<strong>Zr-1.35Sn-0.22Fe-0.13Cr-0.05Ni</strong>合金热处理工艺优化及其高温高压水腐蚀行为研究

doi:10.11902/1005.4537.2024.083

中国腐蚀与防护学报

2025, Vol. 45

Issue (2): 497-505 CSTR: 32134.14.1005.4537.2024.083 DOI: 10.11902/1005.4537.2024.083

研究报告

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Zr-1.35Sn-0.22Fe-0.13Cr-0.05Ni合金热处理工艺优化及其高温高压水腐蚀行为研究

雷艾嘉¹, 戴训², 许江涛², 邓睿驹², 黄雪飞¹(

)

^1.四川大学材料科学与工程学院成都 610065
^2.中国核动力研究设计院反应堆燃料及材料重点实验室成都 610213

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

引用本文:

雷艾嘉, 戴训, 许江涛, 邓睿驹, 黄雪飞. Zr-1.35Sn-0.22Fe-0.13Cr-0.05Ni合金热处理工艺优化及其高温高压水腐蚀行为研究[J]. 中国腐蚀与防护学报, 2025, 45(2): 497-505.
Aijia LEI, Xun DAI, Jiangtao XU, Ruiju DENG, Xuefei HUANG. 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[J]. Journal of Chinese Society for Corrosion and protection, 2025, 45(2): 497-505.

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摘要:

研究了不同热处理工艺处理后得到的Zr-1.35Sn-0.22Fe-0.13Cr-0.05Ni合金在360 ℃、18.6 MPa去离子水环境中的均匀腐蚀行为。实验结果表明，Zr-1.35Sn-0.22Fe-0.13Cr-0.05Ni合金的腐蚀动力学曲线在转折点前表现出典型的类抛物线规律，其腐蚀动力学初次转折时间相较Zircaloy-4合金(Zr-1.50Sn-0.20Fe-0.1Cr)显著推迟，意味着降低Sn元素可以提升锆合金的抗高温高压水腐蚀性能。提高Zr-1.35Sn-0.22Fe-0.13Cr-0.05Ni合金的中间退火温度或延长α相的保温时间可以增加第二相的平均粒径，同时可以使Zr(Fe, Cr)₂中的Fe/Cr原子比率更接近1，有利于延长腐蚀动力学初次转折时间。

关键词 ：锆合金, 腐蚀, 第二相, 累积退火参数

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

收稿日期: 2024-03-18 32134.14.1005.4537.2024.083

ZTFLH:

TG172.82

基金资助:国家重点研发计划(2023YFB3710705);高端装备先进材料与制造重点实验室开放课题(2023KFKT0009)

通讯作者: 黄雪飞，E-mail：huangxf08@scu.edu.cn，研究方向为核材料

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

作者简介: 雷艾嘉，女，1994年生，硕士生

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图1 原始管材AD-RD方向的晶粒取向分布图和AD方向的反极图

表1 锆合金原始管材再结晶分数和小角度晶界占比

图2 Y1合金和Y3合金的第二相分布与第二相粒径统计图

图3 Y1合金和Y3合金基体的高角环形暗场(HAADF)图像

图4 Y1合金和Y3合金中Zr-Fe-Cr相的Fe/Cr比率

图5 Y1合金和Y3合金的第二相明场和选区电子衍射(SAED)花样

图6 锆合金腐蚀增重和时间关系图

表2 腐蚀动力学曲线参数

图7 Y1合金高温高压水腐蚀不同时间后的表面氧化膜截面形貌

图8 Y3合金高温高压水腐蚀不同时间后的氧化膜截面形貌

图9 Zircaloy-4合金高温高压水腐蚀不同时间后的氧化膜截面形貌

图10 Y1合金和Y3合金高温高压水腐蚀不同时间后的金属-氧化物界面三维形貌

图11 金属-氧化物界面Sq与腐蚀时间关系图

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