), the susceptibility of those thermally aged for the equivalent of 10-years was the highest, while the susceptibility of the as-received specimens was the lowest. However, for the notched specimens (which experience triaxial stress), the specimens thermally aged for the equivalent of 20-years showed the highest susceptibility, while the as-received specimens showed the lowest.

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	Denise Paraventi, Michael Wright, John H. Jackson
Publisher	Springer International Publishing
Pages	281-292
Number of pages	12
ISBN (Print)	9783319672434
DOIs	https://doi.org/10.1007/978-3-319-67244-1_18
Publication status	Published - 2018
Event	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017 - Portland, United States Duration: 2017 Aug 13 → 2017 Aug 17

Publication series

Name	Minerals, Metals and Materials Series
Volume	Part F9
ISSN (Print)	2367-1181
ISSN (Electronic)	2367-1696

Other

Other	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017
Country/Territory	United States
City	Portland
Period	17/8/13 → 17/8/17

Bibliographical note

Funding Information:
Acknowledgements This work was financially supported by the Nuclear Safety Research Program through the Korea Foundation of Nuclear Safety (KOFONS), granted financial resource from the Nuclear Safety and Security Commission (NSSC), Republic of Korea (No. 1403006) and by the Human Resources Development of the Korea Institute of Energy Technology Evaluation and Planning (KETEP) grant funded by the Korea Government Ministry of Trade Industry and Energy (MOTIE) (No. 20174030201430).

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

Keywords

Nickel based alloy
Primary water stress corrosion cracking
Thermal aging
Triaxial stress

ASJC Scopus subject areas

Electronic, Optical and Magnetic Materials
Energy Engineering and Power Technology
Mechanics of Materials
Metals and Alloys
Materials Chemistry

Access to Document

10.1007/978-3-319-67244-1_18

Cite this

Yoo, S. C., Choi, K. J., Kim, S., Kim, J. S., Choi, B. H., Kim, Y. J., Kim, J. S., & Kim, J. H. (2018). PWSCC initiation of alloy 600: Effect of long-term thermal aging and triaxial stress. In D. Paraventi, M. Wright, & J. H. Jackson (Eds.), Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors (pp. 281-292). (Minerals, Metals and Materials Series; Vol. Part F9). Springer International Publishing. https://doi.org/10.1007/978-3-319-67244-1_18

PWSCC initiation of alloy 600: Effect of long-term thermal aging and triaxial stress. / Yoo, Seung Chang; Choi, Kyoung Joon; Kim, Seunghyun et al.
Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. ed. / Denise Paraventi; Michael Wright; John H. Jackson. Springer International Publishing, 2018. p. 281-292 (Minerals, Metals and Materials Series; Vol. Part F9).

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

Yoo, SC, Choi, KJ, Kim, S, Kim, JS, Choi, BH , Kim, YJ, Kim, JS & Kim, JH 2018, PWSCC initiation of alloy 600: Effect of long-term thermal aging and triaxial stress. in D Paraventi, M Wright & 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 F9, Springer International Publishing, pp. 281-292, 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017, Portland, United States, 17/8/13. https://doi.org/10.1007/978-3-319-67244-1_18

Yoo SC, Choi KJ, Kim S, Kim JS, Choi BH , Kim YJ et al. PWSCC initiation of alloy 600: Effect of long-term thermal aging and triaxial stress. In Paraventi D, Wright M, 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. 281-292. (Minerals, Metals and Materials Series). doi: 10.1007/978-3-319-67244-1_18

Yoo, Seung Chang ; Choi, Kyoung Joon ; Kim, Seunghyun et al. / PWSCC initiation of alloy 600 : Effect of long-term thermal aging and triaxial stress. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. editor / Denise Paraventi ; Michael Wright ; John H. Jackson. Springer International Publishing, 2018. pp. 281-292 (Minerals, Metals and Materials Series).

@inproceedings{80da0c08a50d4d81b6411a7d311e2a72,

title = "PWSCC initiation of alloy 600: Effect of long-term thermal aging and triaxial stress",

abstract = "Thermally aged nickel based Alloy 600 was investigated to evaluate the effects of long-term thermal aging and triaxial stress on primary water stress corrosion crack initiation behavior. Long-term thermal aging was simulated by heat treatment at 400, °C, a temperature that does not cause excessive formation of second phases that cannot form in nuclear power plant service conditions. Triaxial stress was applied by a round notch in the gauge length of some test specimen; other specimens were smooth. Slow strain rate tests (SSRT) monitored by the direct current potential drop method were conducted to evaluate stress corrosion crack initiation susceptibility of the thermally aged specimens in the primary water environment. For smooth specimens (which experience uniaxial stress), the susceptibility of those thermally aged for the equivalent of 10-years was the highest, while the susceptibility of the as-received specimens was the lowest. However, for the notched specimens (which experience triaxial stress), the specimens thermally aged for the equivalent of 20-years showed the highest susceptibility, while the as-received specimens showed the lowest.",

keywords = "Nickel based alloy, Primary water stress corrosion cracking, Thermal aging, Triaxial stress",

author = "Yoo, {Seung Chang} and Choi, {Kyoung Joon} and Seunghyun Kim and Kim, {Ji Soo} and Choi, {Byoung Ho} and Kim, {Yun Jae} and Kim, {Jong Sung} and Kim, {Ji Hyun}",

note = "Funding Information: Acknowledgements This work was financially supported by the Nuclear Safety Research Program through the Korea Foundation of Nuclear Safety (KOFONS), granted financial resource from the Nuclear Safety and Security Commission (NSSC), Republic of Korea (No. 1403006) and by the Human Resources Development of the Korea Institute of Energy Technology Evaluation and Planning (KETEP) grant funded by the Korea Government Ministry of Trade Industry and Energy (MOTIE) (No. 20174030201430). 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 = "10.1007/978-3-319-67244-1_18",

language = "English",

isbn = "9783319672434",

series = "Minerals, Metals and Materials Series",

publisher = "Springer International Publishing",

pages = "281--292",

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

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

}

TY - GEN

T1 - PWSCC initiation of alloy 600

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

AU - Yoo, Seung Chang

AU - Choi, Kyoung Joon

AU - Kim, Seunghyun

AU - Kim, Ji Soo

AU - Choi, Byoung Ho

AU - Kim, Yun Jae

AU - Kim, Jong Sung

AU - Kim, Ji Hyun

N1 - Funding Information: Acknowledgements This work was financially supported by the Nuclear Safety Research Program through the Korea Foundation of Nuclear Safety (KOFONS), granted financial resource from the Nuclear Safety and Security Commission (NSSC), Republic of Korea (No. 1403006) and by the Human Resources Development of the Korea Institute of Energy Technology Evaluation and Planning (KETEP) grant funded by the Korea Government Ministry of Trade Industry and Energy (MOTIE) (No. 20174030201430). Publisher Copyright: © The Minerals, Metals & Materials Society 2018.

PY - 2018

Y1 - 2018

N2 - Thermally aged nickel based Alloy 600 was investigated to evaluate the effects of long-term thermal aging and triaxial stress on primary water stress corrosion crack initiation behavior. Long-term thermal aging was simulated by heat treatment at 400, °C, a temperature that does not cause excessive formation of second phases that cannot form in nuclear power plant service conditions. Triaxial stress was applied by a round notch in the gauge length of some test specimen; other specimens were smooth. Slow strain rate tests (SSRT) monitored by the direct current potential drop method were conducted to evaluate stress corrosion crack initiation susceptibility of the thermally aged specimens in the primary water environment. For smooth specimens (which experience uniaxial stress), the susceptibility of those thermally aged for the equivalent of 10-years was the highest, while the susceptibility of the as-received specimens was the lowest. However, for the notched specimens (which experience triaxial stress), the specimens thermally aged for the equivalent of 20-years showed the highest susceptibility, while the as-received specimens showed the lowest.

AB - Thermally aged nickel based Alloy 600 was investigated to evaluate the effects of long-term thermal aging and triaxial stress on primary water stress corrosion crack initiation behavior. Long-term thermal aging was simulated by heat treatment at 400, °C, a temperature that does not cause excessive formation of second phases that cannot form in nuclear power plant service conditions. Triaxial stress was applied by a round notch in the gauge length of some test specimen; other specimens were smooth. Slow strain rate tests (SSRT) monitored by the direct current potential drop method were conducted to evaluate stress corrosion crack initiation susceptibility of the thermally aged specimens in the primary water environment. For smooth specimens (which experience uniaxial stress), the susceptibility of those thermally aged for the equivalent of 10-years was the highest, while the susceptibility of the as-received specimens was the lowest. However, for the notched specimens (which experience triaxial stress), the specimens thermally aged for the equivalent of 20-years showed the highest susceptibility, while the as-received specimens showed the lowest.

KW - Nickel based alloy

KW - Primary water stress corrosion cracking

KW - Thermal aging

KW - Triaxial stress

UR - http://www.scopus.com/inward/record.url?scp=85042497439&partnerID=8YFLogxK

U2 - 10.1007/978-3-319-67244-1_18

DO - 10.1007/978-3-319-67244-1_18

M3 - Conference contribution

AN - SCOPUS:85042497439

SN - 9783319672434

T3 - Minerals, Metals and Materials Series

SP - 281

EP - 292

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

A2 - Paraventi, Denise

A2 - Wright, Michael

A2 - Jackson, John H.

PB - Springer International Publishing

Y2 - 13 August 2017 through 17 August 2017

ER -

PWSCC initiation of alloy 600: Effect of long-term thermal aging and triaxial stress

Abstract

Publication series

Other

Bibliographical note

Keywords

ASJC Scopus subject areas

Access to Document

Other files and links

Fingerprint

Cite this