放射性废石墨的处理处置现状  

Research Progress in Treatment and Disposal of Radioactive Graphite Waste

作　　者：郑博文[1] 李晓海[1] 周连泉[1] 王培义[1] 杨丽莉[1] 褚浩然[1] 

机构地区：[1]中国辐射防护研究院,太原030006

出　　处：《辐射防护通讯》2012年第3期32-37,共6页Radiation Protection Bulletin

摘　　要：石墨反应堆退役产生大量放射性废石墨,需要处理后处置。废石墨处理技术主要有焚烧、蒸汽热解、水泥固化、自蔓延固化等,只有焚烧和蒸汽重整热解技术可以实现大幅减容。尽管废石墨的处置存在多种观点,但由于废石墨含有大量长寿命核素,只有深地质处置才能确保安全,然而废石墨数量庞大,处置前的大幅减容是必须的。A large quantity of radioactive graphite waste has been produced from decommissioning of nuclear reactors, and required treatment and conditioning before their disposal, The radioactive graphite waste treatment technologies mainly include incineration, steam pyrolysis, cement immobilization and self-proagating synthesis. Only incineration and steam pyrolysis can reduce the volume of graphite waste greatly. Although there are several opinions for disposal of graphite waste, only the deep＇ geological disposal is able to ensure its safety because the graphite waste contains long-lived radionuelides. The quantity of graphite waste is so large that reduetion of volume is necessary before disposal.

关 键 词：放射性废物 石墨 处理 处置 

分 类 号：TL941[核科学技术—辐射防护及环境保护]