PWSCC Initiation of Alloy 600: Effect of Long-Term Thermal Aging and Triaxial Stress

  • Seung Chang YooEmail author
  • Kyoung Joon Choi
  • Seunghyun Kim
  • Ji-Soo Kim
  • Byoung Ho Choi
  • Yun-Jae Kim
  • Jong-Sung Kim
  • Ji Hyun Kim
Conference paper
Part of the The Minerals, Metals & Materials Series book series (MMMS)


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.


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



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).


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Copyright information

© The Minerals, Metals & Materials Society 2019

Authors and Affiliations

  • Seung Chang Yoo
    • 1
    Email author
  • Kyoung Joon Choi
    • 1
  • Seunghyun Kim
    • 1
  • Ji-Soo Kim
    • 2
  • Byoung Ho Choi
    • 2
  • Yun-Jae Kim
    • 2
  • Jong-Sung Kim
    • 3
  • Ji Hyun Kim
    • 1
  1. 1.Department of Nuclear Engineering, School of Mechanical, Aerospace and Nuclear EngineeringUlsan National Institute of Science and Technology (UNIST)Eonyang-Eup, Ulju-Gun, UlsanRepublic of Korea
  2. 2.Department of Mechanical EngineeringKorea UniversityEonyang-Eup, Ulju-Gun, UlsanRepublic of Korea
  3. 3.Department of Nuclear EngineeringSejong UniversityEonyang-Eup, Ulju-Gun, UlsanRepublic of Korea

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