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γ辐射和高温对放射性废物水泥固化体强度的影响

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Abstract:

为了处理高活性、放热性C级放射性废弃物,在比利时通常采用圆柱体混凝土“超级容器”作为基本途径。“超级容器”是合成的废弃物包,废弃物由碳钢包裹组成,碳钢被波特兰水泥制成的“缓冲器”包裹。自密实混凝土作为一种特殊类型的混凝土,正被考虑用来制备“缓冲器”。一旦“缓冲器”被浇筑并且硬化程度很高时,放射性废弃物就被包裹在“缓冲器”内,存在的缝隙可以采用新拌灌浆料填充(例如自密实砂浆)。用盖子将“超级容器”密封后应用于“超级容器”的混凝土层,即混凝土缓冲器、灌浆料及盖子在硬化期间(灌浆料)与硬化之后(“缓冲器”与盖子)将暴露在废弃物热场与辐射场内。因此,需要解决2个主要的问题1)γ射线(α与β射线被碳钢包裹层阻断,中子的影响可以忽略)对灌浆料硬化强度的影响;2)温度升高(从20℃升高到105℃)对硬化试件强度的影响。为了证实强度是否损失并确定强度损失后的主要机理,采用荧光显微镜,在砂浆或混凝土薄片的截面上直接分析毛细孔隙率。

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