Effects of Matrix and Dendrite Boundary Composition on Stress Corrosion Cracking Performance of Alloy 52M Buttering Layer in Simulated Pressurized Water Reactor Primary Water

被引：2

作者：

Ma, Jiarong ^{[1
,2
]}

Xiong, Qi ^{[1
,2
]}

Xu, Xinhe ^{[1
,2
]}

Cui, Tongming ^{[1
,2
]}

Lu, Zhanpeng ^{[1
,2
]}

Shoji, Tetsuo ^{[3
]}

机构：

[1] Shanghai Univ, Inst Mat, Sch Mat Sci & Engn, Shanghai 200072, Peoples R China

[2] Shanghai Univ, State Key Lab Adv Special Steels, Shanghai 200072, Peoples R China

[3] Tohoku Univ, New Ind Creat Hatchery Ctr, Sendai 9808579, Japan

来源：

CORROSION | 2024年 / 80卷 / 01期

基金：

国家重点研发计划;

关键词：

52M buttering; oxidation; postweld heat treatment; pressurized water reactor; stress corrosion cracking; DISSIMILAR METAL WELD; CR-FE ALLOYS; POST-WELD; HEAT-TREATMENT; STAINLESS-STEEL; IRON CONTENT; NI; MICROSTRUCTURE; SUSCEPTIBILITY; DEFORMATION;

D O I：

10.5006/4392

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The oxidation and stress corrosion cracking (SCC) behaviors of Alloy 52M buttering (52Mb) layer were studied in simulated pressurized water reactor (PWR) primary water after microstructure characterization. The 52Mb layer was first postweld heat treatment (1st-PWHT) and follow-up PWHT (FU-PWHT). Two dilution zones (DZs) were found in both the 1st-PWHT and FU-PWHT 52Mb samples. FU-PWHT decreased the Cr content in the first DZ, enhancing the oxidation rate and accelerating the formation of the local oxidation penetration zone at the oxide/substrate interface. Lower Cr content and high Fe content in the DZ were detrimental to the SCC resistance of the 52Mb in PWR primary water.

引用

页码：69 / 84

页数：16

共 43 条

[31] Microstructural Characterization of Alloy 52 Narrow-Gap Dissimilar Metal Weld After Aging [J].

Sarikka, Teemu ;

Mouginot, Roman ;

Ahonen, Matias ;

Lindqvist, Sebastian ;

Ehrnsten, Ulla ;

Nevasmaa, Pekka ;

Hanninen, Hannu .

PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, 2018, :763-777

[32] High-resolution characterization of intergranular attack and stress corrosion cracking of Alloy 600 in high-temperature primary water [J].

Thomas, LE ;

Bruemmer, SM .

CORROSION, 2000, 56 (06) :572-587

[33]

Toloczko M.B., 2009, P 14 INT C ENV DEGR, P690

[34] Role of carbides in stress corrosion cracking resistance of alloy 600 and controlled-purity Ni-16% Cr-9% Fe in primary water at 360°C [J].

Was, GS ;

Lian, K .

CORROSION, 1998, 54 (09) :675-688

[35] Characterization of stress corrosion cracks in Ni-based weld alloys 52, 52M and 152 grown in high-temperature water [J].

Xie, Yi ;

Wu, Yaqiao ;

Burns, Jatupom ;

Zhang, Jinsuo .

MATERIALS CHARACTERIZATION, 2016, 112 :87-97

[36] Effect of material chemical composition on oxidation and stress corrosion cracking of the submerged arc welding Alloy 52M overlay in a simulated PWR primary water [J].

Xu, Xinhe ;

Jia, Yibo ;

Pan, Deng ;

Cui, Tongming ;

Lu, Zhanpeng ;

Lozano-Perez, Sergio ;

Chen, Junjie ;

Li, Shuangyan ;

Shoji, Tetsuo .

JOURNAL OF NUCLEAR MATERIALS, 2024, 588

[37] The effect of prior deformation on stress corrosion cracking growth rates of Alloy 600 materials in a simulated pressurized water reactor primary water [J].

Yamazaki, Seiya ;

Lu, Zhanpeng ;

Ito, Yuzuru ;

Takeda, Yoichi ;

Shoji, Tetsuo .

CORROSION SCIENCE, 2008, 50 (03) :835-846

[38]

Yonezawa T., 2020, Comprehensive Nuclear Materials, VSecond, P319, DOI DOI 10.1016/B978-0-12-803581-8.00676-7

[39]

Yonezawa T., 2017, The Minerals, Metals & Materials Series, V1, P519

[40] Evaluating the reliability of PWSCC resistance of TT Alloy 690 and associated welds to the end of anticipated PWR plant life [J].

Yonezawa, Toshio ;

Hashimoto, Atsushi .

JOURNAL OF NUCLEAR MATERIALS, 2022, 560

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