我国和瑞典高放废物地质处置库中缓冲材料性质分析

殷玥; 杨球玉; 王旭宏; 侯伟; 吕涛; 李昱茜; 夏加国; 吕敏

doi:10.13204/j.gyjzG20063015

我国和瑞典高放废物地质处置库中缓冲材料性质分析

doi: 10.13204/j.gyjzG20063015

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（[2017]1405号）。

详细信息

作者简介:
殷玥,女,1992年出生,硕士,工程师。电子信箱:yiny_cnpe@163.com

计量
- 文章访问数: 102
- HTML全文浏览量: 10
- PDF下载量: 0
- 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 CHARACTERISTICS OF BUFFER MATERIALS IN GEOLOGICAL DISPOSAL REPOSITORIES FOR HIGH-LEVEL WASTES IN CHINA AND SWEDEN

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

摘要

摘要: 缓冲材料是高放废物地质处置工程屏障系统的重要组成部分。基于瑞典缓冲材料MX-80膨润土的物理性质，对设计要求的主要参数如渗透系数、膨胀力、材料成分开展分析，并以缓冲材料饱和密度作为长期安全性评价指标分析主要影响因素（外间隙宽度、砌块和小球的干密度），为我国高放废物地质处置库缓冲材料的设计提供参考。
- 高放废物 /
- 地质处置 /
- 工程屏障 /
- 缓冲材料
Abstract: Buffer materials are important parts of barrier systems in geological disposal of high-level radioactive wastes. Based on the physical properties of MX-80 bentonite, a Swedish buffer material, the design parameters such as permeability coefficients, swelling forces and material composition were analyzed. The saturated densities of buffer materials were taken as the long-term safety evaluation indexes to analyze the main influencing factors (outer clearance widths, densities of blocks and pellets), which could provide reference to design of buffer materials in geological disposal for high-level wastes in China.
- high-level radioactive waste /
- geological disposal /
- engineering barrier /
- buffer material

HTML全文

参考文献(10)

KARNLAND O, OLSSON S, NILSSON U. Mineralogy and Sealing Properties of Various Bentonites and Smectite-Rich Clay Minerals:SKB TR-06-30[R]. Stockholm, Sweden:Swedish Nuclear Fuel and Waste Management Co(SKB),2006.

VILLAR M V, GOMEZ ESPINA R. Effect of Temperature on the Water Retention Capacity of FEBEX and MX-80 Bentonites[C]//1st European Conference on Unsaturated Soils:Advances in Geoengineering. 2008:257-262.

Swedish Nuclear Fuel and Waste Management Co(SKB). Long Term Safety for KBS-3 Repositories at Forsmark and Laxemar:A First Evaluation. Main Report of the SR-Can Project:SKB TR-06-09[R]. Stockholm, Sweden:SKB,2006.

Swedish Nuclear Fuel and Waste Management Co(SKB).Design, Production and Initial State of the Buffer:SKB TR-10-15[R]. Stockholm, Sweden:SKB,2010.

Swedish Nuclear Fuel and Waste Management Co(SKB).Buffer and Backfill Process Report for the Safety Assessment SR-Can:SKB TR-06-18[R]. Stockholm, Sweden:SKB,2006.

PUSCH R. The Buffer and Backfill Handbook, Part 1:Definitions, Basic Relationships, and Laboratory Methods:SKB TR-02-20[R]. Stockholm, Sweden:Swedish Nuclear Fuel and Waste Management Co(SKB),2002.

刘月妙,徐国庆,刘淑芬. 我国高放废物处置库缓冲/回填材料压实膨胀特性研究[J]. 铀矿地质,2001(1):44-47.

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.

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.

李昱茜,杨球玉,王旭宏,等. 我国高庙子膨润土和日本高放废物地质处置库中缓冲材料物理性质分析[J].工业建筑,2020,50(9):30-33.

施引文献

资源附件(0)

访问统计