ti - 2级溶解剂材料在含氟硝酸中的腐蚀行为

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-04-13 DOI:10.1016/j.jnucmat.2025.155833

R. Priya , K. Kaliraj , S. Ningshen

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引用次数: 0

摘要

在水基提取钚铀回收（PUREX）后处理方法中，ti - 2级作为核废料后处理的候选溶解剂材料。氟化物用于增强高燃耗燃料的溶解。然而，已知氟化物会严重降低商业纯Ti （CP-Ti）在硝酸后处理中的腐蚀行为。本文主要通过电化学和沸腾硝酸研究，了解了ti级2溶解体材料在含有氟离子的硝酸介质中，在11.5 M和1 M HNO3条件下，有和没有络合剂Al(NO3)3的腐蚀行为。动电位极化结果表明，在11.5 M HNO3 + 0.05 M NaF溶液中，与11.5 M HNO3相比，活性腐蚀电位较低，耐蚀性较差，无源电流密度较高。在11.5 M HNO3中，随着温度的升高和氟浓度的增加，耐蚀性能的下降更为明显。在这种酸浓度下，在所有条件下都观察到自发钝化行为。相比之下，1 M HNO3中氟的存在导致了主-被动转变，其特征是腐蚀电位的负移动和被动电流密度的增加。研究发现，在含氟化物和络合剂的硝酸介质中，钛的缓蚀效果很好。沸腾硝酸试验中，1 M HNO3 + 0.05 M NaF溶液的腐蚀速率明显高于11.5 M HNO3 + 0.05 M NaF溶液。SEM， XPS和AFM分析支持这些发现。提出了氟化物在1 M和11.5 M硝酸浓度下影响CP-Ti耐蚀性的腐蚀机理。此外，本研究为在涉及硝酸和氟化物的核后处理环境中使用CP-Ti作为溶解剂材料提供了有价值的见解。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

Corrosion behavior of Ti-Grade2 dissolver material in nitric acid containing fluoride ions

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Corrosion behavior of Ti-Grade2 dissolver material in nitric acid containing fluoride ions

The Ti-grade2 is used as the candidate dissolver material for reprocessing the nuclear-spent fuels in the aqueous-based Plutonium Uranium Recovery by EXtraction (PUREX) reprocessing method. Fluoride is used to enhance the dissolution of high-burn-up fuel. However, fluoride is known to severely degrade the corrosion behaviour of commercially pure Ti (CP-Ti) in reprocessing nitric acid. The present work focuses on understanding the corrosion behaviour of Ti-grade2 dissolver material in nitric acid medium containing fluoride ions with and without complexing agent Al(NO₃)₃ at 11.5 M and 1 M HNO₃ by electrochemical and boiling nitric acid studies. The potentiodynamic polarization results revealed inferior corrosion resistance with active corrosion potential and higher passive current density in 11.5 M HNO₃ + 0.05 M NaF compared to 11.5 M HNO₃. Moreover, the deterioration of corrosion resistance was more pronounced with increasing temperature and fluoride concentration in 11.5 M HNO₃. Spontaneous passivation behavior was observed under all conditions tested in this acid concentration. In contrast, the presence of fluoride in 1 M HNO₃ induced an active-passive transition, characterized by a negative shift in corrosion potential and an increase in passive current density. Corrosion mitigation of titanium was found to be effective in a nitric acid medium containing fluoride and a complexing agent. A significantly higher corrosion rate was observed in 1 M HNO₃ + 0.05 M NaF compared to 11.5 M HNO₃ + 0.05 M NaF during the boiling nitric acid test. SEM, XPS, and AFM analyses supported these findings. The corrosion mechanism by which fluoride influences the corrosion resistance of CP-Ti in both 1 M and 11.5 M nitric acid concentrations was proposed. Additionally, this study provides valuable insights for the use of CP-Ti as a dissolver material in a nuclear reprocessing environment involving nitric acid and fluoride.

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来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.