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引用次数: 0
摘要
辐照诱导生长是一种恒定体积的形状变化,在某些材料的辐照损伤中可以观察到这种变化,而无需外加应力。为了研究辐照生长现象的微观方面,我们对纯锆样品进行了质子辐照,辐照强度达到了许多 dpa。辐照导致辐照区域的表面形态发生了显著变化,这被认为是 hcp 结构 Zr 各向异性生长行为的结果。电子背散射衍射(EBSD)对辐照表面和横截面通厚平面上产生的局部应变进行了表征。结果发现,局部变形量与两个相邻晶粒之间存在的取向错误程度之间存在相关性。透射电子显微镜(TEM)对辐照诱导的缺陷微观结构进行了表征,显示出〈a〉和〈c〉分量环,与文献中中子辐照产生的分量环相似。最后,在局部晶界上制备了特定部位的聚焦离子束 (FIB) TEM 取出物,以研究局部变形的起源。
Electron microscopy characterization of proton irradiation induced growth in pure Zr
Irradiation induced growth is a constant volume shape change that occurs without externally applied stress that is observed in some materials under irradiation damage. Proton irradiation was carried out on a pure Zr sample to many dpa, to enable investigation of microscale aspects of the irradiation growth phenomenon. Irradiation induced a significant surface morphology change in the irradiated area, which is believed to be the result of the anisotropic growth behavior of the hcp structured Zr. The localized strain that developed was characterized by Electron back scatter diffraction (EBSD), on both the irradiated surface and on a cross sectional through-thickness plane. It was found that there is a correlation between the amount of local deformation and level of misorientation existing between two adjacent grains. The irradiation induced defect microstructure was characterized by transmission electron microscopy (TEM), showing 〈a〉 and 〈c〉 component loops similar to that generated by neutron irradiation in literature. Lastly, site specific focused ion beam (FIB) TEM lift-outs were prepared on local grain boundaries to investigate the origin of the localised deformation.
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.