Optimization of Heat Treatment Process and Corrosion Performance in High-temperature and High-pressure of Zr-1.35Sn-0.22Fe-0.13Cr-0.05Ni Alloy

doi:10.11902/1005.4537.2024.083

Journal of Chinese Society for Corrosion and protection

2025, Vol. 45

Issue (2): 497-505 DOI: 10.11902/1005.4537.2024.083

Current Issue | Archive | Adv Search

Optimization of Heat Treatment Process and Corrosion Performance in High-temperature and High-pressure of Zr-1.35Sn-0.22Fe-0.13Cr-0.05Ni Alloy

LEI Aijia¹, DAI Xun², XU Jiangtao², DENG Ruiju², HUANG Xuefei¹(

)

^1.College of Materials Science and Engineering, Sichuan university, Chengdu 610065, China
^2.Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu 610213, China

Cite this article:

LEI Aijia, DAI Xun, XU Jiangtao, DENG Ruiju, HUANG Xuefei. Optimization of Heat Treatment Process and Corrosion Performance in High-temperature and High-pressure of Zr-1.35Sn-0.22Fe-0.13Cr-0.05Ni Alloy. Journal of Chinese Society for Corrosion and protection, 2025, 45(2): 497-505.

Download:

HTML

PDF(13023KB)
Export: BibTeX | EndNote (RIS)

Abstract

The Zr-Sn-Fe-Cr-Ni alloy, due to its insensitivity to dissolved oxygen in high-temperature water corrosion environment, is suitable for reactors with high dissolved oxygen content such as Small Modular Reactors and Advanced Boiling Water Reactors. To develop high-performance Zr-Sn-Fe-Cr-Ni alloys, the Sn content was reduced, and the content of Fe, Cr, and Ni was appropriately increased based on the Zircaloys. Then the influence of heat treatments on the microstructural variations of the new Zr-1.35Sn-0.22Fe-0.13Cr-0.05Ni alloy was characterized. Meanwhile, the corrosion behavior of the Zr-1.35Sn-0.22Fe-0.13Cr-0.05Ni alloys, being subjected to two different heat treatments, was studied in high-temperature and high-pressure water at 360 ^oC/18.6 MPa for 330 d by taking Zircaloy-4 as comparison. Results show that the two different heat treated Zr-1.35Sn-0.22Fe-0.13Cr-0.05Ni alloys exhibited more or less the same corrosion behavior with typical approximate parabolic kinetics in the initial corrosion stage. After 220 d and 250 d of exposure, corrosion transitions occurred respectively. Compared to Zircaloy-4, the corrosion transition time was significantly delayed. This suggests that reducing the Sn content is advantageous in delaying the time for the occurrence of the corrosion transition during the initial corrosion period, which may be conductive to the improvement of long-term corrosion resistance of the Zr-Sn-Fe-Cr-Ni alloys. This may be ascribed to that by increasing the intermediate annealing temperature or extending the holding time by α-phase region for Zr-1.35Sn-0.22Fe-0.13Cr-0.05Ni alloy may be facilitate the increase of the average size of second phase particles, thus make the atomic ratio Fe/Cr closer to 1, which may be conductive to effectively delay the occurrence of the first corrosion transition of the Zr-Sn-Fe-Cr-Ni alloys during the initial corrosion period.

Key words: zirconium alloy corrosion second phase cumulative annealing parameter

Received: 18 March 2024 32134.14.1005.4537.2024.083

TG172.82

Fund: National Key R&D Program of China(2023YFB3710705);Open Project Program of Sichuan Provincial Key Laboratory of Science and Technology for Advanced Materials and Manufacturing Technology of Aviation Equipment(2023KFKT0009)

Corresponding Authors: HUANG Xuefei, E-mail: huangxf08@scu.edu.cn

	Service

	E-mail this article
	Add to citation manager
	E-mail Alert
	RSS
	（）
	Articles by authors
	LEI Aijia
	DAI Xun
	XU Jiangtao
	DENG Ruiju
	HUANG Xuefei

URL:

https://www.jcscp.org/EN/10.11902/1005.4537.2024.083 OR https://www.jcscp.org/EN/Y2025/V45/I2/497

Fig.1 Grain orientation distribution maps (a, b) in AD-RD direction and inverse pole figures (c, d) in AD direction for Y1 alloy (a, c) and Y3 alloy (b, d)

Table 1 Recrystallization fractions and the proportions of low-angle grain boundaries in Y1 and Y3 alloys

Fig.2 Positional distributions (a, b) and particle size statistics (c, d) of second phase particles in Y1 alloy (a, c) and Y3 alloy (b, d)

Fig.3 High-angle annular dark-field scanning (HAADF) images of Y1 alloy (a) and Y3 alloy (b)

Fig.4 Atomic ratios of Fe and Cr in Zr-Fe-Cr phases of Y1 alloy (a) and Y3 alloy (b)

Fig.5 Bright-field images and selected area electron diffraction (SAED) patterns of second phase particles in Y1 alloy (a-c) and Y3 alloy (d-f)

Fig.6 Mass gain curves of Y1, Y3 and Zircaloy-4 alloys during corrosion in high-temperature and high-pressure water

Table 2 Corrosion kinetics parameters of Y1, Y3 and Zircaloy-4 alloys

Fig.7 Cross-sectional morphologies of oxide films formed on Y1 alloy after exposure in high-temperature and high-pressure water for 70 d (a), 160 d (b), 220 d (c), 250 d (d), and 305 d (e)

Fig.8 Cross-sectional morphologies of oxide films formed on Y3 alloy after exposure in high-temperature and high-pressure water for 70 d (a), 160 d (b), 220 d (c), 250 d (d), and 305 d (e)

Fig.9 Cross-sectional morphologies of oxide films formed on Zircaloy-4 alloy after exposure in high-temperature and high-pressure water for 70 d (a), 160 d (b), 250 d (c) and 305 d (d)

Fig.10 3D morphologies of the metal-oxide interfaces of Y1 alloy (a-e) and Y3 alloy (f-j) after exposure in high-temperature and high-pressure water for 70 d (a, f), 160 d (b, g), 220 d (c, h), 250 d (d, i), and 305 d (e, j)

Fig.11 S_qvalues of the metal-oxide interfaces of Y1 and Y3 alloys as a function of corrosion time

1	IAEA. Waterside Corrosion of Zirconium Alloys in Nuclear Power Plants [M]. Vienna: International Atomic Energy Agency, 1998: 11
2	IAEA. Advances in Small Modular Reactor Technology Developments [M]. Vienna: IAEA Advanced Reactors Information System (ARIS), 2018: 11
3	Wei T G, Lin J K, Long C S, et al. Effect of dissolved oxygen in steam on the corrosion behaviors of zirconium alloys [J]. Acta Metall. Sin., 2016, 52: 209 doi: 10.11900/0412.1961.2015.00219
	韦天国, 林建康, 龙冲生等. 蒸汽中的溶解氧对锆合金腐蚀行为的影响 [J]. 金属学报, 2016, 52: 209 doi: 10.11900/0412.1961.2015.00219
4	Urbanic V F, Choubey R, Chow C K. Investigation of variables that influence corrosion of zirconium alloys during irradiation [A]. EuckenCM, GardeAM. Zirconium in the Nuclear Industry: Ninth International Symposium [M]. Philadelphia: ASTM International, 1991: 665
5	Kiran Kumar M, Aggarwal S, Kain V, et al. Effect of dissolved oxygen on oxidation and hydrogen pick up behavior—Zircaloy vs Zr-Nb alloys[J]. Nucl. Eng. Des., 2010, 240: 985
6	Johnson A B, Jr, LeSurf J E, Proebstle R A. Study of zirconium alloy corrosion parameters in the advanced test reactor [A]. SchemelJH, RosenbaumH S. Zirconium in Nuclear Applications [M]. Philadelphia: ASTM International, 1974: 495
7	Adamson R B, Rudling P. 4-Properties of zirconium alloys and their applications in light water reactors (LWRs) [A]. Murty K L. Materials Ageing and Degradation in Light Water Reactors [M]. Cambridge: Woodhead Publishing, 2013: 151
8	Garzarolli F, Broy Y, Busch R A. Comparison of the long-time corrosion behavior of certain Zr alloys in PWR, BWR, and laboratory tests [A]. BradleyER, SabolGP. Zirconium in the Nuclear Industry: Eleventh International Symposium [M]. Philadelphia: ASTM International, 1996: 850
9	Nanikawa S, Etoh Y, Shimada S, et al. Correlation between characteristics of oxide films formed on Zr alloys in BWRs and corrosion performance [A]. SabolGP, MoanGD. Zirconium in the Nuclear Industry: Twelfth International Symposium [M]. Philadelphia: ASTM International, 2000: 815
10	Ruhmann H, Manzel R, Sell H J, et al. In-BWR and out-of-pile nodular corrosion behavior of Zry-2/4 type melts with varying Fe, Cr, and Ni content and varying process history [A]. BradleyE R, SabolG P. Zirconium in the Nuclear Industry: Eleventh International Symposium [M]. Philadelphia: ASTM International, 1996: 865
11	Etoh Y, Shimada S, Yasuda T, et al. Development of new zirconium alloys for a BWR [A]. BradleyER, SabolGP. Zirconium in the Nuclear Industry: Eleventh International Symposium [M]. Philadelphia: ASTM International, 1996: 825
12	Garzarolli F, Cox B, Rudling P. Optimization of Zry-2 for high burnups [J]. J. ASTM Int., 2010, 7: 1
13	Sell H J, Trapp-Pritsching S, Garzarolli F. Effect of alloying elements and impurities on in-BWR corrosion of zirconium alloys [J]. J. ASTM Int., 2006, 3: 1
14	Chai L J, Luan B F, Chen J W, et al. Review on correlation of accumulated annealing parameter and corrosion resistance of Nb-containing zirconium alloys [J]. Rare Met. Mater. Eng., 2012, 41: 1119
	柴林江, 栾佰峰, 陈建伟等. 累积退火参数与含Nb锆合金耐腐蚀性能关系述评 [J]. 稀有金属材料与工程, 2012, 41: 1119
15	Standard test method for corrosion testing of products of zirconium, hafnium, and their alloys in water at 680°F (360 ^oC) or in steam at 750°F (400^oC) [S]. 2019
16	Chai L J, Luan B F, Zhou Y, et al. Review of second phase particles on zirconium alloys (Ⅰ): Zircaloys [J]. Chin. J. Nonferrous Met., 2012, 22: 1594
	柴林江, 栾佰峰, 周宇等. 锆合金第二相研究述评(Ⅰ): Zircaloys合金 [J]. 中国有色金属学报, 2012, 22: 1594
17	Bouineau V, Bénier G, Pêcheur D, et al. Analysis of the waterside corrosion kinetics of zircaloy-4 fuel cladding in French PWRs [J]. Nucl. Technol., 2010, 170: 444
18	Yilmazbayhan A, Motta A T, Comstock R J, et al. Structure of zirconium alloy oxides formed in pure water studied with synchrotron radiation and optical microscopy: Relation to corrosion rate [J]. J. Nucl. Mater., 2004, 324: 6
19	Liu J L, Yu H B, Karamched P, et al. Mechanism of the α-Zr to hexagonal-ZrO transformation and its impact on the corrosion performance of nuclear Zr alloys [J]. Acta Mater., 2019, 179: 328
20	Wei T G, Dai X, Zhao Y, et al. ZrO phase embedded in the oxide of Zr-Sn-Nb-Fe-Cr alloy after corrosion [J]. J. Nucl. Mater., 2022, 571: 153992
21	Yankova M S, Garner A, Baxter F, et al. Untangling competition between epitaxial strain and growth stress through examination of variations in local oxidation [J]. Nat. Commun., 2023, 14: 250 doi: 10.1038/s41467-022-35706-3 pmid: 36646682
22	Wei T G, Dai X, Long C S, et al. Comparison on the microstructure, aqueous corrosion behavior and hydrogen uptake of a new Zr-Sn-Nb alloy prepared by different hot rolling temperature [J]. Corros. Sci., 2021, 192: 109808
23	Likhanskii V V, Aliev T N, Kolesnik M Y, et al. Method of elastic energy minimization for evaluation of transition parameters in oxidation kinetics of Zr alloys [J]. Corros. Sci., 2012, 61: 143
24	Ni N, Lozano-Perez S, Sykes J M, et al. Focussed ion beam sectioning for the 3D characterisation of cracking in oxide scales formed on commercial ZIRLO^TM alloys during corrosion in high temperature pressurized water [J]. Corros. Sci., 2011, 53: 4073
25	Rudling P, Wikmark G, Lehtinen B, et al. Impact of second phase particles on BWR Zr-2 corrosion and hydriding performance [A]. SabolGP, MoanGD. Zirconium in the Nuclear Industry: Twelfth International Symposium [M]. Philadelphia: ASTM International, 2000: 678
26	Tejland P, Andrén H O, Sundell G, et al. Oxidation mechanism in Zircaloy-2—the effect of SPP size distributioN [A]. ComstockB, BarbérisP. Zirconium in the Nuclear Industry: 17th Volume [M]. Philadelphia: ASTM International, 2015: 373
27	Tejland P, Andrén H O. Origin and effect of lateral cracks in oxide scales formed on zirconium alloys [J]. J. Nucl. Mater., 2012, 430: 64
28	Annand K, Nord M, MacLaren I, et al. The corrosion of Zr(Fe, Cr)₂ and Zr₂Fe secondary phase particles in Zircaloy-4 under 350 ^oC pressurised water conditions [J]. Corros. Sci., 2017, 128: 213
29	Proff C, Abolhassani S, Lemaignan C. Oxidation behaviour of zirconium alloys and their precipitates-A mechanistic study [J]. J. Nucl. Mater., 2013, 432: 222
30	Abolhassani S, Proff C, Veleva L, et al. Transmission electron microscopy examinations of metal-oxide interface of zirconium-based alloys irradiated in halden reactor-IFA-638 [A]. ComstockRJ, MottaAT. Zirconium in the Nuclear Industry: 18th International Symposium [M]. Philadelphia: ASTM International, 2018: 614
31	Frankel P G, Wei J, Francis E M, et al. Effect of Sn on corrosion mechanisms in advanced Zr-cladding for pressurised water reactors [A]. ComstockB, BarbérisP. Zirconium in the Nuclear Industry: 17th Volume [M]. Philadelphia: ASTM International, 2015: 404
32	Liao J J, Zhang J S, Zhang W, et al. Critical behavior of interfacial t-ZrO₂ and other oxide features of zirconium alloy reaching critical transition condition [J]. J. Nucl. Mater., 2021, 543: 152474
33	Liao J J, Xu F, Peng Q, et al. Research on the existence and stability of interfacial tetragonal zirconia formed on zirconium alloys [J]. J. Nucl. Mater., 2020, 528: 151846

[1]	ZHAO Jie, XU Guangxu, ZHANG Hongwei, LI Jingfa, LV Ran, WANG Jialong, YAN Donglei. Coupling Effect of Hydrogen Embrittlement and Corrosion of X80 Pipeline Steel in Hydrogen-doped Natural Gas[J]. 中国腐蚀与防护学报, 2025, 45(2): 407-415.
[2]	MIAO Hao, YIN Chenghui, WANG Honglun, GAO Yihui, CHEN Junhang, ZHANG Hao, LI Bo, WU Junsheng, XIAO Kui. Correlation of Laboratory Simulation Test and Field Exposure Test for Three Stainless Steels in Polluted Marine Atmosphere of Qingdao Coastal Area[J]. 中国腐蚀与防护学报, 2025, 45(2): 449-459.
[3]	JIANG Huifang, LIU Yanghao, LIU Ying, LI Yingchao, YU Haobo, ZHAO Bo, CHEN Xi. Mechanism of Microbial Corrosion of J55 Steel in Hydrogen-containing Environments in Underground Hydrogen Storage Facilities[J]. 中国腐蚀与防护学报, 2025, 45(2): 347-358.
[4]	CUI Bolun, ZHAO Jie, LV Ran, LI Jingfa, YU Bo, YAN Donglei. Research Progress in Composite Protection Technology Against Hydrogen-embrittlement and -corrosion for Hydrogen-blended Natural Gas Pipeline[J]. 中国腐蚀与防护学报, 2025, 45(2): 327-337.
[5]	JIN Zhenting, SONG Qining, LIU Qi, PENG Chunlan, XU Nan, LU Qiqing, BAO Yefeng, ZHAO Lijuan, ZHAO Jianhua. Long-term Corrosion Behavior of Three Cu-alloys in 3.5%NaCl Solutions with Different pH Values[J]. 中国腐蚀与防护学报, 2025, 45(2): 506-514.
[6]	ZHAI Xiwei, LIU Shiyi, WANG Li, JIA Ruiling, ZHANG Huixia. Effect of Applied Load on Corrosion Behavior of 5383 Al-alloy Welded Joints[J]. 中国腐蚀与防护学报, 2025, 45(2): 515-522.
[7]	WU Yuhang, CHEN Xu, WANG Shoude, LIU Chang, LIU Jie. Stress Corrosion Behavior of X70 Steel in an Artificial Near-neutral Soil Solution Under Direct Current[J]. 中国腐蚀与防护学报, 2025, 45(2): 489-496.
[8]	ZHENG Wenpei, LIU Yingzheng, ZHANG Yaru, ZHOU Taotao, LI Xingtao, YU Shengyang, JIANG Lumeng. An Integrated Corrosion Rate Prediction Model Based on Global and Local Error Fusion: A Robust Optimization Strategy[J]. 中国腐蚀与防护学报, 2025, 45(2): 523-532.
[9]	BAI Zhengqing, NONG Jing, WEI Shichen, XU Jian. Effect of Pre-charging Hydrogen on Corrosion Behavior of Ni-Cr Alloy in High Temperature and High Pressure Water[J]. 中国腐蚀与防护学报, 2025, 45(2): 338-346.
[10]	CUI Dechun, XIONG Liang, YU Bangting, WU Haozhi, DONG Shaohua, CHEN Lin. Finite Element Analysis of Local Hydrogen Concentration in Hydrogen Pipeline With Corrosion Defects[J]. 中国腐蚀与防护学报, 2025, 45(2): 359-370.
[11]	YANG Zhenyu, JI Chao, GUO Liya, XU Run, PENG Wei, ZHAO Hongshan, WEI Xicheng, DONG Han. Initial Corrosion Behavior of Several Pure Irons and Steels in 3.5%NaCl Solution[J]. 中国腐蚀与防护学报, 2025, 45(2): 469-478.
[12]	TANG Yixin, ZHANG Fei, CUI Zhongyu, CUI Hongzhi, LI Yizhou. Effect of Hydrogen on Crevice Corrosion Behavior of 2205 Duplex Stainless Steel in 3.5%NaCl Solution[J]. 中国腐蚀与防护学报, 2025, 45(2): 431-437.
[13]	YAN Bingchuan, ZENG Yunpeng, ZHANG Ning, SHI Xianbo, YAN Wei. Microbiologically Influenced Corrosion of Cu-bearing Steel Welded Joints for Petroleum Pipes[J]. 中国腐蚀与防护学报, 2025, 45(2): 479-488.
[14]	MA Hongyu, LIU Rui, CUI Yu, KE Peiling, LIU Li, WANG Fuhui. Effect of Hydrostatic Pressure on Corrosion Behavior of Cr/GLC Laminated Coating[J]. 中国腐蚀与防护学报, 2025, 45(1): 103-114.
[15]	YANG Xiaodong, LI Xue, YU Zheng, YANG Shasha, CHEN Minghui, WANG Fuhui. Corrosion Behavior of Enamel Coatings in Molten Salts MgCl₂-KCl-NaCl at 600 ^oC[J]. 中国腐蚀与防护学报, 2025, 45(1): 155-163.

No Suggested Reading articles found!

Viewed

Full text

Abstract

Cited

Shared

Discussed