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

doi:10.1016/j.corsci.2020.108730

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

^*Corresponding author for this work

Metallurgy and Materials

Research output: Contribution to journal › Article › peer-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 language	English
Article number	108730
Journal	Corrosion Science
Volume	172
DOIs	https://doi.org/10.1016/j.corsci.2020.108730
Publication status	Published - 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

General Chemistry
General Chemical Engineering
General Materials Science

Access to Document

10.1016/j.corsci.2020.108730

Cite this

@article{a8e2867c905e4e7295bc9d006b141217,

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

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.",

keywords = "Austenite, Ferrite, Oxide structure, Stainless steel weld, Thermal ageing",

author = "Junjie Chen and Changheui Jang and Kong, {Byeon Seo} and Qian Xiao and {Obulan Subramanian}, Gokul and Kim, {Ho Sub} and Shin, {Ji Ho}",

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: {\textcopyright} 2020 Elsevier Ltd",

year = "2020",

month = aug,

day = "1",

doi = "10.1016/j.corsci.2020.108730",

language = "English",

volume = "172",

journal = "Corrosion Science",

issn = "0010-938X",

publisher = "Elsevier",

}

TY - JOUR

T1 - Effect of thermal ageing on the corrosion behaviour of austenitic stainless steel welds in the simulated PWR primary water

AU - Chen, Junjie

AU - Jang, Changheui

AU - Kong, Byeon Seo

AU - Xiao, Qian

AU - Obulan Subramanian, Gokul

AU - Kim, Ho Sub

AU - Shin, Ji Ho

N1 - 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

PY - 2020/8/1

Y1 - 2020/8/1

N2 - 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.

AB - 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.

KW - Austenite

KW - Ferrite

KW - Oxide structure

KW - Stainless steel weld

KW - Thermal ageing

UR - http://www.scopus.com/inward/record.url?scp=85085504376&partnerID=8YFLogxK

U2 - 10.1016/j.corsci.2020.108730

DO - 10.1016/j.corsci.2020.108730

M3 - Article

AN - SCOPUS:85085504376

SN - 0010-938X

VL - 172

JO - Corrosion Science

JF - Corrosion Science

M1 - 108730

ER -

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

Abstract

Bibliographical note

Keywords

ASJC Scopus subject areas

Access to Document

Fingerprint

Cite this