期刊文献+

高放废物处置库单个竖直钻孔内废物包个数探究 被引量:3

Study on Package Numbers in Single Vertical Borehole in High-level Waste Repository
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摘要 为探究高放废物处置库中单个竖直钻孔内允许放置废物包的数量,采用我国处置库概念设计模型、调研和实验所得参数,以ANSYS workbench为平台进行了模拟探究。结果表明,为满足处置库热力学要求,并综合考虑工程经济和施工建造,建议单个竖直钻孔内废物包数量不多于2个。 The study on the package numbers in single vertical borehole in high‐level waste (HLW) repository for temperature field was performed with the simulation of ANSYS workbench , based on the conceptual design of China and its corresponding experimental parameters .The results suggest that the package numbers are less than 2 in single borehole ,taking into account engineering economy and project construction as w ell .
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2015年第5期787-794,共8页 Atomic Energy Science and Technology
基金 科工局"十二五"地质处置安全评价技术研究资助项目(科工二司(2013)1221)
关键词 高放废物 竖直钻孔 废物包个数 温度场 HLW vertical borehole package number temperature field
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参考文献12

  • 1SKB.Strategy for thermal dimensioning of the final repository for spent nuclear fuel,R-09-04[R].Swedish:SKB,2009.
  • 2POSIVA.Thermal analyses of spent nuclear fuel repository,POSIVA 2003-04[R].Finland:POSIVA,2003.
  • 3SCK · CEN.Update of the near field tempera* ture calculations for disposal of the PAMELA waste types in a monolith-based geological repos- itory,SCK ? CEN-ER-123[R].Belgium:SCK · CEN,2010.
  • 4NWMO.Coupled thermal-mechanical modeling of a deep geological repository using the horizon- tal tunnel placement method in sedimentary rock using CODE_BRIGHT,TR-2010-22[R].Cana- da:NWMO,2010.
  • 5NAGRA.Calculations of the temperature evolu- tion of a repository for spent fuel,vitrified high- level waste and intermediate level waste in opali- nus clay,Technical Report 01-04[R].Switzer- land:NAGRA,2002.
  • 6中国核电工程有限公司.髙放废物地下实验室和处置库概念设计[R]//中国国防科学技术报告.北京:中国核电工程有限公司,2011.
  • 7ANDRA.Evaluation of the feasibility of a geo- logical repository in an argillaceous formation,Report series synthesis[R].France:ANDRA,2005.
  • 8张华,罗上庚.高放废物安全处置第一道重要屏障:高放玻璃固化体[C]//第三届废物地下处置学术研讨会论文集.北京:中国岩石力学与工程学会废物地下处置专业委员会,2010.
  • 9李宁,姚琳,卢可可,等.我国高放废物处置容器设计方案[C]//第四届废物地下处置学术研讨会论文集.北京:中国岩石力学与工程学会废物地下处置专业委员会,2012.
  • 10孙德安,张谨绎,邵莉娜.高庙子膨润土和砂混合样浸水膨胀变型特性〔C]//第四届废物地下处置学术研讨会论文集.北京:中国岩石力学与工程学会废物地下处置专业委员会,2012.

二级参考文献14

  • 1刘俊志.膨润土与花岗岩碎石混合材料制热传导系数[D].台湾中央国立大学,2003.
  • 2刘月妙,徐国庆,刘淑芬,等.内蒙古高庙子膨润土基本性能研究[M].北京:中国核工业音像出版社,2001:1-20.
  • 3TANG A M, CUI Yu-jun, et al, A study on the thermal conductivity of compacted bentonites[J]. Applied Clay Science, 2007(11): 1 - 9.
  • 4PACOVSKY Jaroslav. Some results from geotechnical research on bentonite[C]// KONVALINKA Petr, LUXEMBURK Frantisek, editors. CTU Reports: Experimental Investigation of Building Materials and Technologies, 2002(6): 107 - 116.
  • 5刘月妙,蔡美峰,王驹.内蒙古高庙子钠基膨润土导热性能研究[C]//第二届全国岩土与工程学术大会论文集(下册).武汉,2006:742-746.
  • 6OULD-LAHOUC1NE C, SAKASHITA H, KUMATA T. Measurement of thermal conductivity of buffer materials and evaluation of existing correlations predicting it[J]. Nuclear Engineering and Design, 2002, 216(1/2/3): 1 - 11.
  • 7TIEN Y M, CHU C A, CHUANG W S. The prediction model of thermal conductivity of sand-bentonite based buffer material[C]// Clays in Natural and Engineered Barriers for Radioactive Waste Confinement, Tours, France, 2005.
  • 8KAHR G, MULLER-VON Moos, M. Warmeleitfahigkeit von bentonit MX80 und von montigel nach der heizdrahtmethode[R]. Zurich: Swiss National Cooperative for the Disposal of Radioactive Waste, NAGRA Technisher Bericht, 1982. (KAHR G. MULLER-VON Moos, M.Thermal conductivity of MX80 bentonite and Montigel after hot-wire[R]. Zurich: Swiss National Cooperative for the Disposal of Radionactive Waste, NAGRA Technisher Bericht, 1982.
  • 9KNUTSSON S. On the thermal conductivity and thermal diffusivity of highly compacted Bentonite[R]. SKB Report, Swedish Nuclear Fuel and Waste Management Co, 1983.
  • 10SAKASHITA H, KUMADA T. Heat transfer model for predicting thermal conductivity of highly compacted bentonite[J]. J Atom Soc Jap, 1998, 40:235 - 240.

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