Effect of thermal ageing on the corrosion behaviour of austenitic stainless steel welds in the simulated PWR primary water

Junjie Chen, Changheui Jang, Byeon Seo Kong, Qian Xiao, Gokul Obulan Subramanian, Ho Sub Kim, Ji Ho Shin

Research output: Contribution to journalArticlepeer-review

9 Citations (Scopus)

Abstract

The corrosion behaviour of as-welded and thermally aged ER316L in simulated pressurised water reactor (PWR) primary water was studied. Significant spinodal decomposition without G-phase was observed after thermal ageing. Thermal ageing does not change the duplex oxide film formation mechanism on ER316L. Slightly higher Fe and Ni concentrations are in the external oxide particles of thermally aged ER316L. More Ni enrichment is in ferrite of as-welded ER316L beneath the ferrite/inner oxide layer interface. Oxide films of thermally aged ER316L show higher point defect densities and lower EIS resistances.

Original languageEnglish
Article number108730
JournalCorrosion Science
Volume172
DOIs
Publication statusPublished - 1 Aug 2020

Bibliographical note

Funding Information:
This study was supported by the Korea Hydro and Nuclear Power Co., Ltd . as the Evaluation of Structural Integrity of Reactor Vessel Internals Considering Damage and Seismic Load Project ( L18S054000 ) and the National Research Foundation of Korea (NRF) grant ( 2019M2D2A2050927 ) of the MSIT of the Republic of Korea. Financial support for five of the authors was provided by the BK-Plus Program of the MSIT of the Republic of Korea. The help from the KAIST Analysis Center for Research Advancement is acknowledged.

Funding Information:
This study was supported by the Korea Hydro and Nuclear Power Co. Ltd. as the Evaluation of Structural Integrity of Reactor Vessel Internals Considering Damage and Seismic Load Project (L18S054000) and the National Research Foundation of Korea (NRF) grant (2019M2D2A2050927) of the MSIT of the Republic of Korea. Financial support for five of the authors was provided by the BK-Plus Program of the MSIT of the Republic of Korea. The help from the KAIST Analysis Center for Research Advancement is acknowledged.

Publisher Copyright:
© 2020 Elsevier Ltd

Keywords

  • Austenite
  • Ferrite
  • Oxide structure
  • Stainless steel weld
  • Thermal ageing

ASJC Scopus subject areas

  • Chemistry(all)
  • Chemical Engineering(all)
  • Materials Science(all)

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