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Vitrification of Nuclear Contaminated Lead-Boron Polyethylene

机译:核污染铅硼聚乙烯的玻璃化

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摘要

Lead-Boron Polyethylene (PbBPE) composite formed by diffusing lead and boron carbide powders in the polyethylene is a typical shielding material for radiation protection in nuclear facilities. Cement solidification of contaminated PbBPE could result in the waste volume increase and the radionuclides leaching risk. This study aimed to apply the thermal treatment to reduce the volume of PbBPE and immobilize radionuclides into the stable waste form by turning PbBPE into glass. PE could be pyrolyzed at similar to 450 degrees C, while the residual lead and boron were converted into an undurable lead borate glass at temperature above 900 degrees C. The volume of the waste decreased more than twice after thermal treatment, and the durability of the lead borate glass was enhanced by addition of SiO2. The 7-day Product Consistency Test normalized releases for elements (Pb, B, Co, Sr and Cs) were <1 g/m(2), when 10 wt% SiO2 was added. Glass structure analysis indicated that the enhanced durability resulted from the increased silica tetrahedron and bridging oxygens in the glass network.
机译:铅-硼-聚乙烯(PbBPE)复合材料是一种典型的核设施辐射防护屏蔽材料,由铅和碳化硼粉末在聚乙烯中扩散而成。受污染的PbBPE的水泥固化可能会导致废物量增加和放射性核素的浸出风险。本研究旨在通过热处理来减少PbBPE的体积,并通过将PbBPE转化为玻璃将放射性核素固定为稳定的废物形式。PE可以在类似450℃的温度下热解,而残余的铅和硼在900℃以上的温度下转化为不耐用的硼酸铅玻璃。热处理后,废物的体积减少了两倍以上,并且通过添加SiO2提高了硼酸铅玻璃的耐久性。当添加10 wt%的SiO2时,7天产品一致性试验中元素(Pb、B、Co、Sr和Cs)的标准化释放量<1 g/m(2)。玻璃结构分析表明,玻璃网络中二氧化硅四面体和桥接氧的增加导致了耐久性的提高。

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