Risk Assessment as a Framework for Decisions on Research and Data-Collection for Nuclear-Waste Repositories With Application to Carbon Sequestration Monitoring

2010 ◽  
Author(s):  
Rob P. Rechard ◽  
Sean Mckenna ◽  
David Borns
Keyword(s):  
Risk Assessment ◽  
Carbon Sequestration ◽  
Data Collection ◽  
Nuclear Waste ◽  
Waste Repositories

Condiment: Source Code for Risk Assessment of French Nuclear Waste Repository

1988 ◽  
Vol 127 ◽  
Author(s):  
J. P. Mangin ◽  
E. Mouche ◽  
P. Lovera ◽  
H. Nguyen Ngoc
Keyword(s):  
Risk Assessment ◽  
Nuclear Waste ◽  
Source Code ◽  
Computer Code ◽  
Nuclear Waste Repository ◽  
Single Element ◽  
Aqueous Corrosion ◽  
High Level ◽  
Diffusion Convection ◽  
Waste Repositories

ABSTRACTCONDIMENT is the source code used in MELODIE, the overall French computer code for risk assessment of nuclear waste repositories in geological formations. This code models the diffusion-convection of elements released by a waste package, up to a distance of a few meters from the package. Two versions have been developed simultaneously:- CONDIMENT2 deals with the case of a single element. This version is more specifically designed for vitrified high-level wastes. The boundary conditions are furnished by studies on aqueous corrosion of French nuclear glass R7T7.- CONDIMENT3, deals with two ions that are liable to precipitate. This version is more specifically designed for wastes immobilized in cement.CONDIMENT3 is verified in a configuration for which an analytical solution exists.

Development of the Code Melodie for Long Term Risk Assessment of Nuclear Waste Repositories

1985 ◽  
Vol 50 ◽  
Author(s):  
P. Goblet ◽  
P. Guetat ◽  
J. Lewi ◽  
J-P Mangin ◽  
G. De Marsily ◽  
...  
Keyword(s):  
Risk Assessment ◽  
Nuclear Waste ◽  
Computer Code ◽  
Source Model ◽  
High Level Waste ◽  
Chemical Components ◽  
Advection Dispersion ◽  
The Individual ◽  
High Level ◽  
Waste Repositories

AbstractMELODIE is a computer code developed at the CEA/IPSN for risk assessment of nuclear waste repositories in geological formations. The interactive evolution of the source, geosphere and biosphere is studied for periods of time longer than 100 000 years. In its first version, the code can describe a repository in granite rock located at a specific site.The code is built in a modular form which allows to use different versions of the sub-system models.The basic model for radionuclide migration and hydrpgeology is a subroutine version of the METIS code developed by ENSMP. METIS is a 2D finite element code which solves the advection-dispersion equation for porous media with explicit fracture representation. Linear adsorption kinetics is included as well as matrix diffusion and radionuclide decay chains.The source model developed at CEA/DRDD**** is derived from CONDIMENT which is a 1D finite difference code describing the behaviour of high level waste packages. Four axisymetric layers are individualized: glass matrix, container, bentonite and granite. The glass leaching is modelled as a dissolution and diffusion process of the individual chemical components.The biosphere model ABRICOT developed at the CEA/DPT** is based on a detailed description of agricultural activities defined in individual systems.MELODIE is tested by participation to international exercices such as Pagis [1], Intracoin [2] and Hydrocoin [3]. Future developments will include introduction of scenarios constructed from geoprospective studies and algorithms for sensitivity studies.

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)

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