ODS钢在600和700 ℃静态Pb-Bi共晶中的腐蚀行为及机理

doi:10.11900/0412.1961.2020.00035

金属学报

2020, Vol. 56

Issue (10): 1366-1376 DOI: 10.11900/0412.1961.2020.00035

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ODS钢在600和700 ℃静态Pb-Bi共晶中的腐蚀行为及机理

包飞洋¹^,², 李艳芬¹^,²^,³(

), 王光全²^,⁴, 张家榕², 严伟¹^,²^,³, 石全强²^,³, 单以银¹^,²^,³, 杨柯¹^,², 许斌⁵, 宋丹戎⁵, 严明宇⁵, 魏学栋⁵

1 中国科学技术大学材料科学与工程学院沈阳 110016
2 中国科学院金属研究所沈阳 110016
3 中国科学院金属研究所中国科学院核用材料与安全评价重点实验室沈阳 110016
4 中国科学技术大学纳米科学与技术学院苏州 215000
5 中国核动力研究设计院成都 610005

Corrosion Behaviors and Mechanisms of ODS Steel Exposed to Static Pb-Bi Eutectic at 600 and 700 ℃

BAO Feiyang¹^,², LI Yanfen¹^,²^,³(

), WANG Guangquan²^,⁴, ZHANG Jiarong², YAN Wei¹^,²^,³, SHI Quanqiang²^,³, SHAN Yiyin¹^,²^,³, YANG Ke¹^,², XU Bin⁵, SONG Danrong⁵, YAN Mingyu⁵, WEI Xuedong⁵

1 School of Materials Science and Engineering, University of Science and Technology of China, Shenyang 110016, China
2 Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China
3 Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China
4 Nano Science and Technology Institute, University of Science and Technology of China, Suzhou 215000, China
5 Nuclear Power Institute of China, Chengdu 610005, China

引用本文:

包飞洋, 李艳芬, 王光全, 张家榕, 严伟, 石全强, 单以银, 杨柯, 许斌, 宋丹戎, 严明宇, 魏学栋. ODS钢在600和700 ℃静态Pb-Bi共晶中的腐蚀行为及机理[J]. 金属学报, 2020, 56(10): 1366-1376.
Feiyang BAO, Yanfen LI, Guangquan WANG, Jiarong ZHANG, Wei YAN, Quanqiang SHI, Yiyin SHAN, Ke YANG, Bin XU, Danrong SONG, Mingyu YAN, Xuedong WEI. Corrosion Behaviors and Mechanisms of ODS Steel Exposed to Static Pb-Bi Eutectic at 600 and 700 ℃[J]. Acta Metall Sin, 2020, 56(10): 1366-1376.

全文: PDF(3522 KB) HTML

摘要:

以一种极具潜力的先进核能候选氧化物弥散强化(ODS)钢为研究对象，以不控制氧浓度的液态金属Pb-Bi共晶(LBE)为腐蚀介质，研究了静态下高温(600和700 ℃)不同腐蚀时间对ODS钢腐蚀行为的影响及其微观机制。结果表明，600 ℃腐蚀至2000 h，ODS钢表面生成总厚度约为10 μm的典型双层氧化膜，同时在内氧化层下方形成了一层较薄的富Al氧化层。基于致密的尖晶石内氧化层及富Al氧化层的保护作用有效减缓了腐蚀氧化速率，ODS钢显示优异于其它材料的耐LBE腐蚀性能。ODS钢在700 ℃腐蚀所形成的氧化膜结构及厚度与600 ℃明显不同：腐蚀100 h主要形成了厚度约为500 nm的Al₂O₃保护膜，大幅降低了腐蚀速率；腐蚀时间延长至500 h，大部分区域Al₂O₃氧化膜仍然存在，但同时出现的少量“疖状氧化物”破坏了Al₂O₃保护膜的连续性，从而成为了腐蚀的突破口。

关键词 ：先进核能系统, Pb-Bi共晶(LBE), 氧化物弥散强化(ODS)钢, 高温腐蚀, 氧化膜

Abstract：

With good neutron properties, anti-irradiation performances, heat transfer properties and inherent safety characteristics, liquid lead or Pb-Bi eutectic (LBE) has been a primary candidate coolant for accelerator driven system and advanced nuclear reactors. However, corrosion of structural materials is a critical challenge in the use of liquid lead and LBE in high temperature nuclear reactors. Therefore, research on corrosion compatibility of structural materials with LBE at elevated temperatures is of great significance. In this work, the long-term corrosion experiments in static LBE for a oxide dispersion strengthened (ODS) steel were carried out at 600 and 700 ℃. The temperature effects on different corrosion behaviors were studied by the analyses of XRD, SEM and EDS, and the underlying mechanisms were clarified. After exposing to LBE at 600 ℃ for up to 2000 h, a typical double-layer oxide scale with the thickness of about 10 μm was formed on the surface of ODS steel, which was composed of outer layers of Pb-Fe-O and Fe₃O₄ and inner layer of Fe-Cr-Al spinal. In addition, a thin Al-rich layer was also formed under the inner layer. Due to the protective effect of the relatively dense inner layer and the Al-rich layer, ODS steel showed excellent resistance to LBE corrosion at 600 ℃ with a significantly lower corrosion rate. On the contrary, when exposed to LBE at 700 ℃ , the structure and thickness of the oxide scale formed on the surface of the ODS steel were obviously different. After exposure for 100 h, a dense protective Al₂O₃ oxide layer with a thickness of about 500 nm was formed, greatly reducing the corrosion rate. With the corrosion time prolonging to 500 h at 700 ℃, most of Al₂O₃ layer was still remained. However, a few of nodular-like oxides were formed originated from local weak areas, which broken off the continuity of protective Al₂O₃and led to deeper corrosion by LBE.

Key words： advanced nuclear energy system Pb-Bi eutectic (LBE) oxide dispersion strengthened (ODS) steel high temperature corrosion oxide scale

收稿日期: 2020-01-21

ZTFLH:

TG172

基金资助:国防科技工业核动力技术创新中心项目(HDLCXZX-2019-HD-15-01);国家自然科学基金项目(U1832206);中科院金属研究所“优秀学者”人才引进项目(JY7A7A111A1)

作者简介: 包飞洋，女，1995年，硕士生

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	包飞洋
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	张家榕
	严伟
	石全强
	单以银
	杨柯
	许斌
	宋丹戎
	严明宇
	魏学栋
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https://www.ams.org.cn/CN/10.11900/0412.1961.2020.00035 或 https://www.ams.org.cn/CN/Y2020/V56/I10/1366

图1 腐蚀实验设备的结构示意图

图2 ODS钢在静态Pb-Bi共晶(LBE)中腐蚀不同时间后表面氧化物的XRD谱

图3 ODS钢在600 ℃静态LBE中腐蚀不同时间表面腐蚀形貌的变化

图4 ODS钢在600 ℃静态LBE中腐蚀100 h的表面形貌

表1 图4中ODS钢在600 ℃静态LBE中腐蚀100 h表面氧化物的EDS分析

图5 ODS钢在700 ℃静态LBE中腐蚀不同时间的表面腐蚀形貌

表2 图5e和f中ODS钢在700 ℃静态LBE中腐蚀500 h表面氧化物的EDS分析

图6 ODS钢在600 ℃静态LBE中腐蚀不同时间的截面形貌

图7 ODS钢在600 ℃静态LBE中腐蚀500 h截面的EDS面分析

图8 ODS钢在700 ℃静态LBE中腐蚀100和500 h后的腐蚀截面形貌

图9 ODS钢在700 ℃静态LBE中腐蚀500 h的截面成分EDS面分析

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