放射性废树脂湿法氧化处理过程中对反应器材料腐蚀行为的研究

doi:10.27045/j.1000-8187.202604007

摘要/Abstract

摘要： 湿法氧化法处理放射性废树脂需在强酸性、强氧化性(羟基自由基主导)的工况下进行连续处理,其反应器材料的耐蚀性是工程应用的核心关键。针对316L不锈钢、Incoloy 825合金及Alloy 31合金三种候选反应器合金材料,采用质量损失法结合扫描电子显微镜(SEM)、能谱仪(EDS)及金相显微镜等表征手段,综合研究合金的腐蚀程度、微观形貌与腐蚀产物特征,揭示其腐蚀机制。结果表明,腐蚀168 h后,316L不锈钢、Alloy 31合金和Incoloy 825合金的均匀腐蚀速率分别为0.022、0.001和2.132 mm/a,前两者的耐腐蚀性显著优于Incoloy 825合金;通过提高合金中铬、钼、氮元素的含量,可进一步提升其耐蚀性能;按反应釜壁厚减半为报废依据估算,Incoloy 825合金使用寿命不足2年,而Alloy 31合金与316L不锈钢均超过40年,可满足长期安全服役要求。本文为放射性废树脂湿法氧化技术的材料优化与应用拓展提供了技术支撑。

关键词: 湿法氧化, 放射性废树脂, 耐腐蚀性, Incoloy 825合金, Alloy 31合金, 316L不锈钢

Abstract: The treatment of radioactive spent resin by wet oxidation requires continuous processing of radioactive materials under strongly acidic and oxidizing conditions (dominated by hydroxyl radicals). The corrosion resistance of the reactor materials becomes a core concern in engineering applications. In this paper, the corrosion behaviors of three candidate reactor alloys, namely 316L, Incoloy 825, and Alloy 31, were systematically investigated under the wet oxidation conditions of spent resin. The corrosion degree, micromorphology, and characteristics of corrosion products of the alloys were characterized using the weight loss method combined with scanning electron microscopy (SEM), energy dispersive spectrometry (EDS), and metallographic microscopy, and the corrosion mechanism was revealed. The results demonstrate that after 168 h of exposure, the uniform corrosion rates of 316L, Alloy 31, and Incoloy 825 were 0.022, 0.001, and 2.132 mm/a, respectively, demonstrating that the former two alloys possessed markedly superior corrosion resistance to Incoloy 825. Further enhancement of corrosion performance could be achieved by increasing the contents of chromium, molybdenum, and nitrogen in the alloy matrices. On the basis of the mandatory retirement criterion of wall thickness reduction by half, the estimated service life of Incoloy 825 was less than 2 years, whereas both Alloy 31 and 316L exceeded 40 years, thereby meeting the requirements for long-term safe service. This study provides technical support for the optimization and application expansion of materials used in wet oxidation technology for radioactive waste resins.

Key words: wet-oxidation, radioactive spent resin, corrosion resistance, Incoloy 825, Alloy 31, 316L stainless steel

中图分类号:

TL941

薛海龙, 闫晓俊, 高泽全, 王志伟, 高超, 郭喜良, 闫文付. 放射性废树脂湿法氧化处理过程中对反应器材料腐蚀行为的研究[J]. 辐射防护, 2026, 46(4): 340-352.

XUE Hailong, YAN Xiaojun, GAO Zequan, WANG Zhiwei, GAO Chao, GUO Xiliang, YAN Wenfu. Corrosion of the reactor in the wet-oxidation of radioactive spent resin[J]. RADIATION PROTECTION, 2026, 46(4): 340-352.

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