INVESTIGATION ON THE CORROSIVE ANISOTROPY OF Zr-Sn-Fe-Cr-(Nb) ALLOYS IN 500 ℃ SUPER-HEATED STEAM

doi:10.11900/0412.1961.2016.00043

Acta Metall Sin

2016, Vol. 52

Issue (12): 1565-1571 DOI: 10.11900/0412.1961.2016.00043

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INVESTIGATION ON THE CORROSIVE ANISOTROPY OF Zr-Sn-Fe-Cr-(Nb) ALLOYS IN 500 ℃ SUPER-HEATED STEAM

Jun ZHANG^1,²,Meiyi YAO^1,²(

),Xuankai FENG^1,²,Zhigang WANG^1,²,Jiao HUANG^1,²,Xun DAI³,Jinlong ZHANG^1,²,Bangxin ZHOU^1,²

1 Institute of Materials, Shanghai University, Shanghai 200072, China
2 Laboratory for Microstructures, Shanghai University, Shanghai 200444, China
3 Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu 610213, China

Cite this article:

Jun ZHANG,Meiyi YAO,Xuankai FENG,Zhigang WANG,Jiao HUANG,Xun DAI,Jinlong ZHANG,Bangxin ZHOU. INVESTIGATION ON THE CORROSIVE ANISOTROPY OF Zr-Sn-Fe-Cr-(Nb) ALLOYS IN 500 ℃ SUPER-HEATED STEAM. Acta Metall Sin, 2016, 52(12): 1565-1571.

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Abstract

Zirconium alloys are widely used as nuclear fuel cladding in water reactors because of their low cross-section for thermal neutron absorption, reasonable mechanical properties and adequate corrosion resistance in high temperature water. Zirconium alloys have a prominent anisotropic characteristic because of the hexagonal close-packed crystal structure. The anisotropic growth of oxide layers is related to corrosion conditions and chemical composition of zirconium alloys. The corrosive anisotropy of Zr-0.72Sn-0.32Fe-0.14Cr and Zr-0.85Sn-0.16Nb-0.37Fe-0.18Cr coarse-grained specimens was investigated in a superheated steam at 500 ℃ and 10.3 MPa by autoclave tests. EBSD, SEM and TEM were used to investigate the microstructures of the alloys and the relationship between the oxide thickness and the grain orientation of the metal matrix. Results showed that the structures of second phase particles (SPPs) can be affected by Nb: the face-centered cubic Zr(Fe, Cr)₂ precipitates were mainly detected in Zr-0.72Sn-0.32Fe-0.14Cr alloy, while the face-centered cubic and hexagonal close packed Zr(Nb, Fe, Cr)₂ precipitates were observed in the Zr-0.85Sn-0.16Nb-0.37Fe-0.18Cr alloy. No nodular corrosion appeared on the two alloys for 500 h exposure. There was no big difference between the thickness of oxide layers and the grain orientations, i.e. no corrosive anisotropy of the two alloys was presented.

Key words: zirconium alloy, SPPs, corrosion resistance, corrosive anisotropy, microstructure

Received: 26 January 2016

Fund: Supported by National Natural Science Foundation of China (No.51471102), and the Science and Technology on Reactor Fuel and Materials Laboratory′s Project of Nuclear Power Institute of China (No.STRFML-2015-01)

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	Articles by authors
	Jun ZHANG
	Meiyi YAO
	Xuankai FENG
	Zhigang WANG
	Jiao HUANG
	Xun DAI
	Jinlong ZHANG
	Bangxin ZHOU

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https://www.ams.org.cn/EN/10.11900/0412.1961.2016.00043 OR https://www.ams.org.cn/EN/Y2016/V52/I12/1565

Fig.1 (0001) pole figure of the coarse-grained specimens of alloy A (a) and alloy B (b) (RD—rolling direction, TD—transverse direction)

Fig.2 SEM images of the coarse-grained specimens of alloy A (a) and alloy B (b)

Fig.3 TEM images (a1, b1, c1), and corresponding EDS (a2, b2, c2) and SAED patterns (c1, c2, c3) of particles shown by arrows in Figs.3a1, b1 and c1 respectively for alloy A (a1~a3) and alloy B (b1~c3) (a1~a3) Zr(Fe, Cr)₂ (fcc) (b1~b3) Zr(Nb, Fe, Cr)₂ (fcc) (c1~c3) Zr(Nb, Fe, Cr)₂ (hcp)

Fig.4 Mass gain vs exposure time of alloys A and B for 500 h exposure in super-heated steam at 500 ℃ and 10.3 MPa

Fig.5 Fracture surface images of oxide layers formed on alloys A (a) and B (b) after 500 h exposure in super-heated steam at 500 ℃ and 10.3 MPa

Fig.6 Inverse pole figure showing the orientations of the metal grain surface on which the thickness of the oxide layer was measured (a) and the relationship between the oxide thickness and the grain surface orientations of the metal matrix (b) for alloy A corroded at 500 ℃ in super-heated steam after 500 h exposure

Fig.7 Inverse pole figure showing the orientations of the metal grain surface on which the thickness of the oxide layer was measured (a) and the relationship between the oxide thickness and the grain surface orientations of the metal matrix (b) for alloy B corroded at 500 ℃ in super-heated steam after 500 h exposure

[1]	Liu J Z. Nuclear Structure Materials.Beijing: Chemical Industry Press, 2007: 19
[1]	(刘建章. 核结构材料. 北京: 化学工业出版社, 2007: 19)
[2]	Zhou B X. Chin J Nucl Sci Eng, 1993; 13: 51
[2]	(周邦新. 核科学与工程, 1993; 13: 51)
[3]	Kim H J, Kim T H, Jeong Y H.J Nucl Mater, 2002; 306: 44
[4]	Zhou B X, Peng J C, Yao M Y, Li Q, Xia S, Du C X, Xu G.In: Limb?ck M, Barbéris P eds., Zirconium in the Nuclear Industry: 16th International Symposium, ASTM STP 1529, Baltimore: ASTM International, 2012: 620
[5]	Yao M Y, Zhou B X, Li Q, Xia S, Liu W Q.Shanghai Met, 2008; 30(6): 1
[5]	(姚美意, 周邦新, 李强, 夏爽, 刘文庆. 上海金属, 2008; 30(6): 1)
[6]	Sun G C.Master Thesis, Shanghai University, 2012(孙国成, 上海大学硕士学位论文, 2012)
[7]	Wang Z P, Xue Y T, Liu J N, Shi C Z, Zhang Z.J Xi′an Technol Univ, 2010; 30: 166
[7]	(王正品, 薛钰婷, 刘江南, 石崇哲, 张琢. 西安工业大学学报, 2010; 30: 166)
[8]	Kearns J J.J Nucl Mater, 2001; 299: 171
[9]	Sun G C, Zhou B X, Yao M Y, Xie S J, Li Q.Acta Metall Sin, 2012; 48: 1103
[9]	(孙国成, 周邦新, 姚美意, 谢世敬, 李强. 金属学报, 2012; 48: 1103)
[10]	Zhou B X, Li Q, Yao M Y, Liu W Q, Chu Y L.Corros Prot, 2009; 30: 589
[10]	(周邦新, 李强, 姚美意, 刘文庆, 褚于良. 腐蚀与防护, 2009; 30: 589)
[11]	IAEA. Waterside Corrosion of Zirconium Alloys in Nuclear Power Plants. Austria: IAEA, 1998: 40
[12]	Wang B Y, Zhou B X, Wang Z, Huang J, Yao M Y, Zhou J.Acta Metall Sin, 2015; 51: 1545
[12]	(王波阳, 周邦新, 王桢, 黄娇, 姚美意, 周军. 金属学报, 2015; 51: 1545)
[13]	Charquet D, Tricot R, Wadier, J F.In: Van Swam L F P, Eucken C M eds., Zirconium in the Nuclear Industry: Eighth Symposium, ASTM STP 1023, Philadelphia: ASTM, 1989: 374
[14]	Zhou B X, Li Q, Yao M Y, Xia S, Liu W Q, Chu Y L.Rare Met Mater Eng, 2007; 36: 1129
[14]	(周邦新, 李强, 姚美意, 夏爽, 刘文庆, 褚于良. 稀有金属材料与工程, 2007; 36: 1129)
[15]	Foster J P, Yueh H K, Comstock R J.Zirconium in the Nuclear Industry: 15th International Symposium, ASTM STP 1505, Baltimore: ASTM, 2009: 457
[16]	Yueh H K, Kesterson R L, Comstock R J, Shah H H, Colburn D J, Dahlback M, Hallstadius L.In: Kammenzind B, Rudling P eds., Zirconium in the Nuclear Industry: 14th International Symposium, ASTM STP 1467, Bridgeport: ASTM, 2005: 330
[17]	Wei J, Frankel P, Polatidis E, Blat M, Ambard A, Comstock R J, Hallstadius L, Hudson D, Smith G D W, Grovenor C R M, Klaus M, Cottis R A , Lyon S, Preuss M.Acta Mater, 2013; 61: 4200
[18]	Woo O T, Griffiths M.J Nucl Mater, 2009; 384: 77
[19]	Zhou B X, Yo M Y, Li Q, Xia S, Liu W Q, Chu Y L.Rare Met Mater Eng, 2007; 36: 1317
[19]	(周邦新, 姚美意, 李强, 夏爽, 刘文庆, 褚于良. 稀有金属材料与工程, 2007; 36: 1317)

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