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A facility for studying corrosion via in-situ Raman spectroscopy
Journal of Nuclear Materials ( IF 3.1 ) Pub Date : 2024-03-27 , DOI: 10.1016/j.jnucmat.2024.155053
V.S. Ramsundar , K. Daub , S.Y. Persaud , M.R. Daymond

Several in-core components in nuclear power systems are exposed to high-temperature water in the presence of radiation fields. The dynamic effect of radiation and water chemistry on material performance in these environments is not well understood partly due to significant experimental challenges. A facility consisting of a high temperature/pressure corrosion loop coupled with Raman spectroscopy has been commissioned to examine material behaviour in more realistic reactor conditions. The Raman component of the facility has been validated by conducting experiments with both pre-oxidized, and freshly abraded SS304L in water at 80 °C and 300 °C. Testing in water also revealed the detection limitations of the system. The assessment reported in this paper highlights the capabilities to perform degradation studies of key nuclear components by conducting characterization of materials exposed to high temperature water via Raman spectroscopy, thereby providing chemical, structural and semi-quantitative kinetic information.

中文翻译:

通过原位拉曼光谱研究腐蚀的设施

核电系统中的几个核心部件在辐射场的情况下暴露在高温水中。由于重大的实验挑战,辐射和水化学对这些环境中材料性能的动态影响尚未得到很好的理解。由高温/高压腐蚀回路与拉曼光谱相结合组成的设施已被委托用于检查更真实的反应器条件下的材料行为。该设施的拉曼组件已通过在 80 °C 和 300 °C 水中进行预氧化和新研磨的 SS304L 实验进行验证。水中测试还揭示了系统的检测局限性。本文报告的评估强调了通过拉曼光谱对暴露于高温水的材料进行表征来进行关键核部件降解研究的能力,从而提供化学、结构和半定量动力学信息。
更新日期:2024-03-27
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