硼硅酸盐玻璃
放射分析
放射性废物
辐照
材料科学
浸出(土壤学)
锕系元素
高水平废物
耐久性
乏核燃料
辐射
放射化学
膨润土
废物管理
核化学
环境科学
化学
冶金
化学工程
复合材料
核物理学
土壤科学
工程类
土壤水分
物理
作者
Viktor I. Malkovsky,S. V. Yudintsev,Michael I. Ojovan,В. А. Петров
摘要
Self-irradiation can affect durability of glasses used to immobilize high-level nuclear waste (HLW). The stability of glasses can also be indirectly affected by the radiolytic changes in contact water leading to decrease in its pH although this is unlikely to occur for disposal systems where the interaction of groundwater with glass is delayed to times when radiation dose rates are decreased to levels insignificant to cause such effects. Besides, interaction of the water influenced by radiation with other repository protective elements (container and bentonite) will suppress the radiolytic changes. Literature analysis shows practical absence or very weak effect of self-irradiation on structure and characteristics of borosilicate glasses with typical content of nuclear waste. Data for aluminophosphate glass used in Russia have showed that, after γ -irradiation with a dose of 6.2·10 7 Gy, the leaching rates of elements were decreased approximately twice relatively to pristine samples.
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