期刊文献+

中国高放废物处置库缓冲材料物理性能(英文) 被引量:46

PHYSICAL PROPERTY OF CHINA′S BUFFER MATERIAL FOR HIGH-LEVEL RADIOACTIVE WASTE REPOSITORIES
下载PDF
导出
摘要 深地质处置被国际上公认为处置高放废物的最有效可行的方法。中国深地质处置的概念模型采用多重工程屏障系统(包括废物固化体、废物容器、外包装、缓冲/回填材料)和适宜的地质围岩地质体共同作用来确保高放废物与生物圈的安全隔离。膨润土由于具有极低的渗透性和优良的核素吸附等性能而被国际上选作缓冲材料的基础材料。经过全国筛选,高庙子膨润土矿床被选作我国缓冲材料供应基地。从 2000 年起,对产自该矿床的钠基膨润土 GMZ–1 开始了系统的研究工作。介绍了 GMZ–1 的矿物组成、基本特征和 GMZ–1 在不同干密度、不同含水量条件下的热传导、水传导、力学性能参数及 GMZ–1 在不同干密度条件下的膨胀特性参数测定结果。GMZ–1钠基膨润土具有蒙脱石含量高(75%左右)、杂质矿物相对较少的特点,对于该材料的系统和深入研究对于开发我国缓冲回填材料技术,确保高放废物的安全有效处置有重要意义。 The deep geological disposal is regarded as the most reasonable and effective way to safely dispose high-level radioactive wastes(HLW) in the world. The conceptual model of HLW geological disposal in China is based on a multi-barrier system that combines an isolating geological environment with an engineered barrier system including the vitrified HLW, canister, overpack and buffer/backfill material, The bentonite is selected as base material of the buffer/backfill material in HLW repositories, due to the very low permeability and excellent retardation of nuclides from migration, etc. GMZ deposit is selected as the candidate supplier for buffer material of HLW repositories in China. Since 2000, systematic study was conducted on GMZ-1 that is Na-bentonite produced from GMZ deposit and selected as reference material for Chinese buffer material study. The mineral composition, basic parameters of GMZ-1 bentonite and thermal conductivity, hydraulic conductivity, unconfined compression strength as function of dry density and water content are presented. The swelling stress of GMZ-1 bentonite as function of dry density is also reported, GMZ-1 bentonite is characterized by high content of montmorillonite(about 75%) and less impurities. The adequacy understanding of property and long-term behavior in deep geological condition of GMZ-1 is essential to safe dispose the high-level radioactive wastes in China.
作者 温志坚
出处 《岩石力学与工程学报》 EI CAS CSCD 北大核心 2006年第4期794-800,共7页 Chinese Journal of Rock Mechanics and Engineering
关键词 高放废物处置 高庙子膨润土 缓冲材料 物理性能 high-level radioactive wastes disposal GMZ-1 buffer material physical properties
  • 相关文献

参考文献12

  • 1OECD/NEA.Geological Disposal of Radioactive Waste Review of Developments in the Last Decade[M].Beijing:Atomic Energy Press,2001. 被引量:1
  • 2Pusch R.Required physical and mechanical properties of Buffer Masses(KBS Technical Report No.33)[R].Sweden:Swedish Nuclear Project(Svensk K(a)rnbr(a)nslehantering AB),1977. 被引量:1
  • 3Pusch R.High compacted sodium bentonite for isolating rock-deposited radioactive waste products[J].Nuclear Technology,1979,45(2):153-157. 被引量:1
  • 4Pusch R.The buffer and backfill handbook,part 2:materials and techniques(SKB TR-02-12)[R].[s.l.]:Svensk K(a)rnbr(a)nsle-hantering A B,2001. 被引量:1
  • 5PNC.Research and development on geological disposal of high-level radioactive waste:the first progress report(H3)[R].PNC:TN 1410,1992. 被引量:1
  • 6Gu Q,Du Z.Property of bentonite as buffer-backfill material and its application[J].Oversea Uranium and Gold Geology,1992,(Supp.):73-95. 被引量:1
  • 7Xu G,Li Y,Gu Q,et al.Selection of bentonite deposits[R].Beijing:Beijing Research Institute of Uranium Geology,China National Nuclear Corporation,1996. 被引量:1
  • 8Liu Y,Xu G,Liu S,et al.Study on basic property of GMZ Ca-bentonite[R].Beijing:Beijing Research Institute of Uranium Geology,China National Nuclear Corporation,2000. 被引量:1
  • 9Wen Z J,Liu Y.The first progress report on the study of GMZ sodium bentonite[R].Beijing:Beijing Research Institute of Uranium Geology,China National Nuclear Corporation,2002. 被引量:1
  • 10Wen Z J,Jintoku T.Comparison study of basic property between GMZ-1 and Kunigel V1 Bentonite(Final report for MEXT Nuclear Researchers Exchange Program)[R].[s.l.]:[s.n.],2003. 被引量:1

同被引文献330

引证文献46

二级引证文献353

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部