极低放废物近地表处置的环境安全评价方法研究  

Technical Methods of Evaluation of Near-surface Disposal of Very Low Level Radioactive Waste

作　　者：滕彦国[1,2] 左锐[1,2] 王金生[1,2] 

机构地区：[1]北京师范大学水科学研究院,北京100875 [2]地下水污染控制与修复教育部工程研究中心,北京100875

出　　处：《矿物岩石地球化学通报》2011年第1期59-64,共6页Bulletin of Mineralogy, Petrology and Geochemistry

基　　金：国家自然科学基金资助项目(40773055)

摘　　要：放射性废物处置是当前严峻的环保问题之一,从经济、安全和高效角度出发,将极低放废物从中、低放废物中分离出来单独处置,对核废物的管理与处置具有重要意义。本文以我国西南某极低放废物备选处置场为研究对象,系统分析了处置的相关技术方法,重点研究了屏障技术和环境安全评价方法及其应用。针对拟建在古泥石流体山区山顶上的处置场,选取核素90Sr作为处置对象,选用盆状屏障式处置库,估算产生的核素90Sr的总活度和比活度。选用筛分的颗粒d<1 mm的介质作为屏障材料,厚度为0.5 m,批试验结果显示上述材料对90Sr的吸附效果明显;模拟计算结果显示核素90Sr在50 a内被完全阻滞在包气带中,可以达到安全处置废物的要求。Radioactive waste disposal is one of the most difficult environmental problems worldwide,and has been a hotspot in the field of pollution control and remediation.In order to economically and efficiently dispose radioactive wastes,very low level radioactive waste（VLLW） is separated from low and intermediate levels waste,and the bulk VLLW could be disposed in the disposal site without any special engineering barrier.This approach not only substantially saves disposal costs but also meets the public laws on the environment.Therefore,it is very important for disposal and management of radioactive waste.This paper developed and systemically analyzed several relevant techniques at a VLLW disposal site in the southwestern China,and carefully studied the barrier and technical methods of evaluation.The disposal site is sited on a hilltop of debris flow.In this study,a repository with barrier was selected,90Sr was selected as a typical nuclide,and the releasing concentration was calculated by a given model.The fine particle（d1 mm） was used as barrier material of the repository with the thickness of 0.5 m.The sorption and migration characteristics were measured by batch and column experiments,and the results reflected the material has a good sorption capacity for 90Sr,and the nuclide,90Sr,was completely retarded in the unsaturated zone.

关 键 词：极低放废物 处置 90Sr 屏障 评价方法 

分 类 号：TL942.1[核科学技术—辐射防护及环境保护]