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中国腐蚀与防护学报  2026, Vol. 46 Issue (2): 567-575     CSTR: 32134.14.1005.4537.2025.116      DOI: 10.11902/1005.4537.2025.116
  研究报告 本期目录 | 过刊浏览 |
Fe离子辐照对ODS钢在饱和氧液态铅中腐蚀行为的影响
杜乾1, 马泽林1, 恽迪1, 顾龙2, 郭少强1()
1.西安交通大学核科学与技术学院 陕西省先进核能与技术重点实验室 西安 710049
2.兰州大学核科学与技术学院 兰州 730000
Effect of Fe-ion Irradiation on Corrosion Behavior of ODS Steels in Oxygen-saturated Molten Lead
DU Qian1, MA Zelin1, YUN Di1, GU Long2, GUO Shaoqiang1()
1.Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China
2.School of Nuclear Science and Technology, Lanzhou University, Lanzhou 730000, China
引用本文:

杜乾, 马泽林, 恽迪, 顾龙, 郭少强. Fe离子辐照对ODS钢在饱和氧液态铅中腐蚀行为的影响[J]. 中国腐蚀与防护学报, 2026, 46(2): 567-575.
Qian DU, Zelin MA, Di YUN, Long GU, Shaoqiang GUO. Effect of Fe-ion Irradiation on Corrosion Behavior of ODS Steels in Oxygen-saturated Molten Lead[J]. Journal of Chinese Society for Corrosion and protection, 2026, 46(2): 567-575.

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摘要: 

氧化物弥散强化(ODS)钢具有优异的高温力学性能和抗辐照性能,是铅冷快堆包壳的重要候选材料。然而,其在辐照条件下的液态铅腐蚀行为尚不清楚。为探明辐照-腐蚀影响机制,本文研究5种不同Cr、Si、Al和Zr含量的ODS钢,在600 ℃、Fe离子辐照后,在饱和氧的液态铅中的腐蚀特性。采用电子背散射衍射(EBSD)表征ODS钢的晶粒组织、利用透射电子显微镜(TEM)分析辐照诱导缺陷、通过扫描电子显微镜(SEM)和能谱仪(EDS)检定氧化膜成分及厚度。结果表明,ODS钢辐照后均形成高密度位错环,但未观察到空洞形成。通过与未辐照ODS钢比较,可见辐照对液态铅腐蚀生成氧化膜的成分和厚度影响不显著。其中,9Cr0.5Si4.5Al-ODS钢由于含有4.5% (质量分数) Al和较小的晶粒尺寸,在腐蚀后形成了单一的保护性Al2O3膜;而其余4种ODS钢则均形成了较厚的双层结构的氧化膜。

关键词 ODS钢Fe离子辐照高温液铅腐蚀辐照影响腐蚀    
Abstract

Oxide dispersion-strengthened (ODS) steels are considered promising candidate material for lead-based fast reactor (LFRs) owing to their superior resistance to irradiation-induced swelling and excellent high-temperature mechanical properties. However, improving the corrosion resistance under irradiation conditions remains a major challenge. To investigate the effect of irradiation induced damage on corrosion behavior in molten lead, five ODS steels with varying Cr, Si, Al and Zr contents were subjected to Fe-ion irradiation and subsequent corrosion tests in oxygen-saturated molten lead at 600 ℃. The grain structure and ions irradiation induced damage of the ODS steels were characterized using electron backscatter diffraction (EBSD) and transmission electron microscopy (TEM) operated at 200 kV respectively. After corrosion tests, the morphology and composition of the formed oxide scales were characterized using scanning electron microscopy (SEM) and energy dispersive spectroscopy (EDS). The results showed that all ODS steels developed high-density dislocation loops under irradiation, whilst significant void formation was not observed. Comparative analysis of irradiated and unirradiated samples revealed that irradiation had no significant effect on the chemical composition or thickness of the oxide scales formed by the subsequent molten lead corrosion. Among the five ODS steels, the 9Cr0.5Si4.5Al-ODS steel formed a protective Al2O3 scale due to the addition of 4.5% Al and its fine-grained structure. In contrast, the other four ODS steels developed relatively thicker duplex oxide scales.

Key wordsODS steel    Fe-ion irradiation    liquid lead    corrosion    irradiation-affected corrosion
收稿日期: 2025-04-11      32134.14.1005.4537.2025.116
ZTFLH:  TG174  
基金资助:国家重点研发计划(2020YFB1902103)
通讯作者: 郭少强,E-mail:guos2019@xjtu.edu.cn,研究方向为核材料腐蚀与核燃料循环
作者简介: 杜 乾,男,2001年生,博士生
SampleCrSiAlZrWVFe
9Cr0.5Si10.690.534--1.390.17Bal.
9Cr0.5Si4.5Al10.150.3884.59-1.390.17Bal.
9Cr0.5Si4.5Al0.6Zr10.440.4944.790.4351.720.18Bal.
12Cr1Si0.5Zr11.990.971.350.3711.69-Bal.
12Cr2Si0.5Zr11.81.492.020.3251.67-Bal.
表 1  5种ODS钢的化学成分 (mass fraction / %)
图1  SRIM计算3.5 MeV Fe离子在ODS钢内部的辐照损伤深度分布和Fe离子束沉积浓度分布
图2  5种ODS钢的取向分布图(IPF)
图3  明场相欠聚焦和过聚焦模式下的孔洞和(110)双束条件下的位错环
图4  9Cr0.5Si-ODS钢在液态铅中腐蚀24 h后氧化膜截面SEM图及EDS元素面分布图
图5  9Cr0.5Si4.5Al-ODS钢在液态铅中腐蚀24 h后氧化膜截面SEM图及EDS元素线分布图
图6  9Cr0.5Si4.5Al0.6Zr-ODS钢在液态铅中腐蚀24 h后氧化膜截面SEM图及EDS元素面分布图
图7  12Cr1Si0.5Zr-ODS钢在液态铅中腐蚀24 h后氧化膜截面SEM图及EDS元素面分布
图8  12Cr2Si0.5Zr-ODS钢在液态铅中腐蚀24 h后氧化膜截面SEM图及EDS元素面分布图
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