The synergy of corrosion and fretting wear process on Inconel 690 in the high temperature high pressure water environment

Zihao Wang; Jian Xu; Jie Li; Long Xin; Yonghao Lu; Tetsuo Shoji; Yoichi Takeda; Yuichi Otsuka; Yoshiharu Mutoh

doi:10.1016/j.jnucmat.2018.02.021

The synergy of corrosion and fretting wear process on Inconel 690 in the high temperature high pressure water environment

Zihao Wang, Jian Xu, Jie Li, Long Xin, Yonghao Lu, Tetsuo Shoji, Yoichi Takeda, Yuichi Otsuka, Yoshiharu Mutoh

Research output: Contribution to journal › Article › peer-review

4 Citations (Scopus)

Abstract

The synergistic effect of corrosion and fretting process of the steam generator (SG) tube was investigated by using a self-designed high temperature test rig in this paper. The experiments were performed at 100°C, 200°C and 288°C, respectively. The fretting corrosion damage was studied by optical microscopy (OM), scanning electron microscope (SEM), energy dispersive spectrometer (EDS), Raman spectroscopy and auger electron spectroscopy (AES). The results demonstrated that the corrosion process in high temperature high pressure (HTHP) water environment had a distinct interaction with the fretting process of Inconel 690. With the increment of temperature, the damage mechanism changed from a simple mechanical process to a mechanochemical process.

Original language	English
Pages (from-to)	255-262
Number of pages	8
Journal	Journal of Nuclear Materials
Volume	502
DOIs	https://doi.org/10.1016/j.jnucmat.2018.02.021
Publication status	Published - 2018 Apr 15

Keywords

Fretting
High temperature corrosion
Mechanochemistry
PWR
Steam generator

ASJC Scopus subject areas

Nuclear and High Energy Physics
Nuclear Energy and Engineering
Materials Science(all)

Access to Document

10.1016/j.jnucmat.2018.02.021

Fingerprint Dive into the research topics of 'The synergy of corrosion and fretting wear process on Inconel 690 in the high temperature high pressure water environment'. Together they form a unique fingerprint.

Cite this

The synergy of corrosion and fretting wear process on Inconel 690 in the high temperature high pressure water environment. / Wang, Zihao; Xu, Jian; Li, Jie; Xin, Long; Lu, Yonghao; Shoji, Tetsuo; Takeda, Yoichi; Otsuka, Yuichi; Mutoh, Yoshiharu.

In: Journal of Nuclear Materials, Vol. 502, 15.04.2018, p. 255-262.

Research output: Contribution to journal › Article › peer-review

@article{6de3d8cd29a145178c5f07960bd74bef,

title = "The synergy of corrosion and fretting wear process on Inconel 690 in the high temperature high pressure water environment",

abstract = "The synergistic effect of corrosion and fretting process of the steam generator (SG) tube was investigated by using a self-designed high temperature test rig in this paper. The experiments were performed at 100°C, 200°C and 288°C, respectively. The fretting corrosion damage was studied by optical microscopy (OM), scanning electron microscope (SEM), energy dispersive spectrometer (EDS), Raman spectroscopy and auger electron spectroscopy (AES). The results demonstrated that the corrosion process in high temperature high pressure (HTHP) water environment had a distinct interaction with the fretting process of Inconel 690. With the increment of temperature, the damage mechanism changed from a simple mechanical process to a mechanochemical process.",

keywords = "Fretting, High temperature corrosion, Mechanochemistry, PWR, Steam generator",

author = "Zihao Wang and Jian Xu and Jie Li and Long Xin and Yonghao Lu and Tetsuo Shoji and Yoichi Takeda and Yuichi Otsuka and Yoshiharu Mutoh",

year = "2018",

month = apr,

day = "15",

doi = "10.1016/j.jnucmat.2018.02.021",

language = "English",

volume = "502",

pages = "255--262",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier",

}

TY - JOUR

T1 - The synergy of corrosion and fretting wear process on Inconel 690 in the high temperature high pressure water environment

AU - Wang, Zihao

AU - Xu, Jian

AU - Li, Jie

AU - Xin, Long

AU - Lu, Yonghao

AU - Shoji, Tetsuo

AU - Takeda, Yoichi

AU - Otsuka, Yuichi

AU - Mutoh, Yoshiharu

PY - 2018/4/15

Y1 - 2018/4/15

N2 - The synergistic effect of corrosion and fretting process of the steam generator (SG) tube was investigated by using a self-designed high temperature test rig in this paper. The experiments were performed at 100°C, 200°C and 288°C, respectively. The fretting corrosion damage was studied by optical microscopy (OM), scanning electron microscope (SEM), energy dispersive spectrometer (EDS), Raman spectroscopy and auger electron spectroscopy (AES). The results demonstrated that the corrosion process in high temperature high pressure (HTHP) water environment had a distinct interaction with the fretting process of Inconel 690. With the increment of temperature, the damage mechanism changed from a simple mechanical process to a mechanochemical process.

AB - The synergistic effect of corrosion and fretting process of the steam generator (SG) tube was investigated by using a self-designed high temperature test rig in this paper. The experiments were performed at 100°C, 200°C and 288°C, respectively. The fretting corrosion damage was studied by optical microscopy (OM), scanning electron microscope (SEM), energy dispersive spectrometer (EDS), Raman spectroscopy and auger electron spectroscopy (AES). The results demonstrated that the corrosion process in high temperature high pressure (HTHP) water environment had a distinct interaction with the fretting process of Inconel 690. With the increment of temperature, the damage mechanism changed from a simple mechanical process to a mechanochemical process.

KW - Fretting

KW - High temperature corrosion

KW - Mechanochemistry

KW - PWR

KW - Steam generator

UR - http://www.scopus.com/inward/record.url?scp=85042382443&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=85042382443&partnerID=8YFLogxK

U2 - 10.1016/j.jnucmat.2018.02.021

DO - 10.1016/j.jnucmat.2018.02.021

M3 - Article

AN - SCOPUS:85042382443

VL - 502

SP - 255

EP - 262

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

ER -