核废料处置库热-力耦合数值模拟研究

Coupled Thermo-mechanical Numerical Simulation of the Radioactive Waste Repository

  • 摘要: 基于岩石的热-力耦合特性,文章应用 ABAQUS有限元软件对核废料处置库 1 000 a内的温度场以及开挖和回填后的应力场进行了数值模拟分析,初步得到了核废料处置库温度场随时间的演化规律以及围岩和缓冲材料应力场的变化特征。模拟结果表明:废物体中心温度在处置 6.3 a左右达到最高值 116℃,而后不断下降,最后进入长期缓慢的下降阶段。缓冲材料的导热系数对处置库围岩的温度场有着较大的影响,缓冲材料的导热系数越大,废物体中心所能达到的最高温度就越低。处置隧道和处置坑回填后,围岩内部拉应力较大,接近抗拉强度,有被拉坏的风险。缓冲材料内部的拉应力与压应力都较大,在处置隧道与处置坑相交处存在被拉坏的风险,而在处置隧道的底脚处存在被压坏的风险。

     

    Abstract: Based on the thermo-mechanical coupling characteristics of rocks, the temperature field and stress field in 1 000 years after excavation and backfill were calculated by using finite element program ABAQUS, and the evolution laws of temperature field of the nuclear waste repository and stress field of surrounding rocks and buffer material were obtained. The results show that the maximum temperature at the center of nuclear waste reaches 116℃ in 6.3 years after dispose, then decreases gradually and finally goes into the slow decreasing period. The conductivity of buffer material has great influence on temperature field of surrounding rocks, the higher the conductivity is, the lower the maximum temperature at the center of nuclear waste is. After backfill of the disposal tunnel and pit, the tensile stress of surrounding rocks is very large which is very close to the tensile strength and there are risks of tensile fracture failure. The tensile and compressive stresses are both very high in buffer material, tensile fracture failure could occur at the intersection of the disposal tunnel and pit, and compressive fracture failure could occur at the floor of the disposal tunnel.

     

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