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arXiv 2202.03641cond-mat.mtrl-sci
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Fe-Ti-Y-O体系在中子辐照下纳米氧化物析出及其相关稳定性的动力学蒙特卡罗模拟

Kinetic Monte Carlo Modelling of Nano-oxide Precipitation and its Associated Stability under Neutron Irradiation for the Fe-Ti-Y-O system

Christopher Nellis, Celine Hin

AI总结:

本文开发了一种动力学蒙特卡罗模型,研究Fe-Ti-Y-O体系中纳米氧化物在晶界处的析出行为及其中子辐照稳定性,揭示了氧化物尺寸与剂量率的反比关系以及晶界附近氧化物更易溶解的规律。

摘要:

在开发核材料的过程中,预测其在跨越数十年的长期辐照条件下的行为是一项重大挑战。我们开发了一种新颖的动力学蒙特卡罗(KMC)模型,用于研究纳米结构铁素体合金(NFA)中沿晶界的Y-Ti-O氧化物析出行为。该模型还评估了氧化物对中子辐照的响应,甚至模拟了反应堆部件所期望的长dpa范围内的辐射损伤水平。我们的模拟研究了在1023 K、1123 K和1223 K热处理过程中,温度和晶界汇对一种类12YWT合金氧化物特征的影响。模拟中观察到的氧化物特征与现有文献吻合良好。此外,发现晶界对析出的影响很小。所得的氧化物构型和位置被用于后续模拟,在这些模拟中,将它们暴露于模拟中子辐照下,在673 K、773 K和873 K三个温度下,以10^(-3)、10^(-4)和10^(-5) dpa/s的剂量率,累积总剂量达到8 dpa。这证明了氧化物尺寸与剂量率之间预期的反比关系。在873 K和10^(-3) dpa/s条件下进行的长期辐照模拟被推进到66 dpa,发现晶界附近的氧化物更容易溶解。此外,我们对一种类14YWT合金进行了辐照模拟,以重现中子辐照实验的结果。类14YWT合金中较大的氧化物没有溶解,并表现出与实验结果相似的稳定性。

英文摘要:

While developing nuclear materials, predicting their behavior under long-term irradiation regimes spanning decades poses a significant challenge. We developed a novel Kinetic Monte Carlo (KMC) model to explore the precipitation behavior of Y-Ti-O oxides along grain boundaries within nanostructured ferritic alloys (NFA). This model also assessed the response of the oxides to neutron irradiation, even up simulated radiation damage levels in the desired long dpa range for reactor components. Our simulations investigated how temperature and grain boundary sinks influenced the oxide characteristics of a 12YWT-like alloy during heat treatments at 1023 K, 1123 K, and 1223 K. The oxide characteristics observed in our simulations were in good agreement with existing literature. Furthermore, the impact of grain boundaries on precipitation was found to be minimal. The resulting oxide configurations and positions were used in subsequent simulations that exposed them to simulated neutron irradiation to a total accumulated dose of 8 dpa at three temperatures: 673 K, 773 K, and 873 K, and at dose rates of 10^(-3), 10^(-4), and 10^(-5) dpa/s. This demonstrated the expected inverse relationship between oxide size and dose rate. In a long-term irradiation simulation at 873 K and 10^(-3) dpa/s was taken out to 66 dpa and found the oxides in the vicinity of the grain boundary were more susceptible to dissolution. Additionally, we conducted irradiation simulations of a 14YWT-like alloy to reproduce findings from neutron irradiation experiments. The larger oxides in the 14YWT-like alloy did not dissolve and displayed stability similar to the experimental results.

机构、总结、中文摘要均由AI分析而来,可能存在错误,请以论文正文为准。

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