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:10.1007/978-3-030-04639-2_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	Minerals, Metals and Materials Series
Publisher	Springer International Publishing
Pages	281-292
Number of pages	12
ISBN (Print)	9783030046385, 9783030046392, 9783319515403, 9783319651354, 9783319728520, 9783319950211
DOIs	https://doi.org/10.1007/978-3-030-04639-2_18
Publication status	Published - 2019
Event	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019 - Boston, United States Duration: 2019 Aug 18 → 2019 Aug 22

Publication series

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

Conference

Conference	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019
Country/Territory	United States
City	Boston
Period	19/8/18 → 19/8/22

Bibliographical note

Funding Information:
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:
© 2019, The Minerals, Metals & Materials Society.

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

10.1007/978-3-030-04639-2_18

Cite this

Yoo, SC, Choi, KJ, Kim, S, Kim, JS, Choi, BH , Kim, YJ, Kim, JS & Kim, JH 2019, Pwscc initiation of alloy 600: effect of long-term thermal aging and triaxial stress. in Minerals, Metals and Materials Series. Minerals, Metals and Materials Series, Springer International Publishing, pp. 281-292, 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019, Boston, United States, 19/8/18. https://doi.org/10.1007/978-3-030-04639-2_18

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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.",

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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: 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} 2019, The Minerals, Metals & Materials Society.; 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019 ; Conference date: 18-08-2019 Through 22-08-2019",

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AU - Yoo, Seung Chang

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AU - Kim, Ji Soo

AU - Choi, Byoung Ho

AU - Kim, Yun Jae

AU - Kim, Jong Sung

AU - Kim, Ji Hyun

N1 - Funding Information: 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: © 2019, The Minerals, Metals & Materials Society.

PY - 2019

Y1 - 2019

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.

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KW - Primary water stress corrosion cracking

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KW - Triaxial stress

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SN - 9783319950211

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BT - Minerals, Metals and Materials Series

PB - Springer International Publishing

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ER -

Pwscc initiation of alloy 600: effect of long-term thermal aging and triaxial stress

Abstract

Publication series

Conference

Bibliographical note

Keywords

ASJC Scopus subject areas

Access to Document

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