我国高放废物地质处置屏障系统的温度场分析

夏加国; 侯伟; 王旭宏; 杨球玉; 吕涛; 吕敏

doi:10.13204/j.gyjzG20063017

我国高放废物地质处置屏障系统的温度场分析

doi: 10.13204/j.gyjzG20063017

中国核电工程有限公司, 北京 100840

基金项目:

国家国防科技工业局项目（科工二司[2017]1405号）。

详细信息

作者简介:
夏加国,男,1989年出生,博士,工程师。电子信箱:xia.jiaguo@163.com

计量
- 文章访问数: 143
- HTML全文浏览量: 14
- PDF下载量: 2
- 被引次数: 0
出版历程
- 收稿日期: 2020-06-30
- 刊出日期: 2020-11-23

ANALYSIS ON THE THERMAL FIELDS OF BARRIER SYSTEMS FOR GEOLOGICAL DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN CHINA

China Nuclear Power Engineering Co., Ltd., Beijing 100840, China

摘要

摘要: 高放废物深地质处置是通过天然屏障和工程屏障（包括废物体容器、处置容器和缓冲材料）实现对放射性废物的有效包容和隔离。基于花岗岩处置场址，以高庙子膨润土为缓冲材料，应用FLAC 3D软件开展我国大时间尺度下处置库屏障系统的热学分析，研究放射性废物在衰变释热条件下，处置环境的温度场随时间的演化规律，分析不同导热系数的缓冲材料对处置环境的温度场的影响。
- 高放废物 /
- 地质处置 /
- 缓冲材料 /
- 热学分析
Abstract: Deep geological disposal of high-level radioactive wastes can effectively contain and isolate radioactive wastes by natural and engineering barriers (including waste containers, disposal containers and buffer materials). Based on the granite disposal site, Gaomiaozi bentonite was used as buffer materials, and FLAC 3D software was used to analyze the barrier system of the disposal repository on large time scale in China. The change thermal rules of the thermal field for the disposal environment with time under the condition of decay and heat release of radioactive wastes were studied, and the impact of buffer materials with different thermal conductivity on the thermal field of the disposal environment was analyzed.
- high-level radioactive waste /
- geological disposal /
- buffer material /
- thermal analysis

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参考文献(19)

国防科学技术工业委员会,科学技术部,国家环境保护总局.高放废物地质处置研究发展规划指南[EB/OL].http://www.docin.com/p-1566715281.html.

吕涛,李昶,杨球玉,等.高放废物地质处置库热学分析的参数敏感性研究[J]. 辐射防护, 2015, 35(2):82-89.

李昶,李星宇,杨球玉,等. 我国高放废物深钻孔处置热学分析[J].工业建筑, 2018,48(4):36-39.

ITASCA Consulting Group, INC. FLAC3D(Fast Lagrangian Analysis of Continua in 3 Dimensions) User's Guide[M].Version 7.0. Grand Rapids, USA:Itasca Consulting Group,Inc.,2011.

胡斌,张倬元,黄润秋,等. FLAC3D前处理程序的开发及仿真效果检验[J]. 岩石力学与工程学报,2002,21(9):1387-1391.

Swedish Nuclear Fuel and Waste Management Co (SKB). SFL Concept Study:Main Report:SKB TR-13-14[R]. Stockholm,Sweden:SKB, 2013.

Swedish Nuclear Fuel and Waste Management Co (SKB). Heat Propagation in and Around the Deep Repository Thermal Calculation Supplied to Three Hypothetical Sites:Aberg, Beberg and Ceberg:SKB TR-99-02[R]. Stockholm,Sweden:SKB, 1999.

Swedish Nuclear Fuel and Waste Management Co (SKB). Thermal Dimensioning of the Deep Repository Influence of Canister Spacing, Canister Power, Rock Thermal Properties and Nearfield Design on the Maximum Canister Surface Temperature:SKB TR-03-09[R]. Stockholm,Sweden:SKB, 2003.

Swedish Nuclear Fuel and Waste Management Co (SKB). Strategy for thermal Dimensioning of the Final Repository for Spent Nuclear Fuel:SKB TR-09-04[R]. Stockholm,Sweden:SKB, 2009.

Swedish Nuclear Fuel and Waste Management Co (SKB). Thermal Evolution of the Repository-the Effect of Heat Generating Waste:SKB TR-18-04[R]. Stockholm, Sweden:SKB, 2018.

Swedish Nuclear Fuel and Waste Management Co (SKB). Thermal and Thermo-Mechanical Evolution of the Äspö Prototype Repository Rock Mass:SKB TR-13-10[R]. Stockholm,Sweden:SKB, 2013.

Swedish Nuclear Fuel and Waste Management Co (SKB). THM-issues in Repository Rock:Thermal, Mechanical, Thermo-Mechanical and Hydro-Mechanical Evolution of the Rock at the Forsmark and Laxemar Sites:SKB TR-10-23[R]. Stockholm,Sweden:SKB, 2010.

Swedish Nuclear Fuel and Waste Management Co (SKB). Äspö Pillar Stability Experiment, Final Report Rock Mass Response to Coupled Mechanical Thermal Loading:SKB TR-07-01[R]. Stockholm,Swedan:SKB, 2007.

侯伟,王旭宏,杨球玉,等. 我国高放废物地质处置库缓冲材料的设计要求[J]. 工业建筑, 2020,50(9):8-11.

殷玥,杨球玉,王旭宏,等. 我国和瑞典高放废物地质处置库中缓冲材料性质分析[J]. 工业建筑, 2020,50(9):34-37

,33.

李昱茜,侯伟,王旭宏,等. 我国高放废物地质处置库缓冲材料饱和密度影响因素分析[J]. 工业建筑, 2020,50(9):25-29

,74.

胡仁喜,龙凯,康士廷,等. Patran2014与Nastran2014有限元分析从入门到精通[M].北京:机械工业出版社,2017.

AGESKOG L, JANSSON P. Heat Propagation in and Around the Deep Repository[R]. SKB TR-99-02. Stockholm, Sweden:Swedish Nuclear Fuel and Waste Management Co. (SKB), 1999.

中国核电工程有限公司. 高放废物地下实验室和处置库概念设计[R]. 北京:中国核电工程有限公司,2011.

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