理论与试验研究

考虑膨润土颗粒层的高放废物处置库温度场解析解

  • 周祥运 ,
  • 胡世翔 ,
  • 卓为顶 ,
  • 孙德安 ,
  • 许迅
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  • 1.南京工程学院 土木工程与智慧管理研究所,南京 211167;
    2.上海大学 力学与工程科学学院,上海 200444
周祥运(1992—),男,河南信阳人,博士,讲师,主要从事高放废物处置库缓冲材料传热特性等方面的研究工作。E-mail:zhouxiangyun@njit.edu.cn
孙德安(1962—),男,浙江余姚人,博士,教授、博士生导师,主要从事土力学等方面的研究工作。E-mail:sundean@shu.edu.cn

收稿日期: 2024-10-09

  网络出版日期: 2025-06-13

基金资助

国家自然科学基金(42077229,52378354);江苏省高等学校基础科学(自然科学)研究面上项目(23KJD560002);南京工程学院引进人才科研启动基金(YKJ202323)

Analytical Solution to Temperature Field of the Repository for Deposing the High-Level Radioactive Waste Considering the Bentonite Pellet Layer

  • Zhou Xiangyun ,
  • Hu Shixiang ,
  • Zhuo Weiding ,
  • Sun De'an ,
  • Xu Xun
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  • 1. Institute of Civil Engineering and Intelligent Management, Nanjing Institute of Technology, Nanjing 211167, P.R. China;
    2. School of Mechanics and Engineering Science, Shanghai University, Shanghai 200444, P.R. China

Received date: 2024-10-09

  Online published: 2025-06-13

摘要

高放废物处置库温度场的时空演化规律是处置库热量尺寸设计和安全性能评估的重要参考之一。根据处置库多重屏障系统设计,建立了二维轴对称条件下处置单元的三层热分析模型。采用拉普拉斯变换和有限傅里叶正弦变换及其逆变换方法,对传热控制方程进行求解,获得了膨润土块层、颗粒层及围岩层的温度场半解析解。通过与数值解和双层模型解的比较分析,证实了三层模型解的可靠性及其在描述复杂热传导问题中的优势。进一步探讨了几何参数和材料热物性参数对缓冲层峰值温度的影响规律,并利用模型半解析解确定了不同类型核废料处置容器的合理间距,同时对瑞典原型处置库的加热试验结果进行了预测分析。结果表明:考虑膨润土颗粒层时缓冲层峰值温度较未考虑情况升高14.84 ℃;由于颗粒层热传导系数较低,其厚度对缓冲层峰值温度具有显著影响;当处置容器间距大于20 m时,缓冲层峰值温度变化趋于平缓;模型半解析解能够有效预测原型处置库加热试验的温度响应特性。

本文引用格式

周祥运 , 胡世翔 , 卓为顶 , 孙德安 , 许迅 . 考虑膨润土颗粒层的高放废物处置库温度场解析解[J]. 地下空间与工程学报, 2025 , 21(3) : 780 -791 . DOI: 10.20174/j.JUSE.2025.03.05

Abstract

The spatiotemporal distribution of temperature fields serves as a critical basis for the thermal design and safety assessment of high-level radioactive waste repositories. Based on the multi-barrier concept of disposal systems, a two-dimensional axisymmetric three-layer thermal model was developed. The governing heat transfer equations were solved using the Laplace transform, Fourier transform, and their corresponding inverse transforms, yielding semi-analytical expressions for temperature distributions in the bentonite block layer, pellet layer, and host rock. Comparative analyses with numerical simulations and two-layer analytical solutions demonstrated the validity and superior capability of the three-layer model in addressing complex heat conduction phenomena. Utilizing the derived semi-analytical solutions, parametric studies were conducted to investigate the influence of geometric and thermal properties on buffer layer temperature maxima. Furthermore, the model was applied to determine optimal disposal container spacing for various nuclear waste types and to simulate the thermal response in Sweden's prototype repository. The results indicate: (1) inclusion of the bentonite pellet layer increases buffer peak temperature by 14.84 ℃ compared to its exclusion; (2) pellet layer thickness significantly affects temperature maxima due to its relatively low thermal conductivity; (3) buffer temperature variations become negligible when container spacing exceeds 20 m; (4) the proposed solution accurately predicts thermal behavior in prototype repository heating experiments.

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