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首页> 外文期刊>Metals >Results of High-Temperature Heating Test for Irradiated U-10Zr(-5Ce) with T92 Cladding Fuel
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Results of High-Temperature Heating Test for Irradiated U-10Zr(-5Ce) with T92 Cladding Fuel

机译:T92包覆燃料对U-10Zr(-5Ce)辐照的高温加热试验结果

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A microstructure observation using an optical microscope, SEM and EPMA was performed for the irradiated U-10Zr and U-10Zr-5Ce fuel slugs with a T92 cladding specimen after a high-temperature heating test. Also, the measured eutectic penetration rate was compared with the value predicted by the existing eutectic penetration correlation being used for design and modeling purposes. The heating temperature and duration time for the U-10Zr/T92 specimen were 750 °C and 1 h, and those for the U-10Zr-5Ce/T92 specimen were 800 °C and 1 h. In the case of the U-10Zr/T92 specimen, the migration phenomena of U, Zr, Fe, and Cr as well as the Nd lanthanide fission product were observed at the eutectic melting region. The measured penetration rate was similar to the value predicted by the existing eutectic penetration rate correlation. In addition, when comparing with measured eutectic penetration rates for the unirradiated U-10Zr fuel slug with FMS (ferritic martensitic steel, HT9 or Gr.91) cladding specimens which had been reported in the literature, the measured eutectic penetration rate for the irradiated fuel specimen was higher than that for the unirradiated U-10Zr specimen. In the case of the U-10Zr-5Ce/T92 specimen in which there had been a gap between the fuel slug and cladding after the irradiation test, the eutectic melting region was not found because contact between the fuel slug and cladding did not take place during the heating test.
机译:高温加热试验后,对带有T92熔覆样品的U-10Zr和U-10Zr-5Ce燃料块进行光学显微镜,SEM和EPMA显微组织观察。同样,将测得的共晶渗透率与现有的共晶渗透相关性所预测的值进行比较,该相关性已用于设计和建模目的。 U-10Zr / T92标本的加热温度和持续时间为750°C和1 h,U-10Zr-5Ce / T92标本的加热温度和持续时间为800°C和1 h。在U-10Zr / T92样品的情况下,在共晶熔融区观察到了U,Zr,Fe和Cr以及Nd镧系元素裂变产物的迁移现象。测得的渗透率类似于现有共晶渗透率相关性预测的值。此外,与文献中已报道的采用FMS(铁素体马氏体钢,HT9或Gr.91)熔覆样品的未辐照U-10Zr燃料块的共晶渗透率的测量值相比,辐照燃料的共晶渗透率的测量值标本高于未辐照的U-10Zr标本。在U-10Zr-5Ce / T92样品的情况下,辐照试验后的燃料块和包层之间存在间隙,未发现共晶熔化区域,因为燃料块和包层之间未发生接触在加热测试中。

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