Eu(III)在膨润土–砂混合物中的迁移试验研究

doi:10.13722/j.cnki.jrme.2014.s2.095

Abstract
Figure/Table
References (18)
Related Citation (0)

Download: PDF (791 KB) HTML (1 KB)
Export: BibTeX | EndNote (RIS)

Abstract Radionuclides will diffuse to the outside after the overpack has been destroyed in the high level radioactive waste(HLW) disposal. The diffusion coefficient of radionuclides in buffer backfilling material plays an important role in evaluating the property of the engineering barrier of disposal repository in HLW disposal. Taking 2.0×10－5 mol/L of Eu(III) solution as influent，the migration of Eu(III) in compacted GMZ bentonite-sand mixtures is studied under the conditions of convection，diffusion and adsorption；and the migration progress is modeled by the convection-dispersion equation. The fitting curves can fit the test data very well，which confirms the validity of experimental method. The effective diffusion coefficients and apparent diffusion coefficients of Eu(III) in compacted GMZ bentonite-sand mixtures are De = 1.62×10－12–4.87×10－12 m2/s，Da = 1.44×10－14–9.41×10－14 m2/s，respectively. And then，the effect of sand ratio on apparent diffusion coefficient is discussed. The research results can be used to forecast the relationship between migration length of Eu(III) in buffer backfilling material with time and provide a reference for the design of buffer backfilling material for HLW disposal in China.

Key words： soil mechanics Eu(III) bentonite-sand mixtures convection-dispersion equation diffusion coefficient high level radioactive waste

	Service

	E-mail this article
	Add to my bookshelf
	Add to citation manager
	E-mail Alert
	RSS
	Articles by authors
	ZHOU Lang
	ZHANG Huyuan
	CHEN Hang
	YAN Ming

Cite this article:

ZHOU Lang,ZHANG Huyuan,CHEN Hang, et al. LABORATORY RESEARCH ON MIGRATION OF EU(III) IN COMPACTED GMZ BENTONITE-SAND MIXTURES[J]. , 2014, 33(S2): 4163-4167.

URL:

https://rockmech.whrsm.ac.cn/EN/10.13722/j.cnki.jrme.2014.s2.095 OR https://rockmech.whrsm.ac.cn/EN/Y2014/V33/IS2/4163

[1]	PUSCH R. Highly compacted sodium bentonite for isolating rock-deposited radioactive waste products[J]. Nuclear Technology，1979，45(9)：153-157.
[2]	王驹，张铁岭. 世界放射性废物地质处置[M]. 北京：原子能出版社，1999.(WANG Ju，ZHANG Tieling. Geological disposal of radioactive waste in the world[M]. Beijing：Atomic Energy Press，1999(in Chinese))
[3]	罗嗣海，钱七虎，周文斌，等. 高放废物深地质处置及其研究概况[J].岩石力学与工程学报，2004，23(5)：831-838.(LUO Sihai，QIAN Qihu，ZHOU Wenbin，et al. Deep geological disposal of high-level nuclear waste and its research outlines[J]. Chinese Journal of Rock Mechanics and Engineering，2004，23(5)：831-838.(in Chinese))
[4]	WANG XK，CHEN YX，WU YC. Diffusion of Eu(III) in compacted bentonite-effect of pH，solution concentration and humic acid[J] Applied Radiation and Isotopes，2004，60(6)：963-969.
[5]	GARCÍA-GUTIÉRREZ M，CORMENZANA JL，MISSANAT，et al. Diffusion of strongly sorbing cations(60Co and 152Eu) in compacted FEBEX bentonite[J]. Physics and Chemistry of the Earth，2011，36(17)：1708-1713.
[6]	TORSTENFELT B，ALLARD B. Radionuclide diffusion and mobilitiesin compacted bentonite[R]. [S. l.]：TR83-34，1983.
[7]	LEE JO，CHO WJ，HAHN PS，et al. Effect of dry density on Sr-90 diffusion in a compacted Ca-bentonite for a backfill of radioactive waster repository[J]. Annals of Nuclear Energy，1996，23(9)：121-138.
[8]	SHACKELFORD CD. Laboratory diffusion testing for waste disposal—areview[J]. Journal of Contaminant Hydrology，1991，(7)：177-217.
[9]	VAN GENUCHTEN MT，WIERENGA PJ. Solute dispersion coefficients and retardation factors[C]//Methods of Soil Analysis.KLUTEA ed.New York：American Society of Agronomy，1986：1025-1054.
[10]	陈崇希，李国敏. 地下水溶质运移理论及模型[M].北京：中国地质大学出版社，1996：45-46.(LIChongxi，LI Guomin. Theory and model of solute transport in groundwater[M]. Beijing：China Universityof Geosciences Press，1996：45-46.(in Chinese))
[11]	李韵珠，李保国. 土壤溶质运移[M].北京：科学出版社，1998：277.(LIYunzhu，LI Baoguo. Solute transport in soil[M]. Beijing：Science Press，1998：277.(in Chinese))
[12]	HAMAMOTOS，PERERAM S A，RESURRECCIONA，et al. The solute diffusion coefficient in variably compacted，unsaturated volcanicash soils[J]. Vadose Zone Journal，2009，(8)：942-952.
[13]	CHOWJ，LEE JO，KANG CH. Hydraulic conductivity of bentonite-sand mixtures for a potential backfill material for a high-level radioactive waste repository[J]. Journal of the Korean Nuclear Society，2000，32(5)：495-503.
[14]	ABICHOUT，BENSONH B，EDILT B. Micro-structure and hydraulic conductivity of simulated sand-bentonite mixtures[J]. Clays and Clay Minerals，2002，50(5)：537-545.
[15]	KOMINE H. Simplified evaluation on hydraulic conductivities of sand-bentonite mixture backfill[J].Applied Clay Science，2004，26(1)：13-19.
[16]	AMETA NK，WAYAL AS. Effect of bentonite on permeability of dune sand[J]. Electronic Journal of Geotechnical Engineering，2008，13(A)：1-7.
[17]	张虎元，赵天宇，卢一亭，等. 膨胀条件下混合型缓冲回填材料的渗透特性[J]. 岩石力学与工程学报，2011，30(增1)：3149-3156.(ZHANG Huyuan，ZHAO Tianyu，LU Yiting，et al. Permeability of bentonite-sand mixtures as backfill/buffer material in HLW disposal under swelling conditions[J]. Chinese Journal of Rock Mechanics and Engineering，2011，30(Supp.1)：3149-3156.(in Chinese))
[18]	WANG X K，TAN X L，NING Q L，et al.Simulation of radionuclides 99Tc and 243Am migration in compacted bentonite[J]. Applied Radiation and Isotopes，2005，62(5)：759-764.