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 proceedingConference 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 languageEnglish
Title of host publicationProceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
PublisherSpringer International Publishing
Pages281-292
Number of pages12
ISBN (Print)9783319672434
DOIs
Publication statusPublished - 2018 Jan 1
Event18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017 - Portland, United States
Duration: 2017 Aug 132017 Aug 17

Publication series

NameMinerals, Metals and Materials Series
VolumePart F9
ISSN (Print)2367-1181
ISSN (Electronic)2367-1696

Other

Other18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017
CountryUnited States
CityPortland
Period17/8/1317/8/17

Fingerprint

Thermal aging
Crack initiation
Corrosion
Water
Nickel
Nuclear power plants
Gages
Strain rate
Heat treatment

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

Cite this

Yoo, S. C., Choi, K. J., Kim, S., Kim, J. S., Choi, B-H., Kim, Y-J., ... Kim, J. H. (2018). PWSCC initiation of alloy 600: Effect of long-term thermal aging and triaxial stress. In 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; Kim, Ji Soo; Choi, Byoung-Ho; Kim, Yun-Jae; Kim, Jong Sung; Kim, Ji Hyun.

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; Vol. Part F9).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Yoo, SC, Choi, KJ, Kim, S, Kim, JS, Choi, B-H, Kim, Y-J, Kim, JS & Kim, JH 2018, PWSCC initiation of alloy 600: Effect of long-term thermal aging and triaxial stress. in 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 B-H, Kim Y-J et al. PWSCC initiation of alloy 600: Effect of long-term thermal aging and triaxial stress. In 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). https://doi.org/10.1007/978-3-319-67244-1_18
Yoo, Seung Chang ; Choi, Kyoung Joon ; Kim, Seunghyun ; Kim, Ji Soo ; Choi, Byoung-Ho ; Kim, Yun-Jae ; Kim, Jong Sung ; Kim, Ji Hyun. / 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. Springer International Publishing, 2018. pp. 281-292 (Minerals, Metals and Materials Series).
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