Please wait a minute...
 首页  期刊介绍 期刊订阅 联系我们
 
最新录用  |  预出版  |  当期目录  |  过刊浏览  |  阅读排行  |  下载排行  |  引用排行  |  百年期刊
Journal of Tsinghua University(Science and Technology)    2017, Vol. 57 Issue (4) : 410-414     DOI: 10.16511/j.cnki.qhdxxb.2017.25.013
NUCLEAR ENERGY AND NEW ENERGY |
Radiation stability of a cementation matrix for spent radioactive resin
LI Junfeng1, QIU Yu1, WANG Jianlong1,2
1. Collaborative Innovation Center for Advanced Nuclear Energy Technology, Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China;
2. Beijing Key Laboratory of Radioactive Waste Treatment, Tsinghua University, Beijing 100084, China
Download: PDF(1378 KB)  
Export: BibTeX | EndNote | Reference Manager | ProCite | RefWorks    
Abstract  The radiation stability of the cementation matrix for spent radioactive resin when exposed to high radioactive fluxes was investigated using a sulfoaluminate cementation matrix for radioactive waste. The variation of the compressive strength after irradiation, the strength losses after freezing and the leach rate were compared for various γ-ray radiation doses. The microstructures of the hydration products in the irradiated cementation matrix were observed using an SEM. The results show that the radiation reduces the compressive strength of the cementation matrix with the losses increasing with the dose. The strength losses after freezing were also increased by the radiation. The adsorption of leaching ions was reduced. The aluminium micelles in the microstructure were reduced. The radiation may cause the decomposition of the aluminium micelles, which may led to the increased radionuclide leach rate. The results also showed that the matrix stability was not affected by the radiation when the total absorbed dose was below 105Gy.
Keywords radioactive waste resin      cementation      radiation stability      compressive strength      leaching rate     
ZTFLH:  X591  
Issue Date: 15 April 2017
Service
E-mail this article
E-mail Alert
RSS
Articles by authors
LI Junfeng
QIU Yu
WANG Jianlong
Cite this article:   
LI Junfeng,QIU Yu,WANG Jianlong. Radiation stability of a cementation matrix for spent radioactive resin[J]. Journal of Tsinghua University(Science and Technology), 2017, 57(4): 410-414.
URL:  
http://jst.tsinghuajournals.com/EN/10.16511/j.cnki.qhdxxb.2017.25.013     OR     http://jst.tsinghuajournals.com/EN/Y2017/V57/I4/410
  
  
  
  
  
  
[1] International Atomic Energy Agency. Application of Ion Exchange Processes for the Treatment of Radioactive Waste and Management of Spent Ion Exchangers, No. 408[R]. Vienna: IAEA, 2002.
[2] 施仲齐, 方栋, 云桂春. 核电站的环境影响[M]. 北京: 水利电力出版社, 1984. SHI Zhongqi, FANG Dong, YUN Guichun. The Environment Impaction of Nuclear Power Plant[M]. Beijing: Water & Power Press, 1984. (in Chinese)
[3] International Atomic Energy Agency. Treatment of Spent Ion-exchange Resins for Storage and Disposal, No. 254[R]. Vienna: IAEA, 1985.
[4] Atabek R, Bouniol P, Vitorge P, et al. Cement use for radioactive-waste embedding and disposal purposes[J]. Cement and Concrete Research, 1992, 22(2-3): 419-429.
[5] 王韧, 杨景田. 压水堆核电站放射性废液的水泥固化研究[J]. 辐射防护, 1982, 2(5): 352-360.WANG Ren, YANG Jingtian. Studies on cement solidification of radioactive waste solutions produced from PWR nuclear power plant[J]. Radiation Protection, 1982, 2(5): 352-360. (in Chinese)
[6] 罗上庚. 废离子交换树脂的优化处理[J]. 核科学与工程, 2003, 23(2): 165-172.LUO Shanggeng. Optimal treatment of spent ion exchange resin[J]. Chinese Journal of Nuclear Science and Engineering, 2003, 23(2): 165-172. (in Chinese)
[7] 周耀中. 放射性废离子交换树脂的水泥固化技术研究与机理探讨[D]. 北京: 清华大学, 2002.ZHOU Yaozhong. Mechanism Study on Solidification of Radioactive Spent Resin Using ASC Cement[D]. Beijing: Tsinghua University, 2002. (in Chinese)
[8] LI Junfeng, ZHAO Gang, WANG Jianlong. Solidification of low-level-radioactive resins in ASC-zeolite blends[J]. Nuclear Engineering and Design, 2005, 235(7): 817-820.
[9] 李俊峰, 王建龙, 叶裕才. 模拟放射性废树脂的沸石和特种水泥混合物固化[J]. 原子能科学技术, 2006, 40(3): 288-291.LI Junfeng, WANG Jianlong, YE Yucai. Solidification of radioactive resin by using ASC cement and zeolite blends[J]. Atomic Energy Science and Technology, 2006, 40(3): 288-291. (in Chinese)
[10] LI Junfeng, WANG Jianlong. Advances in cement solidification technology for waste radioactive ion exchange resins: A review[J]. Journal of Hazardous Materials, 2006, 135(1-3): 443-448.
[11] 周耀中, 叶裕才, 云桂春, 等. 特种水泥固化放射性废离子交换树脂的初步研究[J]. 辐射防护, 2002, 22(4): 225-230. ZHOU Yaozhong, YE Yucai, YUN Guichun, et al. Study on solidification of spent ion exchange resin using ASC cement[J]. Radiation Protection, 2002, 22(4): 225-230. (in Chinese)
[12] 孙奇娜, 李俊峰, 王建龙. 模拟放射性含硼废液的水泥固化研究[J]. 原子能科学技术, 2010, 44(S1): 153-158. SUN Qina, LI Junfeng, WANG Jianlong. Study on cementation of simulated radioactive borated liquid wastes[J]. Atomic Energy Science and Technology, 2010, 44(S1): 153-158. (in Chinese)
[13] 沈晓冬, 严生, 吴学权, 等. 水泥固化体的铯的浸出行为[J]. 核科学与工程, 1994, 14(2): 134-140.SHEN Xiaodong, YAN Sheng, WU Xuequan, et al. The Cs leach behaviour of cement waste form[J]. Chinese Journal of Nuclear Science and Engineering, 1994, 14(2): 134-140. (in Chinese)
[14] Gougar M, Scheetz B E, Roy D M. Ettringite and C-S-H Portland cement phases for waste ion immobilization: A review[J]. Waste Management, 1996, 16(4): 295-303.
[15] Glasser F P. Progress in the immobilization of radioactive wastes in cement[J]. Journal of Hazardous Materials, 1992, 22(2-3): 201-216.
[16] GB 14569.1—2011. 低、 中水平放射性废物固化体性能要求—水泥固化体[S]. 北京: 环境保护部, 中华人民共和国国家质量监督检验检疫总局, 2011.GB 14569.1—2011. Performance Requirements for Low and Intermediate Level Radioactive Waste Form-Cemented Waste Form[S]. Beijing: Ministry of Environmental Protection, General Administration of Quality Supervision Inspection and Quarantine, 2011. (in Chinese)
[17] GB/T 7023—2011. 低、 中水平放射性废物固化体标准浸出试验方法[S]. 北京: 环境保护部, 中华人民共和国国家技术监督局, 2011.GB/T 7023—2011. Standard Test Method for Leachability of Low and Intermediate Level Solidified Radioactive Waste Forms[S]. Beijing: Ministry of Environmental Protection, General Administration of Quality Supervision Inspection and Quarantine, 2011. (in Chinese)
[1] WANG Qiang, YANG Jun, WANG Dengquan. Properties of the reaction products of alkali-activated electric furnace nickel slag[J]. Journal of Tsinghua University(Science and Technology), 2018, 58(6): 593-597,602.
[2] ZHANG Zengqi, SHI Mengxiao, WANG Qiang, CUI Qiang. Accuracy of equivalent age method for predicting mass concrete properties[J]. Journal of Tsinghua University(Science and Technology), 2016, 56(8): 806-810.
[3] ZHANG Wenfeng, LI Junfeng, WANG Jianlong. Effect of emulsifiers on the cementation of spent radioactive organic solvents[J]. Journal of Tsinghua University(Science and Technology), 2015, 55(6): 666-671.
Viewed
Full text


Abstract

Cited

  Shared   
  Discussed   
Copyright © Journal of Tsinghua University(Science and Technology), All Rights Reserved.
Powered by Beijing Magtech Co. Ltd