scholarly journals Comment on “Modelling coseismic displacements of fracture systems in crystalline rock during large earthquakes: Implications for the safety of nuclear waste repositories” as published by Lei and Loew (2021) in IJRMMS, 138, 104590

2021 ◽  
pp. 105013
Author(s):  
Billy Fälth ◽  
Susanne Grigull ◽  
Jenny Gåling ◽  
Diego Mas Ivars ◽  
Frederic Wagner
Keyword(s):  
Nuclear Waste ◽  
Crystalline Rock ◽  
Fracture Systems ◽  
Waste Repositories ◽  
Large Earthquakes

High-level nuclear waste management: a geochemical perspective

1989 ◽  
Vol 16 (4) ◽  
pp. 498-503
Author(s):  
T. T. Vandergraaf
Keyword(s):  
Contaminant Transport ◽  
Nuclear Waste ◽  
Fission Products ◽  
Crystalline Rock ◽  
Nuclear Waste Management ◽  
Geochemical Processes ◽  
Fracture Systems ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Canada Limited

Atomic Energy of Canada Limited is investigating the concept of the disposal of high-level radioactive waste in an underground vault in an intrusive crystalline rock formation. The environmental impact of such a disposal is, to a large extent, dictated by geochemical processes involving rock-forming minerals, groundwater, and fission products and actinides in the waste. These various geochemical processes impact on the transport of contaminants, including radionuclides and chemically toxic elements, from a used-fuel disposal vault towards the biosphere. The extent and importance of the geochemical processes on contaminant transport are discussed. The predominant processes controlling the velocity of contaminant transport are the various geochemical interactions of the dissolved contaminant species with the minerals lining the surfaces of conductive fractures and fracture systems. Key words: radionuclide, uranium, nuclear contaminant, transport, sorption, diffusion, geochemistry, fission products, granite.

Nuclear Waste Repositories in Crystalline Rock- an Overview of Flow and Nuclide Transport Mechanisms

1994 ◽  
Vol 353 ◽  
Author(s):  
Ivars Neretnieks
Keyword(s):  
Nuclear Waste ◽  
Field Experiments ◽  
Fracture Network ◽  
Crystalline Rock ◽  
Transport Mechanisms ◽  
The Matrix ◽  
Nuclide Transport ◽  
Waste Repositories ◽  
And Diffusion ◽  
Diffusion Properties

AbstractNuclides eventually escaping from nuclear waste repositories in crystalline rock will move with the seeping water in the fracture network. Most important nuclides interact physically or chemically with the rock and are expected to be considerably retarded allowing them to decay to insignificant concentrations. Velocity variations may allow some portions of the nuclides to move faster. Matrix diffusion and sorption on the surfaces of the rock are by far the most powerful retardation mechanisms and depend, in addition to the sorption and diffusion properties, directly on the magnitude of the “flow wetted surface”which is the contact surface between the mobile water carrying the nuclides and the fracture surfaces over which the nuclides diffuse into the matrix.A number of field experiments have been performed over the last 15 years to help validate the concepts and models and to obtain data. A number of such experiments are described and discussed in relation to the above issues.

Changes of Selected Structural and Mechanical Properties of the Strzelin Granites As Induced By Thermal Loads / Wpływ Obciążeń Termicznych Na Zmiany Niektórych Strukturalnych I Mechanicznych Właściwości Granitów Strzelińskich

2012 ◽  
Vol 57 (4) ◽  
pp. 951-974 ◽  
Author(s):  
Andrzej Nowakowski ◽  
Mariusz Młynarczuk
Keyword(s):  
Mechanical Properties ◽  
Nuclear Waste ◽  
Structural Changes ◽  
Structural Parameters ◽  
Total Porosity ◽  
Fracture Network ◽  
Qualitative Description ◽  
Temperature Changes ◽  
Heating And Cooling ◽  
Waste Repositories

Abstract Temperature is one of the basic factors influencing physical and structural properties of rocks. A quantitative and qualitative description of this influence becomes essential in underground construction and, in particular, in the construction of various underground storage facilities, including nuclear waste repositories. The present paper discusses the effects of temperature changes on selected mechanical and structural parameters of the Strzelin granites. Its authors focused on analyzing the changes of granite properties that accompany rapid temperature changes, for temperatures lower than 573ºC, which is the value at which the β - α phase transition in quartz occurs. Some of the criteria for selecting the temperature range were the results of measurements carried out at nuclear waste repositories. It was demonstrated that, as a result of the adopted procedure of heating and cooling of samples, the examined rock starts to reveal measurable structural changes, which, in turn, induces vital changes of its selected mechanical properties. In particular, it was shown that one of the quantities describing the structure of the rock - namely, the fracture network - grew significantly. As a consequence, vital changes could be observed in the following physical quantities characterizing the rock: primary wave velocity (vp), permeability coefficient (k), total porosity (n) and fracture porosity (η), limit of compressive strength (Rσ1) and the accompanying deformation (Rε1), Young’s modulus (E), and Poisson’s ratio (ν).

Experimental study and modeling of uranium (VI) transport through ferrous olivine rock columns

2000 ◽  
Vol 88 (9-11) ◽  
Author(s):  
M. Rovira ◽  
F.Z. El Aamrani ◽  
L. Duro ◽  
Ignasi Casas ◽  
Joan de Pablo ◽  
...  
Keyword(s):  
Nuclear Waste ◽  
Reactive Transport ◽  
Calculated Data ◽  
Buffering Capacity ◽  
Retardation Factor ◽  
Reactive Transport Modeling ◽  
Redox Active ◽  
Different Types ◽  
Free Media ◽  
Waste Repositories

The Lovasjärvi intrusion (SE-Finland) contents a high percentage of ferrous olivine (> 65%). This material has been suggested as a redox-active backfill-additive in deep nuclear waste repositories, due to the large Fe(II) proportion in its mineral composition. In order to understand the processes involved in the redox buffering capacity of this material the transport of uranium (VI) through olivine columns was studied. The results showed considerable retardation factor for the U(VI), particularly in carbonate-free media. The experimental data were simulated by means of reactive transport modeling. The best agreement between the experimental and calculated data was obtained considering that the interaction of U(VI) with the olivine surface occurred at two different types of sorption sites. One type accounts for the sorption capacity of the olivine mineral, and a second type accounts for the sorption on amorphous Fe(OH)

scholarly journals Geologic environments for nuclear waste repositories

2017 ◽  
Vol 120 ◽  
pp. 06003 ◽  
Author(s):  
Evan K. Paleologos ◽  
Abdel-Mohsen O. Mohamed ◽  
Kosmas Pavlopoulos
Keyword(s):  
Nuclear Waste ◽  
Waste Repositories

Perceived Risk and Benefit of Nuclear Waste Repositories: Four Opinion Clusters

Risk Analysis ◽  
2012 ◽  
Vol 33 (6) ◽  
pp. 1038-1048 ◽  
Author(s):  
Roman Seidl ◽  
Corinne Moser ◽  
Michael Stauffacher ◽  
Pius Krütli
Keyword(s):  
Nuclear Waste ◽  
Perceived Risk ◽  
Risk And Benefit ◽  
Waste Repositories
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