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.

Environmental Remediation of High-Level Nuclear Waste in Geological Repository: Modified Computer Code Creates Ultimate Benchmark in Natural Systems

2010 ◽  
Author(s):  
Geoffrey J. Peter
Keyword(s):  
Nuclear Waste ◽  
Environmental Remediation ◽  
Computer Code ◽  
Nuclear Waste Repository ◽  
Natural Systems ◽  
Permanent Storage ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Waste Repositories

Isolation of high-level nuclear waste in permanent geological repositories has been a major concern for over 30 years due to the migration of dissolved radio nuclides reaching the water table (10,000-year compliance period) as water moves through the repository and the surrounding area. Repositories based on mathematical models allow for long-term geological phenomena and involve many approximations; however, experimental verification of long-term processes is impossible. Countries must determine if geological disposal is adequate for permanent storage. Many countries have extensively studied different aspects of safely confining the highly radioactive waste in an underground repository based on the unique geological composition at their selected repository location. This paper discusses two computer codes developed by various countries to study the coupled thermal, mechanical, and chemical process in these environments, and the migration of radionuclide. Further, this paper presents the results of a case study of the Magma-hydrothermal (MH) computer code, modified by the author, applied to nuclear waste repository analysis. The MH code verified by simulating natural systems thus, creating the ultimate benchmark. This approach based on processes similar to those expected near waste repositories currently occurring in natural systems.

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.

Application of Coupled Thermo-Hydro-Mechanical-Chemical (THMC) Processes in Hydrothermal Systems to Processes Near a High-Level Nuclear Waste Repository

2011 ◽  
Author(s):  
Geoffrey J. Peter
Keyword(s):  
Nuclear Waste ◽  
Transport Theory ◽  
Reaction Rates ◽  
Hydrothermal Systems ◽  
Coupled Processes ◽  
Nuclear Waste Repository ◽  
High Level Nuclear Waste ◽  
Waste Repository ◽  
High Level ◽  
Waste Repositories

Modeling of coupled processes in the geology near a high-level nuclear waste repository is similar to the modeling of coupled Thermo-Hydro-Mechanical-Chemical (THMC) processes that occur in magma-hydrothermal systems. Former Professor Denis Norton and his colleagues at the Geoscience Department at University of Arizona studied magma-hydrothermal systems extensively. These hydro-thermal codes were verified by obtaining excellent matches between calculated δ18O–values and measured δ18O–values in three principal rock units: basalt, gabbro, and gneiss. This paper reviews the concept of transport theory used in the formulation of the conservation principle used to model the hydrothermal systems. In addition, the paper reviews conservation of mass, momentum, energy, and chemical component equations as applied to the multicomponent-multiphase systems related to hydrothermal systems and obtains parallels to reaction rates and radionuclide transport in the geology of a high level nuclear water repository. Further, this paper compares published results obtained by other researchers modeling coupled THMC process in the geology of high-level nuclear waste repositories.

Introduction

2020 ◽  
pp. 1-19
Author(s):  
Rosemary A. Joyce
Keyword(s):  
Nuclear Waste ◽  
Common Sense ◽  
Planning Process ◽  
Pilot Project ◽  
The United States ◽  
Nuclear Waste Repository ◽  
Alternative Futures ◽  
Us Government ◽  
Marker Design ◽  
Waste Repositories

Providing an introduction to the planning process for the Waste Isolation Pilot Project and the marker design that continues to be the basis of nuclear waste repository proposals in the United States, including for Yucca Mountain, this chapter lays the groundwork for consideration of the contradictions between opinions produced through expert consultation and the expertise of archaeologists. US government efforts described enlisted a variety of “experts” to propose alternative futures, identify models for communication over long spans of time, and assess the likely durability of proposed designs for a marker over nuclear waste repositories. To understand these expert reports, this chapter introduces the concept of an anthropology of common sense as a way to understand how government experts understood the archaeological sites that they offered as models.

Sign in / Sign up

Export Citation Format

Share Document