裂隙岩体水流—传热模型试验与计算理论研究
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摘要
对于高放射核废物,建造地下处置库,利用深部岩石洞室进行永久储存是目前唯一可能实现的处置方案。为评估处置库的安全性,需要研究处置库近场裂隙岩体内的水流-传热过程。本文的研究内容和主要成果如下：
(1)选用甘肃北山地区(中国高放射核废物处置库重要预选场区)的花岗岩,制作高度×宽度×厚度为1502.5mm×904mm×300mm的规则裂隙岩体模型,试验模拟了裂隙水流动-传热和岩石热传导之间的相互作用。结果表明,裂隙水流动-传热能够显著改变模型温度场分布,热源对裂隙以外岩体温度的影响和模型温度场达到稳态所需的时间随热源温度升高、裂隙水流速降低和裂隙填砂而增大；邻近热源的裂隙水流动是影响模型温度分布的主要因素,远离热源的裂隙水流动主要影响边界温度和模型温度场达到稳态所需的时间；试验过程中裂隙水无相变产生,温度变化对裂隙水压强的影响很小。
(2)分析了裂隙水与填充颗粒之间瞬时热平衡假定及影响因素,分析了裂隙水与岩石壁面之间瞬时热平衡假定对水流-传热的影响。填充裂隙内的换热平衡时间受水-填充颗粒对流换热系数与颗粒直径的比值控制,比值越大,时间越短；考虑裂隙水与岩石壁面对流换热(非瞬时热平衡)时计算得到的裂隙水温度低于瞬时热平衡假定的计算结果；裂隙水流动距离与流速的比值越大,水与岩石壁面间的对流换热越充分,岩石的体积比热和热传导系数的乘积与对流换热系数的比值越小、与裂隙开度的比值越大,水与岩石壁面间的对流换热速度越快,因为瞬时热平衡假定而产生的差别越小。
(3)建立了规则裂隙岩体水流-传热的有限差分格式控制方程,编写了计算机程序并运用TOUGH2对模型试验进行了模拟和参数敏感性分析。模型试验、有限差分计算和TOUGH2计算结果基本一致；热源温度、裂隙开度、裂隙水流速和岩石体积比热是影响裂隙水温度的敏感参数,邻近热源侧垂直裂隙的稳态出水温度受其它裂隙的影响很小。
(4)考虑核废物罐放热功率是时间的函数、岩石和水的热物理参数是温度的函数、回填材料的体积比热是饱和度的函数,利用有限差分计算程序,分析了处置库近场裂隙岩体水流-传热特征。裂隙水的流动促进了热量沿水流方向的传递,改变了岩石的温度分布,增大了处置库的影响范围；核废物罐温度最大值随垂直裂隙水流速、裂隙开度的增大和裂隙与处置库水平距离的减小而下降；流入处置库的水平裂隙水能够减缓核废物罐的升温速度,但是对其温度最大值的影响很小。
For safe disposal of high level radioactive nuclear waste, the only currently suitable approach is underground disposal facilities. Better understandly of water flow and heat transfer in fractured rocks is needed for evaluating the safety of the nuclear waste repositories. The main contents and results of this thesis are follows:
(1) Physical modelling experiments were conducted to study water flow and heat transfer in fractured rocks. Granite rocks were taken from the Beishan area in Gansu province, which is being investigated as a potential site for the high-nuclear waste repository in China, to construct a fractured rock model of height-1502.5mm*width-904mm*thickness-300mm, consists of nine rock blocks with two vertical and two horizontal fractures. The experimental results revealed, water flow and heat transfer in fractures can significantly change the temperature field of the model, for higher heat source temperatures, lower water velocities and sands filled in the fractures the range of influence of the heat source to rocks matris beyond fractures is larger, and the time for asymptotically approaching steady-state is longer; the vertical fracture adjacent to the heat source controled the temperature distribution in the model while the other fractures mainly influenced the boundary temperature and the time for approaching steady-state; there was no phase change of the water in the fractures, and the temperature variations had little effect on the water pressure.
(2) Influence of thermal dynamic equilibrium assumptions for water and filled particles fractures as well as for rock face and fracture water was analyzied. The time to reach thermal equilibrium in the fractures is controlled by the ratio of convective heat transfer coefficient to particle diameter, longer time is needed for larger ratios; the temperature of water in the fractures calculated from using thermal equilibrium assumption is larger than that calculated by considering transient heat convection; and the discrepancy from using thermal equilibrium assumption is insignificant, for larger ratios of water travel distance to water flow velocity, for smaller ratios of the product of volume specific heat and thermal conductivity of rock matrix to convective heat transfer coefficient and to aperture of the fracture.
(3) Finite difference equations of water flow and heat transfer in reqularly fractured rocks were developed and with the computer code written and TOUGH2code simulations of the experiments and the paramete sensitivity analyses were conducted. There was a good agreement between the experiment data, and the numerical calculations; parametric sensitivity analyses indicated that the temperature distribution was highly sensitive to the heat source temperature, fracture aperture, water flow velocity and the volume specific heat of the rock matrix, and the water temperature in the vertical fracture adjacent to the heat source was not significantly affected by the other fractures.
(4) Considering the thermal output of the nuclear waste canisters as a function of time, thermal parameters of rock and water as functions of temperature, volume specific heat of the fill materials as a function of saturation, the characteristics of water flow and heat transfer in fractured rocks in the near-field of the repositories were analyzed by using the developed finite difference code. Water flow enhances heat transfer along the flow, changes the temperature field of the rock matrix, and thus increases the range of influence of the repositories, and the peak value of the canister temperature becomes lower if the water flow velocity and the aperture of the vertical fracture are increased and the distance between the vertical fracture and the canister is decreased; water flow into the repository from horizontal fracture slows the canister heating, but has little effect on the peak value of the temperature.
(1)选用甘肃北山地区(中国高放射核废物处置库重要预选场区)的花岗岩,制作高度×宽度×厚度为1502.5mm×904mm×300mm的规则裂隙岩体模型,试验模拟了裂隙水流动-传热和岩石热传导之间的相互作用。结果表明,裂隙水流动-传热能够显著改变模型温度场分布,热源对裂隙以外岩体温度的影响和模型温度场达到稳态所需的时间随热源温度升高、裂隙水流速降低和裂隙填砂而增大；邻近热源的裂隙水流动是影响模型温度分布的主要因素,远离热源的裂隙水流动主要影响边界温度和模型温度场达到稳态所需的时间；试验过程中裂隙水无相变产生,温度变化对裂隙水压强的影响很小。
(2)分析了裂隙水与填充颗粒之间瞬时热平衡假定及影响因素,分析了裂隙水与岩石壁面之间瞬时热平衡假定对水流-传热的影响。填充裂隙内的换热平衡时间受水-填充颗粒对流换热系数与颗粒直径的比值控制,比值越大,时间越短；考虑裂隙水与岩石壁面对流换热(非瞬时热平衡)时计算得到的裂隙水温度低于瞬时热平衡假定的计算结果；裂隙水流动距离与流速的比值越大,水与岩石壁面间的对流换热越充分,岩石的体积比热和热传导系数的乘积与对流换热系数的比值越小、与裂隙开度的比值越大,水与岩石壁面间的对流换热速度越快,因为瞬时热平衡假定而产生的差别越小。
(3)建立了规则裂隙岩体水流-传热的有限差分格式控制方程,编写了计算机程序并运用TOUGH2对模型试验进行了模拟和参数敏感性分析。模型试验、有限差分计算和TOUGH2计算结果基本一致；热源温度、裂隙开度、裂隙水流速和岩石体积比热是影响裂隙水温度的敏感参数,邻近热源侧垂直裂隙的稳态出水温度受其它裂隙的影响很小。
(4)考虑核废物罐放热功率是时间的函数、岩石和水的热物理参数是温度的函数、回填材料的体积比热是饱和度的函数,利用有限差分计算程序,分析了处置库近场裂隙岩体水流-传热特征。裂隙水的流动促进了热量沿水流方向的传递,改变了岩石的温度分布,增大了处置库的影响范围；核废物罐温度最大值随垂直裂隙水流速、裂隙开度的增大和裂隙与处置库水平距离的减小而下降；流入处置库的水平裂隙水能够减缓核废物罐的升温速度,但是对其温度最大值的影响很小。
For safe disposal of high level radioactive nuclear waste, the only currently suitable approach is underground disposal facilities. Better understandly of water flow and heat transfer in fractured rocks is needed for evaluating the safety of the nuclear waste repositories. The main contents and results of this thesis are follows:
(1) Physical modelling experiments were conducted to study water flow and heat transfer in fractured rocks. Granite rocks were taken from the Beishan area in Gansu province, which is being investigated as a potential site for the high-nuclear waste repository in China, to construct a fractured rock model of height-1502.5mm*width-904mm*thickness-300mm, consists of nine rock blocks with two vertical and two horizontal fractures. The experimental results revealed, water flow and heat transfer in fractures can significantly change the temperature field of the model, for higher heat source temperatures, lower water velocities and sands filled in the fractures the range of influence of the heat source to rocks matris beyond fractures is larger, and the time for asymptotically approaching steady-state is longer; the vertical fracture adjacent to the heat source controled the temperature distribution in the model while the other fractures mainly influenced the boundary temperature and the time for approaching steady-state; there was no phase change of the water in the fractures, and the temperature variations had little effect on the water pressure.
(2) Influence of thermal dynamic equilibrium assumptions for water and filled particles fractures as well as for rock face and fracture water was analyzied. The time to reach thermal equilibrium in the fractures is controlled by the ratio of convective heat transfer coefficient to particle diameter, longer time is needed for larger ratios; the temperature of water in the fractures calculated from using thermal equilibrium assumption is larger than that calculated by considering transient heat convection; and the discrepancy from using thermal equilibrium assumption is insignificant, for larger ratios of water travel distance to water flow velocity, for smaller ratios of the product of volume specific heat and thermal conductivity of rock matrix to convective heat transfer coefficient and to aperture of the fracture.
(3) Finite difference equations of water flow and heat transfer in reqularly fractured rocks were developed and with the computer code written and TOUGH2code simulations of the experiments and the paramete sensitivity analyses were conducted. There was a good agreement between the experiment data, and the numerical calculations; parametric sensitivity analyses indicated that the temperature distribution was highly sensitive to the heat source temperature, fracture aperture, water flow velocity and the volume specific heat of the rock matrix, and the water temperature in the vertical fracture adjacent to the heat source was not significantly affected by the other fractures.
(4) Considering the thermal output of the nuclear waste canisters as a function of time, thermal parameters of rock and water as functions of temperature, volume specific heat of the fill materials as a function of saturation, the characteristics of water flow and heat transfer in fractured rocks in the near-field of the repositories were analyzed by using the developed finite difference code. Water flow enhances heat transfer along the flow, changes the temperature field of the rock matrix, and thus increases the range of influence of the repositories, and the peak value of the canister temperature becomes lower if the water flow velocity and the aperture of the vertical fracture are increased and the distance between the vertical fracture and the canister is decreased; water flow into the repository from horizontal fracture slows the canister heating, but has little effect on the peak value of the temperature.
引文
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