THE USE OF CLAY AS AN ENGINEERED BARRIER IN RADIOACTIVE-WASTE MANAGEMENT - A REVIEW

被引:394
作者
Sellin, Patrik [1 ]
Leupin, Olivier X. [2 ]
机构
[1] SKB Swedish Nucl Fuel & Waste Management Co, Stockholm, Sweden
[2] NAGRA Natl Genossenschaft Lagerung Radioaktiver A, Wettingen, Switzerland
关键词
Bentonite; Barrier; Nuclear Waste; Geological Disposal; Waste Management; HIGH-LEVEL WASTE; SWELLING CHARACTERISTICS; BENTONITE; SMECTITE; MONTMORILLONITE; KINETICS; SORPTION; MODEL; COLORADO; SYSTEM;
D O I
10.1346/CCMN.2013.0610601
中图分类号
O64 [物理化学(理论化学)、化学物理学];
学科分类号
070304 ; 081704 ;
摘要
Geological disposal is the preferred option for the final storage of high-level nuclear waste and spent nuclear fuel in most countries. The selected host rock may be different in individual national programs for radioactive-waste management and the engineered barrier systems that protect and isolate the waste may also differ, but almost all programs are considering an engineered barrier. Clay is used as a buffer that surrounds and protects the individual waste packages and/or as tunnel seal that seals off the disposal galleries from the shafts leading to the surface. Bentonite and bentonite/sand mixtures are selected primarily because of their low hydraulic permeability in a saturated state. This ensures that diffusion will be the dominant transport mechanism in the barrier. Another key advantage is the swelling pressure, which ensures a self-sealing ability and closes gaps in the installed barrier and the excavation-damaged zone around the emplacement tunnels. Bentonite is a natural geological material that has been stable over timescales of millions of years and this is important as the barriers need to retain their properties for up to 10(6) y. In order to be able to license a final repository for high-level radioactive waste, a solid understanding of how the barriers evolve with time is needed. This understanding is based on scientific knowledge about the processes and boundary conditions acting on the barriers in the repository. These are often divided into thermal, hydraulic, mechanical, and (bio)chemical processes. Examples of areas that need to be evaluated are the evolution of temperature in the repository during the early stage due to the decay heat in the waste, re-saturation of the bentonite blocks installed, build-up of swelling pressure on the containers and the surrounding rock, and degradation of the montmorillonite component in the bentonite. Another important area of development is the engineering aspects: how can the barriers be manufactured, subjected to quality control, and installed? Geological disposal programs for radioactive waste have generated a large body of information on the safety-relevant properties of clays used as engineered barriers. The major relevant findings of the past 35 y are reviewed here.
引用
收藏
页码:477 / 498
页数:22
相关论文
共 75 条
[1]  
ANDRA, 2005, DOSS 2005 ARG ARCH M
[2]   Multicomponent diffusion of a suite of tracers (HTO, Cl, Br, I, Na, Sr, Cs) in asingle sample of Opalinus Clay [J].
Appelo, C. A. J. ;
Van Loon, L. R. ;
Wersin, P. .
GEOCHIMICA ET COSMOCHIMICA ACTA, 2010, 74 (04) :1201-1219
[3]  
Atomic Energy of Canada Limited (AECL), 1994, AECL Report No. AECL-10711, COG -93-1
[4]  
Birgersson M., 2010, TR1040 SKB
[5]   Ion equilibrium between montmorillonite interlayer space and an external solution-Consequences for diffusional transport [J].
Birgersson, Martin ;
Karnland, Ola .
GEOCHIMICA ET COSMOCHIMICA ACTA, 2009, 73 (07) :1908-1923
[6]   Freezing in saturated bentonite - A thermodynamic approach [J].
Birgersson, Martin ;
Karnland, Ola ;
Nilsson, Ulf .
PHYSICS AND CHEMISTRY OF THE EARTH, 2008, 33 (SUPPL. 1) :S527-S530
[7]  
Bock H., 2010, SELF SEALING FRACTUR
[8]  
Bradbury M.H., 1201 NTB
[9]   Experimental measurements and modeling of sorption competition on montmorillonite [J].
Bradbury, MH ;
Baeyens, B .
GEOCHIMICA ET COSMOCHIMICA ACTA, 2005, 69 (17) :4187-4197
[10]  
Burst J.F., 1959, Clays and Clay Minerals, V6, P327, DOI DOI 10.1346/CCMN.1957.0060124