裂隙水流-传热对高放废物处置库近场温度影响的三维离散元分析
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摘要
裂隙水流-传热是高放废物处置库行为的重要影响因素。为研究裂隙水流-传热对高放废物处置库近场温度的影响,采用3DEC离散元软件计算分析了完整岩体模型和裂隙岩体水流模型对处置库近场温度分布和演变的影响。计算分析表明:由于裂隙水流的吸热降温作用,裂隙岩体模型的废物罐表面膨润土温度低于完整岩体模型的废物罐表面膨润土温度,并缩短了达到稳态所需要的时间;裂隙水流上游区域废物罐表面膨润土温度显著低于裂隙水流下游区域废物罐表面膨润土温度;在设定条件下,裂隙岩体模型的废物罐表面膨润土最高温度约为完整岩体模型废物罐表面膨润土最高温度的75%,裂隙水流速度从0.2mm/s增大到0.5mm/s,废物罐表面膨润土最高温度降低约4%。
Fracture water flow and heat transfer is an important influence factor on the behavior of high level radioactive waste repositories.The 3DEC discrete element software was used for analyzing an intact rock model without water flow and a fractured rock model with water flow.The influence characteristics of fracture water flow on the near field temperature distributions and evolutions were analyzed for a hypothetical high level radioactive waste repository.The calculations reveal that due to the endothermic effect of fracture water flow,the temperatures of the bentonite at the canisters surface obtained from the fractured rock model are lower than those from the intact rock model,and the time to reach steady state for the former is shorter;the temperatures of the ben-tonite at the canisters surface in the upstream are significantly lower than those in the downstream of the fractured rock model;under given conditions,the maximum temperature of the canisters surface bentonite for the fractured rock model is about 75% of that for the intact rock model,and when the fracture water velocity is increased from 0.2mm/s to 0.5 mm/s,the peak temperature of bentonite at the canisters surface is reduced by about 4%.
Fracture water flow and heat transfer is an important influence factor on the behavior of high level radioactive waste repositories.The 3DEC discrete element software was used for analyzing an intact rock model without water flow and a fractured rock model with water flow.The influence characteristics of fracture water flow on the near field temperature distributions and evolutions were analyzed for a hypothetical high level radioactive waste repository.The calculations reveal that due to the endothermic effect of fracture water flow,the temperatures of the bentonite at the canisters surface obtained from the fractured rock model are lower than those from the intact rock model,and the time to reach steady state for the former is shorter;the temperatures of the ben-tonite at the canisters surface in the upstream are significantly lower than those in the downstream of the fractured rock model;under given conditions,the maximum temperature of the canisters surface bentonite for the fractured rock model is about 75% of that for the intact rock model,and when the fracture water velocity is increased from 0.2mm/s to 0.5 mm/s,the peak temperature of bentonite at the canisters surface is reduced by about 4%.
引文
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[3]刘淑芬,郭永海,王驹,等.高放废物地质处置库北山预选区地下水的形成和分布[J].铀矿地质,2007,23(6):356-362.LIU Shufen,GUO Yonghai,WANG Ju,et al.Groundwater formation and distribution in the preselected Beishan area of repository for high level radioactive waste[J].Uranium Geology,2007,23(6):356-362(in Chinese).
[4]吕涛,杨球玉,王旭宏,等.我国高放废物地质处置库地下主体结构构想[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.
[5]刘文岗,王驹,周宏伟,等.高放废物处置库花岗岩热-力耦合模拟研究[J].岩石力学与工程学报,2009,28(增刊1):2 875-2 882.LIU Wengang,WANG Ju,ZHOU Hongwei,et al.Coupled thermo-mechanical analysis of granite for high-level radioactive waste repository[J].Chinese Journal of Rock Mechanics and Engineering,2009,28(Suppl.1):2 875-2 882(in Chinese).
[6]赵宏刚,王驹,苏锐.HLW水平处置硐室间距分析[J].世界核地质科学,2014,31(增刊1):305-312.ZHAO Honggang,WANG Ju,SU Rui.Thermal dimension analysis of the HLW horizontal disposal[J].World Nuclear Geoscience,2014,31(Suppl.1):305-312(in Chinese).
[7]张玉军.热-水-力耦合模型及原位试验二维有限元分析[J].岩土工程学报,2007,29(3):313-318.ZHANG Yujun.Coupled thermo-hydro-mechanical model and 2D FEM analysis for FEBEX insitu test[J].Chinese Journal of Geotechnical Engineering,2007,29(3):313-318(in Chinese).
[8]张勇,项彦勇.裂隙水流传热对核废处置库近场温度影响的半解析计算分析[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.
[9]ABDALLAH G,THORAVAL A,SFEIR A,et al.Thermal convection of fluid in fractured media[J].International Journal of Rock Mechanics&Mining Science&Geomechanics Abstracts,1995,32(5):481-490.
[10]赵宏刚.高放废物处置库热传导特性及处置硐室稳定性研究——以甘肃北山预选区为例[D].北京:核工业北京地质研究院,2009.
[11]李亚萍.甘肃北山花岗岩裂隙几何学特征研究[D].北京:中国地震局地质研究所,2005.
[12]路威.裂隙岩体水流-传热模型试验与计算理论研究[D].北京:北京交通大学,2012.