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缓冲材料参数对核废料处置库近场影响的二维有限元分析 被引量:2

Two-Dimensional FEM Analysis of Near Field Influence of Buffer Material Parameters on High Level Radioactive Nuclear Waste Repository
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摘要 以高放射性核废料地质处置的FEBEX原位试验作为数值计算模型,利用有限元软件Code-Bright,通过改变膨润土初始渗透系数、初始吸力和初始进气值,得到热-水-力(thermo-hydro-mechanical,THM)耦合作用下处置库关闭后缓冲层饱和度和吸力的变化规律,以及以上3个因素对这些性状影响的敏感程度,研究结果可为核废料处置库缓冲材料的选取提供参考. The FEBEX in-situ test a calculation model. By changing for geological disposal of high-level radioactive nuclear waste is used as the initial permeability, the initial suction and the air entry value, variation of saturation, and suction under the coupled thermo-hydro-mechanical (THM) action are analyzed using a Code-Bright program after the closure of nuclear waste repository. By analyzing sensitivity of the three parameters on these traits, valuable reference is presented for the selection of buffer materials of the nuclear waste repository.
出处 《上海大学学报(自然科学版)》 CAS CSCD 北大核心 2012年第5期539-544,共6页 Journal of Shanghai University:Natural Science Edition
关键词 膨润土 核废料处置库 热-水-力耦合 数值模拟 bentonite nuclear waste repository coupled thermo-hydro-mechanical (THM) numericalsimulation
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  • 2Eduardo E. Alonso.工程屏障中的气体迁移(英文)[J].岩石力学与工程学报,2006,25(4):693-708. 被引量:8
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