Radionuclide Retardation During Transport Through Fractured Granite

1981 ◽  
Vol 11 ◽  
Author(s):  
Ian G. McKinley ◽  
Julia M. West

In several countries low permeability crystalline rocks (e.g. granites) are under consideration as potential hosts for radioactive waste repositories. In such formations groundwater flow occurs predominantly in specific fractures rather than being a general porous flow through the entire rock matrix. By considering fractures to be simple parallel plates various authors have demonstrated the potential importance of diffusion into dead-end pores and the rock matrix itself (‘matrix diffusion’) as a mechanism for the retention of migrating radionuclides. Complementing these theoretical studies, several insitu migration experiments are planned in single fissures in crysalline rocks in Sweden, the U.K. and the U.S.A. The ‘parallel plate’ approximation to a single fissure is, however, acknowledged to be a gross simplification of any real case where “flowing” fractures are expected to be either filled or coated with secondary minerals, formed by hydrothermal alteration of fracture surfaces In the evaluation of net radio-nuclide retardation, therefore, the effect of sorption onto such secondary minerals must be carefully considered.

1985 ◽  
Vol 80 (1-2) ◽  
pp. 45-76 ◽  
Author(s):  
D.A. Lever ◽  
M.H. Bradbury ◽  
S.J. Hemingway

1985 ◽  
Vol 50 ◽  
Author(s):  
A. Atkinson ◽  
D. J. Goult ◽  
J. A. Hearne

AbstractA preliminary assessment of the long-term durability of concrete in a repository sited in clay is presented. The assessment is based on recorded experience of concrete structures and both field and laboratory studies. It is also supported by results of the examination of a concrete sample which had been buried in clay for 43 years.The enoineering lifetime of a 1 m thick reinforced concrete slab, with one face in contact with clay, and the way in which pH in the repository as a whole is likely to vary with time have both been estimated from available data. The estimates indicate that engineering lifetimes of about 103 years are expected (providing that sulphate resisting cement is used) and that pH is likely to remain above 10.5 for about 106 years.


1995 ◽  
Vol 412 ◽  
Author(s):  
K. Noshita ◽  
T. Nishi ◽  
M. Matsuda ◽  
T. Izumida

AbstractCarbon-14 sorption by cementitious materials should be enhanced to ensure the long term safety of radioactive waste repositories. The sorption mechanism of inorganic C- 14 (CO32- was investigated using batch sorption experiments and zeta potential measurements. The results suggested that C-14 was adsorbed onto the cement surface by an electrostatic force, due to the reaction between SiO2 and CaO contained in the cementitious composition. That is, SiO2 was originally negatively charged (SiO-) in cement, but became positively charged through the interaction of Ca2+. These positive sites on the SiO2 surface adsorbed inorganic C-14. Ordinary Portland cement (OPC) did not contain enough SiO2 compared with its CaO content to produce sufficient numbers of C-14 adsorption sites. The C-14 distribution coefficient (Kd) was increased from 2,000 to 7,000 mL/g by adding SiO2 to OPC.


2012 ◽  
Vol 1475 ◽  
Author(s):  
Ursula Alonso ◽  
Tiziana Missana ◽  
Miguel Garcia-Gutierrez ◽  
Henar Rojo ◽  
Alessandro Patelli ◽  
...  

ABSTRACTCement-based materials, like concrete and mortar, are widely used in radioactive waste repositories. A deep characterization of these heterogeneous materials, and of their main phases, is necessary to evaluate their capability of retaining critical radionuclides (RN).In this study, the ion beam technique micro- Particle Induced X- Ray Emission (μPIXE) is used to characterize the concrete and mortar used in the Spanish low level waste repository. Two calcium silicate hydrate (CSH) phases with different Ca/Si ratio are also studied, because they are known to be amongst the most relevant phases, formed upon cement hydration, that retain RN. The retention of thorium on the above mention materials, as relevant tetravalent actinide, is also analyzed. Results are compared with Scanning Electron Microscopy- Energy Dispersive X-Ray Spectroscopy (SEM-EDX) analyses.


2019 ◽  
Vol 95 (2) ◽  
pp. 133-139
Author(s):  
I. P. Korenkov ◽  
Tatyana N. Lashchenova ◽  
N. K. Shandala ◽  
V. V. Romanov

Algorithm for management of decision-making on the decommissioning of nuclear and radiation hazardous objects (RHO) should be both based on an comprehensive approach, with taking into account all the potential dangers, and relied upon on the requirements of a modern regulatory framework, as well as economically sound and socially oriented. The aim of the work was a development of a comprehensive approach to the assessment of the degree of the potential danger of near surface radioactive waste repositories in RHO, on the base of which it is possible to make substantiated management decisions for their decommissioning. Tasks: To develop an array of radio-ecological approaches, including radiation-hygienic, hydrogeological and engineering criteria for the assessment of the potential danger of radioactive waste repositories. Results There are presented radiation hygienic, hydrogeological and engineering and technical criteria on the basis of which there are calculated coefficients of the relative hazard of storages. In dependence to the value of the coefficients there are suggested four categories of danger - a safe, low dangerous, dangerous and very dangerous. There are elaborated approaches on management decisions-making in various variants of decommissioning - the conversion, renovation, conservation and liquidation.


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