Kieran Lynch , Ömer Koç , Graeme Greaves , Alexander Carruthers , Mia Maric , Michael Preuss , Aidan Cole-Baker , Philipp Frankel , Joseph Robson
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引用次数: 0
摘要
众所周知，Zircaloy-2 和 -4 中的 Zr（Fe，Cr）2 第二相颗粒（SPPs）会在辐照下发生非晶化和溶解。在本研究中，我们使用透射电子显微镜（TEM）在 320 °C、600 keV Ar2+辐照条件下，将样品置于 13 和 24 dpa 两种不同的剂量下，对它们的演变进行了原位研究。利用扫描透射电子显微镜和能量色散 X 射线光谱（STEM-EDX）对辐照前后的样品进行了全面的表征，从而检测到沉淀化学的微妙变化。在两种剂量下，SPPs 都完全非晶化，同时向周围基质释放铁。在 SPP 内核中，铁/铬比下降，而在与基体的界面上，铁/铬比上升，这是界面上弹道混合和铁向外扩散的结果。虽然发现铁沿 c 轴方向比沿 a 轴方向扩散得更远，但没有观察到位错环的排列或溶质与基体中缺陷的偏析。
Evolution of Zr(Fe,Cr)2 second phase particles in Zircaloy-2 under heavy ion irradiation
The Zr(Fe,Cr)2 second phase particles (SPPs) found in Zircaloy-2 and -4 are known to amorphize and dissolve under irradiation. In the present work, their evolution has been studied in situ in a transmission electron microscope (TEM) under 600 keV Ar2+ irradiation at 320 °C, taking samples to two different doses of 13 and 24 dpa. Using scanning transmission electron microscopy coupled with energy-dispersive X-ray spectroscopy (STEM-EDX), the samples were thoroughly characterised before and after irradiation, allowing subtle changes in precipitate chemistry to be detected. At both doses the SPPs were fully amorphous, with an accompanying release of Fe to the surrounding matrix. The Fe/Cr ratio was seen to decrease in the SPP core and increase at the interface with the matrix, a result of ballistic mixing across the interface coupled with outward diffusion of Fe. No alignment of dislocation loops or segregation of solute to defects in the matrix was observed, although Fe was found to diffuse further along the c-axis direction compared to the a-axis direction.
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.
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