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Thermal behaviour of caesium implanted in UO2: A comparative study with the xenon behaviour
Journal of Nuclear Materials ( IF 2.8 ) Pub Date : 2020-09-11 , DOI: 10.1016/j.jnucmat.2020.152520
C. Panetier , Y. Pipon , C. Gaillard , N. Moncoffre , T. Wiss , D. Mangin , O. Dieste , B. Marchand , R. Ducher , R. Dubourg , T. Epicier , L. Raimbault

Xenon and caesium are among the most impacting fission products when studying the nuclear fuel: xenon for its role on the fuel rod thermomechanical behaviour during reactor operation and caesium in the case of atmospheric radioactive release during an accident in a nuclear power plant. This paper focuses on the comparison of caesium and xenon thermal behaviour in polycrystalline uranium dioxide (UO2) pellets. Caesium-133 or xenon-136 stable isotopes were introduced in depleted UO2 samples by ion implantation at a maximum concentration of 0.08 at% at a depth of around 140 nm below the sample surface. Annealing under reducing atmosphere (Ar/H2 5 %) was performed at 1000 °C or 1600 °C, which corresponds respectively to a representative temperature during nuclear reactor operation (at the centre of the fuel pellets) and during an accident. The caesium migration in UO2 was investigated by Secondary Ion Mass Spectrometry and compared to the thermal behaviour of xenon in UO2 at 1600 °C. Transmission Electron Microscopy was performed in order to characterise UO2 microstructure before and after annealing. The results indicate that caesium has a different behaviour than xenon with which it is often compared for its release from the nuclear fuel. In particular, we highlight a difference between the growth kinetics of caesium and of xenon bubbles at 1600 °C which can be correlated to the availability of thermal vacancies in UO2 and to the different ability of Xe and Cs atoms for thermal resolution.



中文翻译:

铯在UO 2中的热行为:与氙气行为的比较研究。

氙和铯是研究核燃料时影响最大的裂变产物:氙在反应堆运行期间对燃料棒热机械行为的作用,以及在核电站事故期间在大气中释放铯的铯。本文着重比较多晶二氧化铀(UO 2)颗粒中铯和氙的热行为。通过离子注入,在样品表面以下约140 nm处,以最大浓度0.08 at%的离子注入将铯133或氙136稳定同位素引入到贫化的UO 2样品中。在还原气氛下退火(Ar / H 25%)是在1000°C或1600°C下执行的,这分别对应于核反应堆运行期间(在燃料芯块的中心)和事故期间的代表温度。通过二次离子质谱研究了铯在UO 2中的迁移,并与氙在1600°C下在UO 2中的热行为进行了比较。进行透射电子显微镜以表征UO 2退火前后的显微组织。结果表明铯与氙的行为不同,经常将其与从核燃料中释放的氙进行比较。特别是,我们着重指出了铯和氙气气泡在1600°C的生长动力学之间的差异,这可能与UO 2中热空位的可用性以及Xe和Cs原子的热分解能力不同有关。

更新日期:2020-09-15
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