上海大学学报(自然科学版) ›› 2023, Vol. 29 ›› Issue (4): 769-.

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高放废物处置库温度场解析

何路强, 周祥运, 孙德安   

  1. 上海大学 力学与工程科学学院, 上海 200444
  • 收稿日期:2022-06-22 出版日期:2023-08-30 发布日期:2023-09-01
  • 基金资助:
    国家自然科学基金资助项目 (42077229)

Analytical study on temperature field of high-level radioactive waste disposal repository 

HE Luqiang, ZHOU Xiangyun, SUN Dean   

  1. School of Mechanics and Engineering Science, Shanghai University, Shanghai 200444, China
  • Received:2022-06-22 Online:2023-08-30 Published:2023-09-01
  • Contact: 孙德安 (1962—), 男, 教授, 博士生导师, 博士, 研究方向为非饱和土力学.

摘要: 高放废物处置库的温度场分布特征是处置库安全性能评估和尺寸设计的重要依据之 一. 根据 KBS-3V 型处置库概念设计, 建立了单废物罐的轴对称 2 维传热模型. 首先, 借助有 限傅里叶正弦变换、分离变量法和冲量定理法得到单废物罐放热条件下围岩任意点的温度解 析表达式, 通过与已有的半解析解和线热源解结果的对比分析, 验证了该模型的有效性; 采用 在岩壁温度上叠加缓冲层温度差的方法得到废物罐表面温度, 然后分析了废物罐近场温度演 化规律; 最后, 对材料热参数、核废物衰变参数以及几何参数对废物罐表面温度的影响进行了 分析. 研究结果表明: 废物罐近场温度在前 2 年快速上升并达到峰值, 之后温度随处置时间缓 慢下降; 缓冲区温度梯度较大, 而围岩区温度梯度较小; 缓冲材料和围岩导热系数越大、缓冲 层厚度越薄、核废物燃烧值越小、冷却时间越长, 则废物罐表面温度越低; 膨润土颗粒层厚度 对废物罐表面温度的影响大于膨润土块层厚度, 这是因为颗粒层材料导热系数较低. 

关键词: 高放废物处置库, 传热模型, 温度场, 解析解 

Abstract: The temperature distribution characteristic of a high-level radioactive waste disposal repository is important for evaluating its safety performance and designing appropriate thermal dimensions. Based on the conceptual design of the KBS-3V disposal repository, a two-dimensional axisymmetric heat transfer model for a single nuclear waste canister is established. By means of the finite Fourier sine transform, the separation of variables and the impulse theorem, an analytical expression is obtained from which the surrounding rock temperature at any point, under a single-waste-canister heat release condition, can be determined. The validity of the proposed model is verified by comparing the results of existing semi-analytical solutions with linear heat source solutions. The surface temperature of the waste canister is obtained by superposing the temperature difference of the buffer layer on the rock wall temperature, before analyzing the near-field temperature evolution of the waste canister. Finally, the effect of material thermal parameters, nuclear waste decay parameters, and geometric parameters on the waste canister surface temperature are analyzed. The results show that the near-field temperature of the waste canister increased rapidly, reaching a peak within the first two years of the canister being disposed of, after which the temperature decreases slowly with the disposal time. The buffer temperature gradient is large while the rock temperature gradient is small. The larger the thermal conductivity of the buffer material and surrounding rock, the thinner the buffer layer, the smaller the combustion value of nuclear waste, and the longer the cooling time, the lower the surface temperature of the waste canister. The thickness of the bentonite pellet layer has a greater effect on the surface temperature of the waste canister than that of the bentonite block layer, mainly because of the lower thermal conductivity of granular layer material.

Key words: high-level radioactive waste disposal repository, heat transfer model, temperature ?eld, analytical solution

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