10000 hours thermal aging behavior and supercritical CO2 corrosion performance of candidate cladding AFA alloys for novel gas - cooled reactors

doi:10.1016/j.jnucmat.2024.154913

IMR OpenIR

	10000 hours thermal aging behavior and supercritical CO2 corrosion performance of candidate cladding AFA alloys for novel gas - cooled reactors
	Shu, Ming 1,2; Zhou, Qin 2; Sun, Yongduo 1; Wu, Bin 3; Ming, Hongliang 3; Xiao, Jun 1
通讯作者	Zhou, Qin(qinzhou@tsinghua.edu.cn)
	2024-04-01
发表期刊	JOURNAL OF NUCLEAR MATERIALS
ISSN	0022-3115
卷号	591 页码:13
摘要	This study investigated the thermal aging (10,000 h at 650 degrees C) and corrosion performance (3000 h at 650 degrees C/15 MPa under sCO2) of two AFA alloys (AFA-20 and AFA-14), featuring 20 wt.% and 14 wt.% Cr. The increase in Cr content elevated the thermodynamically stable a content and promoted its precipitation. The a precipitation within the matrix significantly decelerated the coarsening kinetics of the Laves phase in AFA-20 over 5000 h aging. The intergranular a phase facilitated crack formation, potentially increasing elongation, while the intragranular a phase mitigated stress concentration at grain boundaries, making AFAs more brittle. AFA-20 developed a continuous protective Al2O3 oxide layer, whereas AFA-14, lacking this shielding, experienced increased internal oxidation. M23C6 carbides formed in the internal reaction zone, yet notably enriched in Mo rather than Cr.
关键词	AFA Thermal aging SupercriticalCO2 a phase Chromium
资助者	Special Funds for the Key Research and Development Program of the Ministry of Science and Technology of China ; Natural Science Founda-tion of Sichuan Province
DOI	10.1016/j.jnucmat.2024.154913
收录类别	SCI
语种	英语
资助项目	Special Funds for the Key Research and Development Program of the Ministry of Science and Technology of China[2020YFB1901800] ; Natural Science Founda-tion of Sichuan Province[2022NSFSC1191]
WOS研究方向	Materials Science ; Nuclear Science & Technology
WOS类目	Materials Science, Multidisciplinary ; Nuclear Science & Technology
WOS记录号	WOS:001174441400001
出版者	ELSEVIER
引用统计	被引频次：5[WOS] [WOS记录] [WOS相关记录]
文献类型	期刊论文
条目标识符	http://ir.imr.ac.cn/handle/321006/184746
专题	中国科学院金属研究所
通讯作者	Zhou, Qin
作者单位	1.Nucl Power Inst China, Chengdu 610213, Peoples R China 2.Tsinghua Univ, Inst Nucl & New Energy Technol, Beijing 100084, Peoples R China 3.Chinese Acad Sci, CAS Key Lab Nucl Mat & Safety Assessment, Inst Met Res, Shenyang 110016, Peoples R China
推荐引用方式 GB/T 7714	Shu, Ming,Zhou, Qin,Sun, Yongduo,et al. 10000 hours thermal aging behavior and supercritical CO2 corrosion performance of candidate cladding AFA alloys for novel gas - cooled reactors[J]. JOURNAL OF NUCLEAR MATERIALS,2024,591:13.
APA	Shu, Ming,Zhou, Qin,Sun, Yongduo,Wu, Bin,Ming, Hongliang,&Xiao, Jun.(2024).10000 hours thermal aging behavior and supercritical CO2 corrosion performance of candidate cladding AFA alloys for novel gas - cooled reactors.JOURNAL OF NUCLEAR MATERIALS,591,13.
MLA	Shu, Ming,et al."10000 hours thermal aging behavior and supercritical CO2 corrosion performance of candidate cladding AFA alloys for novel gas - cooled reactors".JOURNAL OF NUCLEAR MATERIALS 591(2024):13.