论文标题
SN对锆及其Hydrides中广义堆叠断层能量表面的影响
Effect of Sn on generalized stacking fault energy surfaces in zirconium and its hydrides
论文作者
论文摘要
ZR合金燃料覆层中的氢含水是水基核反应堆的主要安全问题。在这里,我们研究了SN形成氢化物内平面缺陷的稳定,SN是甲壳化中使用的主要合金元素。为了解释在实验中观察到的氢化物和平面缺陷的形成,我们进行了原子尺度的从头算计算,重点是与HCP $α$ -ZR和FCC锆氢化物中的溶质相互作用。我们的计算表明,SN浓度的增加会导致$α$ -ZR和氢化物相的堆叠断层的稳定。但是,与其他氢化物相相比,在$α$ -ZR中,SN的溶液焓较低,指示了在ZR Hydride/Matrix界面处的SN耗竭/富集的两个竞争过程。这是通过实验发现来证实的,其中SN被Hydrides驱除,大多被困在界面和平面缺陷处,表明氢化物相内的堆叠断层。我们的系统研究使我们能够了解氢化物阶段溶质的存在和分布,从而更深入了解该合金在其使用寿命中的微观结构演变。
Hydrogen embrittlement in Zr alloy fuel cladding is a primary safety concern for water based nuclear reactors. Here we investigated the stabilisation of planar defects within the forming hydrides by Sn, the primary alloying element of Zircaloy-4 used in the cladding. In order to explain formation of hydrides and planar defects observed in our experiments, we performed atomic-scale ab initio calculations focusing on the solute interactions with generalized stacking faults in hcp $α$-Zr and fcc zirconium hydrides. Our calculations showed that an increase in Sn concentration leads to a stabilisation of stacking faults in both $α$-Zr and hydride phases. However, the solution enthalpy of Sn is lower in the $α$-Zr as compared to the other hydride phases indicative of two competing processes of Sn depletion/enrichment at the Zr hydride/matrix interface. This is corroborated by experimental findings, where Sn is repelled by hydrides and is mostly found trapped at interfaces and planar defects indicative of stacking faults inside the hydride phases. Our systematic investigation enables us to understand the presence and distribution of solutes in the hydride phases, which provides a deeper insight into the microstructural evolution of such alloy's properties during its service lifetime.