岩土力学 ›› 2025, Vol. 46 ›› Issue (8): 2626-2638.doi: 10.16285/j.rsm.2024.1125CSTR: 32223.14.j.rsm.2024.1125

• 数值分析 • 上一篇    下一篇

热-水-力多场耦合下高放废物处置库核心处置单元间距设计研究

张奇1, 2,王驹1,刘江峰2,曹胜飞1,谢敬礼1,成建峰1   

  1. 1. 核工业北京地质研究院 国家原子能机构高放废物地质处置创新中心,北京 100029; 2. 中国矿业大学 深地工程智能建造与健康运维全国重点实验室,江苏 徐州 221116
  • 收稿日期:2024-09-11 接受日期:2025-02-14 出版日期:2025-08-11 发布日期:2025-08-17
  • 作者简介:张奇,男,1991年生,博士,高级工程师,主要从事高放废物地质处置缓冲材料多物理场模拟研究。E-mail: zhangqi428@126.com
  • 基金资助:
    国家原子能机构核设施退役及放射性废物治理项目;中国矿业大学深地工程智能建造与健康运维全国重点实验室开放基金(No. SKLGDUEK2202)

Core disposal elements spacing design for high-level radioactive waste repository under coupled thermo-hydro-mechanical condition

ZHANG Qi1, 2, WANG Ju1, LIU Jiang-feng2, CAO Sheng-fei1, XIE Jing-li1, CHENG Jian-feng1   

  1. 1. CAEA Innovation Center for Geological Disposal of High-Level Radioactive Waste, Beijing Research Institute of Uranium Geology, Beijing 100029, China; 2. State Key Laboratory of Intelligent Construction and Healthy Operation and Maintenance of Deep Underground Engineering, China University of Mining and Technology, Xuzhou, Jiangsu 221116, China
  • Received:2024-09-11 Accepted:2025-02-14 Online:2025-08-11 Published:2025-08-17
  • Supported by:
    This work was supported by China Atomic Energy Authority (CAEA) through the Geological Disposal Program, and the Open Fund of State Key Laboratory of Intelligent Construction and Healthy Operation and Maintenance of Deep Underground Engineering, China University of Mining & Technology (SKLGDUEK2202).

摘要: 高放废物核心处置单元在热-水-力耦合条件下的长期性能对于现场试验及处置库概念设计具有重要意义。以核心处置单元为研究对象,构建了相应热-水-力多场耦合模型,借助有限元数值模拟软件COMSOL Multiphysics,开展了不同处置方式下高放废物核心处置单元三维数值模拟研究。模拟结果表明,当竖直处置1个、2个和3个废物罐时,单场传热模拟下处置单元最小处置间距比热-水-力耦合下更大,这是因为单场传热模拟,不考虑缓冲材料吸水饱和度升高,缓冲材料热传导系数偏小所致,但单场传热模拟得出的处置间距,对于处置单元是偏安全的。随着处置坑内废物罐个数的增加,废物罐的平均处置面积略有增加,热场分析结果表明,一个处置坑处置一个废物罐时最能节省处置面积。当采用水平处置时,处置单元内热量向外传输比竖直处置时要慢,热场分析结果表明,竖直处置更能节省处置面积。

关键词: 高放废物地质处置, 处置库概念设计, 热-水-力耦合, 数值模拟, 传热

Abstract: It is of great significance to investigate the long-term performance of core disposal element of high-level radioactive waste under coupled thermo-hydro-mechanical condition, especially for the site experiments and repository conceptual design. In this work, a coupled thermo-hydro-mechanical model was proposed based on the core disposal element. The finite element numerical simulation software COMSOL Multiphysics was employed to conduct the 3D numerical simulation on the core disposal element under different disposal concepts. The simulation results indicate that the minimum disposal distance between deposition holes obtained by thermal transfer simulation is larger than that by coupled thermo-hydro-mechanical simulation, when disposing 1 canister, 2 canisters, and 3 canisters vertically in the deposition hole. That’s because the increase in water saturation of the buffer material is not considered in the thermal transfer simulation, resulting in a smaller thermal conductivity coefficient of the buffer material. However, the disposal spacing derived from thermal transfer simulation provides a more secure approach for disposal elements. It can be seen that as the number of canisters in the deposition hole increases, the average disposal area of the canisters slightly increases. The results of thermal transfer analysis indicate that it is optimal to allocate one canister per deposition hole in terms of disposal area conservation alone. For horizontally disposal, the overall heat transfer to the outside of the deposition hole deteriorates is slower than vertically disposal. The results of thermal transfer analysis indicate that it is optimal to disposal vertically.

Key words: geological disposal of high-level radioactive waste, repository conceptual design, thermo-hydro-mechanical coupling, numerical simulation, heat transfer

中图分类号: TU 411
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