论文标题
溶质点缺陷相互作用,耦合的扩散和辐射诱导的FCC镍中的隔离
Solute-point defect interactions, coupled diffusion, and radiation induced segregation in fcc nickel
论文作者
论文摘要
暴露于辐照的材料中溶质的辐射诱导的分离(RIS)是一个众所周知的问题。它通过偏爱辐射引起的降解现象(例如硬化和脆化)来影响核反应堆核心成分的寿命。在这项工作中,检查了以面部为中心(FCC)NI-X(X = Cr,Fe,Ti,Ti,Mn,Si,p)稀释二元合金的RIS趋势。目的是研究实验观察到的隔离背后的驱动力和动力学机制。通过从头开始计算,确定了点 - 缺陷稳定性以及与溶质的相互作用,以及迁移能和尝试频率。然后在平均场框架中计算传输和扩散系数,以获取合金中溶质缺陷动力学耦合的完整图片。结果表明,除了CR外,所有考虑的溶质都宁愿空位介导的空位介导,而不是在热和辐射诱导的迁移过程中的间隙介导的扩散。另一方面,CR优先迁移在混合式铃铛配置中。在这里显示P和Si富含P和Si,在材料照射期间,Fe和Mn将在水槽中耗尽。另一方面,Ti和Cr在较低温度下的富集与较高温度范围的耗尽之间显示了一个交叉。将这项工作的结果与以前的以人体中心(BCC)为中心的研究进行了比较,并在奥氏体合金中的RIS中进行了讨论。
Radiation-induced segregation (RIS) of solutes in materials exposed to irradiation is a well-known problem. It affects the life-time of nuclear reactor core components by favouring radiation-induced degradation phenomena such as hardening and embrittlement. In this work, RIS tendencies in face-centered cubic (fcc) Ni-X (X = Cr, Fe, Ti, Mn, Si, P) dilute binary alloys are examined. The goal is to investigate the driving forces and kinetic mechanisms behind the experimentally observed segregation. By means of ab initio calculations, point-defect stabilities and interactions with solutes are determined, together with migration energies and attempt frequencies. Transport and diffusion coefficients are then calculated in a mean-field framework, to get a full picture of solute-defect kinetic coupling in the alloys. Results show that all solutes considered, with the exception of Cr, prefer vacancy-mediated over interstitial-mediated diffusion during both thermal and radiation-induced migration. Cr, on the other hand, preferentially migrates in a mixed-dumbbell configuration. P and Si are here shown to be enriched, and Fe and Mn to be depleted at sinks during irradiation of the material. Ti and Cr, on the other hand, display a crossover between enrichment at lower temperatures, and depletion in the higher temperature range. Results in this work are compared with previous studies in body-centered cubic (bcc) Fe, and discussed in the context of RIS in austenitic alloys.