Abstract: 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 (d<1 mm) was used as barrier material of the repository with the thickness of 0. 5 m. The sorption and migrat ion 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.
Key words: VLLW; disposal; 90Sr; barrier material; technical methods
Bulletin of Mineralogy, Petrology and Geochemistry Vol. 30, No.1, 2011, page 59-64
(Source from http://www.cnki.com.cn/)
