摘要
高放废物的妥善处置是核能可持续发展的前提,在国际范围内受到高度重视,地质处置是普遍接受的方案。高放废物模拟地质处置研究平台由25套模拟多重屏障系统及其共用的低氧环境构成,可以模拟多种不同处置条件下的核素浸出情况。完成部分系统的装填运行。结果表明,多种元素的浸出受到了多重屏障的抑制,并随着时间的推移浸出浓度趋于稳定;不同的处置温度、玻璃体类型、围岩类型、膨润土含素玻璃粉均对重要核素的浸出有显著影响;多种包装材料的耐蚀性能差异显著。下一步实验中,根据现有的研究结果,对玻璃体、膨润土、包装材料等的装填进行优化,对取样系统进行改进,完善总体的实验方案,研究多种处置条件对元素的浸出影响。
The proper disposal of high-level radioactive waste is the premise of the sustainable development of nuclear industry,and highly regarded across the globe.Geological disposal has been universally accepted.A research platform for simulating geological disposal conditions was established,which includes 25 systems simulating the multi-barrier circumstances and a shared low oxygen case.Some systems have been filled and operated.The results shew that the leaching of many elements was restrained and the leaching concentration would be steady as time extended;the simulation discovered that disposal temperature,glass form,host rock type,and simulation glass powder in bentonite had notable effects on the leaching of important elements;and the corrosion resistance of several package materials differed significantly.In the further experiments,the filling of glass,bentonite,and package materials will be optimized,and the sampling system will be modified so as to improve the overall experimental scheme and study the effects of disposal factors on the leaching of elements.
出处
《世界核地质科学》
CAS
2017年第1期54-62,共9页
World Nuclear Geoscience
关键词
高放废物
地质处置
研究平台
浸出浓度
high-level radioactive waste
geological disposal
research platform
leaching concentration
