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Desorption of Implanted Deuterium in Heavy Ion-Irradiated Zry-2

机译：重离子辐照Zry-2中植入氘的解吸

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To understand the degradation behavior of light water reactor (LWR) fuel-cladding tubes under neutron irradiation, a detailed mechanism of hydrogen pickup related to the point defect formation (i.e., a-component and c-component dislocation loops) and to the dissolution of precipitates must be elucidated. In this study, 3.2 MeV Ni3+ ion irradiation was conducted on Zircaloy-2 samples at room temperature. Thermal desorption spectroscopy is used to evaluate the deuterium desorption with and without Ni3+ ion irradiation. A conventional transmission electron microscope and a spherical aberration-corrected high-resolution analytical electron microscope are used to observe the microstructure. The experimental results indicate that radiation-induced dislocation loops and hydrides form in Zircaloy-2 and act as major trapping sites at lower (400–600 °C) and higher (700–900 °C)-temperature regions, respectively. These results show that the detailed microstructural changes related to the hydrogen pickup at the defect sinks formed by irradiation are necessary for the degradation of LWR fuel-cladding tubes during operation.
机译：要了解中子辐射下轻型水反应器（LWR）燃料包层管的降解行为，与点缺陷形成（即，A-组分和C组分脱位环）和溶解有关的氢拾气器的详细机制沉淀物必须阐明。在本研究中，在室温下在锆瓦罗伊-2样品上进行3.2mEV Ni3 +离子辐射。热解吸光谱用于评估氘解吸和不含Ni3 +离子辐射的氘解吸。传统的透射电子显微镜和球面像差校正的高分辨率分析电子显微镜用于观察微结构。实验结果表明，Zircaloy-2中的辐射诱导的位错环和氢化物形式，分别用作较低（400-600℃）和更高（700-900℃）的高温区域的主要捕获位点。这些结果表明，在操作期间，通过照射形成的缺陷槽的辐射沉积相关的详细微观结构改变是必要的。

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