中国高放废物地质处置研究进展:1985～2004  

Geological disposal of high level radioactive waste in China:Progress during 1985～2004

作　　者：王驹[1] 徐国庆[1] 郑华铃[2] 范显华[3] 王承祖 范智文[5] 

机构地区：[1]核工业北京地质研究院,北京100029 [2]中国核工业集团公司科技部,北京100822 [3]中国原子能科学研究院,北京102413 [4]核工业北京工程设计研究院,北京100084 [5]中国辐射防护研究院,太原030006

出　　处：《世界核地质科学》2005年第1期5-16,共12页World Nuclear Geoscience

摘　　要：如何安全处置高放废物是核工业可持续发展面临的挑战性问题.我国的高放废物深地质处置研究从1985年开始,提出的计划目标是:于21世纪中叶建成我国高放废物地质处置库,处置的对象是玻璃固化块、超铀废物和部分乏燃料,处置库为竖井-坑道型,候选围岩为花岗岩,位于饱和带中.在1985～2004的20 a中,我国高放废物地质处置研究取得了进展,已确定我国高放废物最终处置走'深地质处置',并且是'三步曲'式的技术路线,即处置库选址和场址评价-地下实验室-处置库.经过全国筛选对比,已初步选定甘肃北山地区为重点预选区,该区地处戈壁,地壳结构完整,地壳稳定,人烟稀少,地质条件和水文地质条件均有利.20世纪90年代初期,开展了地下实验室的选址工作,初步选择了北京郊区2处地点为我国高放废物地质处置'普通地下实验室'的场址.已确定使用膨润土作为处置库的回填材料,并初步确定内蒙古高庙子膨润土为我国高放废物处置库的首选缓冲回填材料.对膨润土的矿物学、岩土力学、物理力学性质和热学性质进行了研究.已获得一批放射性核素(主要是Np、Pu、Tc)在北山花岗岩和膨润土上的吸附分配比、扩散系数和弥散系数等参数,建立了低氧手套箱和模拟处置库温度、压力和氧化-还原条件的小型实验装置.高放废物中的关键核素的化学行为研究也取得进展.花岗岩接触带核素迁移、铀矿床中超铀元素迁移、青铜器腐蚀等天然类比研究取得了成果.还开展了高放废物地质处置系统总性能评价源项和生物圈模式的调研.概念设计研究仅在20世纪90年代初开展了部分研究.从1999年开始,与国际原子能机构开展了2期高放废物地质处置技术合作项目,极大地提高了我们的技术水平.20 a的科研工作为我国在21世纪完成高放废物地质处置奠定了一定基础.Safe disposal of high level radioactive waste (HLW) is a challenging issue for the sustainable development of nuclear energy. The studies for the disposal of HLW in China started in 1985, the proposed goal was to build China's high level waste repository by mid-21st Century, while the waste to be disposed of will be vitrified waste, transuranic waste and small amount of spent fuel. The proposed repository was a shaft-tunnel-silo model hosted by granite in saturated zone. In the period of 1985 to 2004, progress was made in China's HLW disposal program. It was decided that 'deep geological disposal' will be used to dispose of China s HLW, while the technical strategy for the development of repository will a 3-step strategy, that includes steps of site selection & site evaluation, construction of underground research laboratory, and construction of repository. Based on nation wide screening, the Beishan area, Cansu Province, northwestern China, located in Gobi desert area with few inhabitants, integral crust structure and favorable geological and hydrogeological conditions, was selected as the most potential area for China s repository. In early 1990 s, site selection for underground research laboratory was conducted, 2 sites in the suburb of Beijing were preliminarily selected as the potential sites for a ' generic underground research laboratory' . It was determined to use bentonite as backfill material for the repository, while the bentonite from Gaomiaozi deposit in Inner Mongolia was selected as potential buffer and backfill material for China s repository. The studies on the mineralogical, geotechnical, physico-mechanical and thermal properties of the Gaomiaozi bentonite have been conducting. Some parameters such as sorption radio, diffusion coefficient and dispersion coefficient of radionuchdes (Np, Pu and Tc) in Beishan granite and bentonite have been obtained. A low-oxygen glove box and a device simulating the temperature, pressure and redox potential of repository have been established. China has also made

关 键 词：中国 高放废物 地质处置 地下实验室 场址特性评价 

分 类 号：X771[环境科学与工程—环境工程]