High-temperature corrosion testing of titanium beryllides in the presence of water vapor and oxygen

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-07-17 DOI:10.1016/j.jnucmat.2024.155294

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Abstract

Beryllium-based intermetallics are promising materials for the blankets of future fusion reactors and have potential applications in other areas of the nuclear industry, such as fission reactor reflectors and space technology. Understanding the high-temperature corrosion behavior of these materials in a noble gas medium containing chemically active impurities is essential for evaluating their suitability and guiding their application.

This study investigates the high-temperature corrosion of titanium beryllide Be₁₂Ti in the form of plate and grinded samples, produced by JSC “Ulba Metallurgical Plant” (Ust-Kamenogorsk, Kazakhstan). The corrosion tests were conducted under non-isothermal vapor-gas mixture (Ar + D₂O or Ar + H₂O flowing atmospheres) purging conditions using thermogravimetric (TG) analysis, differential scanning calorimetry (DSC), and mass-spectrometry of the gas phase.

As a result of the corrosion tests, new experimental data on thermal effects have been obtained, describing the corrosion processes of Be₁₂Ti samples across a wide range of temperatures and various heating rates in the presence of water vapor in the purge gas. The dependencies of sample mass change under heating conditions have been determined, and the characterization results of the samples before and after high-temperature corrosion tests are presented.

Corrosion of titanium beryllides, both for Be₁₂Ti plate and grinded samples, follows similar mechanisms. At around 500 °C, the mass of the samples begins to increase, and hydrogen isotopes are released. The test results indicate that corrosion of titanium beryllides with varying surface inhomogeneities proceeds similarly within the temperature range of 500–900 °C, showing a linear dependence on temperature.

The results revealed significant insights into the oxidation mechanisms and the formation of corrosion products, which are crucial for optimizing the material's performance in fusion reactor environments.

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水蒸气和氧气存在下的铍化钛高温腐蚀试验

铍基金属间化合物是未来聚变反应堆坯料的理想材料，在核工业的其他领域也有潜在应用，如裂变反应堆反射器和空间技术。本研究调查了 "乌尔巴冶金厂 "股份公司（哈萨克斯坦，乌斯季卡缅诺戈尔斯克）生产的铍化钛 Be12Ti 的高温腐蚀情况。腐蚀试验是在非等温汽气混合物（Ar + D2O 或 Ar + H2O 流动气氛）吹扫条件下进行的，使用了热重分析法（TG）、差示扫描量热法（DSC）和气相质谱分析法。腐蚀试验的结果是获得了有关热效应的新实验数据，描述了 Be12Ti 样品在吹扫气体中存在水蒸气的情况下，在宽温度范围和各种加热速率下的腐蚀过程。确定了加热条件下样品质量变化的相关性，并介绍了高温腐蚀试验前后样品的表征结果。在 500 °C 左右，样品的质量开始增加，氢同位素开始释放。测试结果表明，表面不均匀度不同的铍化钛的腐蚀在 500-900 ℃ 的温度范围内进行得相似，与温度呈线性关系。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.