Self-irradiation effect on thermal conductivity of (Pu_0.91Cm_0.09)O₂

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• 作者：Tsuyoshi Nishi ; ^{nishi.tsuyoshi@jaea.go.jp} ; Masahide Takano ; Mitsuo Akabori ; Yasuo Arai
• 刊名：Journal of Nuclear Materials
• 出版年：2013
• 出版时间：February, 2013
• 年：2013
• 卷：433
• 期：1-3
• 页码：531-533
• 全文大小：167 K

文摘

To clarify the dependence of thermal conductivity on storage time of MA containing oxide fuel, the thermal diffusivity of (Pu_0.91Cm_0.09)O₂ was measured at 473, 523 and 573 K by a laser flash method using the sample stored for 48, 264, 504, and 960 h. The heat capacity was measured by a drop calorimetry to derive the thermal conductivity. It was confirmed that the degradation of the thermal conductivity was attributed to the accumulation of lattice defects caused by self-irradiation, because the dependence of thermal conductivity on storage time could be approximated by the equation used for self-irradiation lattice expansion model.