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作 者:林美琼[1] 胥胜利[2] 李永德[3] 魏峰[1] 殷奇[1] 范显华[1]
机构地区:[1]中国原子能科学研究院放射化学研究所,北京102413 [2]北京核工程研究院,北京100840 [3]清华大学土木工程系,北京100084
出 处:《核化学与放射化学》2003年第3期134-137,共4页Journal of Nuclear and Radiochemistry
摘 要:以134Cs和85,89Sr为示踪剂,采用新型的类玻璃水泥材料固化3种模拟废液。液固比为0.45~0.55,混合搅拌5min后灌入直径与高相等的圆柱体模子中,在室温和大气条件下密封养护28d。脱模后的废物固化体完全浸入去离子水中,按照GB7023 86的方法,测定核素浸出率。实验结果表明:134Cs,85,89Sr在第42d的浸出率分别为4.0×10-4,2.0×10-4,6.9×10-4;3.5×10-5,2.3×10-5,7.5×10-5cm/d,满足GB14569.1 93性能要求,优于普通硅酸盐水泥固化体。A novel material——resemble vitrifiable cement for conditioning low and mediate level radioactive waste has been developed. Waste form has been characterized for their physical and chemical performance, phase composition. The cement formulation has been patented. In this experiment the cement is mixed with simulated wastes spiked with 134 Cs and 85,89 Sr by 5 min at least. The Ratio of the waste to the cement is 0.45~0.55. The mixture is packed into cylindrical molds which has the same dimension of diameter and height. The grouts are cured for a period of 28 d in a room temperature curing chamber at an atmospheric pressure. The cured waste form is then completely immersed into deionized water. According to standard GB7023-86, leaching rate of 134 Cs and 85,89 Sr are measured. The result shows that the leaching rate of the species 134 Cs and 85,89 Sr is to be on the order 10 -4 and 10 -5 on the 42 d immersion, respectively and is better than that of commercial cement.
关 键 词:类玻璃水泥固化体 ^134CS ^85 89Sr 浸出率 测定 中低放废液 固化处理 放射性废液
分 类 号:TL941.11[核科学技术—辐射防护及环境保护]
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