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首页> 外文期刊>Nuclear Instruments & Methods in Physics Research. B, Beam Interactions with Materials and Atoms >Microstructure analysis of Kr~+ irradiation and post-irradiation corrosion of modified N36 zirconium alloy
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Microstructure analysis of Kr~+ irradiation and post-irradiation corrosion of modified N36 zirconium alloy

机译：改性N36锆合金的Kr〜+辐照及辐照后腐蚀的组织分析

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摘要

The irradiation behaviors and corrosion properties of a modified N36 zirconium alloy with the composition of Zr-0.8Sn-1Nb-0.3Fe, developed by Nuclear Power Institute of China, were investigated by transmission electron microscopy and focused ion beam. The polished samples were irradiated by 400 keV Kr~+ ions up to 25 dpa at 360 °C using a NEC 400 kV ion implanter. The as-received and irradiated samples were corroded for 14 days at the water-vapor environment with 10.3 MPa and 400 °C. The krypton gas bubbles were formed in zirconium matrix and their size was increased with increasing ion dose. Meanwhile, a model that related with gas bubble size and displacement damage had been established. After the corrosion, a layer composed of zircona with different stoichiometric composition was formed on the sample surface. The higher the displacement damage was, the thicker the corrosion layer would be. An empirical equation between oxide thickness and displacement damage was provided. From sample surface to matrix inner, the oxygen content was decreased with increasing corrosion depth. Correspondingly, the zircona was changed from ZrO_2 with monoclinic structure on the sample surface to the mixtures of ZrO_2 with tetragonal structure and ZrO_2 with monoclinic structure in the middle of corrosion layer, and then to ZrO_2 with tetragonal structure near alloy matrix.
机译：用透射电子显微镜和聚焦离子束研究了由中国核动力研究所研制的Zr-0.8Sn-1Nb-0.3Fe组成的改性N36锆合金的辐照行为和腐蚀性能。使用NEC 400 kV离子注入机，在360°C下以高达25 dpa的400 keV Kr〜+离子照射抛光过的样品。接收和辐照的样品在水蒸气环境为10.3 MPa和400°C的环境下腐蚀了14天。 z气泡在锆基体中形成，其大小随着离子剂量的增加而增加。同时，建立了与气泡尺寸和位移损伤有关的模型。腐蚀后，在样品表面上形成了由具有不同化学计量组成的氧化锆组成的层。位移损伤越高，腐蚀层越厚。提供了氧化物厚度和位移损伤之间的经验方程。从样品表面到基质内部，氧含量随腐蚀深度的增加而降低。相应地，氧化锆从样品表面的单斜结构的ZrO_2变为腐蚀层中间的单方结构的ZrO_2和单斜结构的ZrO_2的混合物，然后在合金基体附近转变为四方结构的ZrO_2。

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