Wellenberg, Switzerland: Controls on Groundwater Flow and Solute Transport Derived From Hydrochemical Observations

1997 ◽  
Vol 506 ◽  
Author(s):  
H. N. Waber ◽  
F. J. Pearson ◽  
A. Scholtis
Keyword(s):  
Radioactive Waste ◽  
Groundwater Flow ◽  
Solute Transport ◽  
Host Rock ◽  
Intermediate Level ◽  
Isotopic Data ◽  
The North ◽  
Central Switzerland ◽  
Waste Repository ◽  
Intermediate Level Radioactive Waste

The Wellenberg area, central Switzerland, is under investigation for a potential low and intermediate level radioactive waste repository. The host rock, the Palfris marl, is bounded on the north by Cretaceous limestone units of the Drusberg nappe and is underlain by a sequence of Tertiary to Jurassic sediments (limestones, marls) of the Wissberg-Firrenband-Equivalent. Chemical and isotopic data on groundwaters and rocks show that three essentially independent groundwater flow regimes occur in the area: (1) groundwaters of the Palfris marl, (2) groundwaters of the limestone units of the Drusberg nappe, and (3) groundwaters of the Wissberg-Firrenband Equivalent.

The Hydrogeologic Environment for a Proposed Deep Geologic Repository in Canada for Low and Intermediate Level Radioactive Waste

2011 ◽  
Author(s):  
Jonathan F. Sykes ◽  
Stefano D. Normani ◽  
Yong Yin ◽  
Mark R. Jensen
Keyword(s):  
Radioactive Waste ◽  
Solute Transport ◽  
Regional Scale ◽  
Intermediate Level ◽  
Geologic Repository ◽  
Site Specific ◽  
Ordovician Limestone ◽  
Intermediate Level Radioactive Waste ◽  
The Impact

A Deep Geologic Repository (DGR) for low and intermediate level radioactive waste has been proposed by Ontario Power Generation for the Bruce nuclear site in Ontario, Canada. As proposed the DGR would be constructed at a depth of about 680 m below ground surface within the argillaceous Ordovician limestone of the Cobourg Formation. This paper describes the hydrogeology of the DGR site developed through both site characterization studies and regional-scale numerical modelling analysis. The analysis provides a framework for the assembly and integration of the site-specific geoscientific data and examines the factors that influence the predicted long-term performance of the geosphere barrier. Flow system evolution was accomplished using both the density-dependent FRAC3DVS-OPG flow and transport model and the two-phase gas and water flow computational model TOUGH2-MP. In the geologic framework of the Province of Ontario, the DGR is located on the eastern flank of the Michigan Basin. Borehole logs covering Southern Ontario combined with site-specific data from 6 deep boreholes have been used to define the structural contours and hydrogeologic properties at the regional-scale of the modelled 31 sedimentary strata that may be partially present above the Precambrian crystalline basement rock. The regional-scale domain encompasses an approximately 18500km2 region extending from Lake Huron to Georgian Bay. The groundwater zone below the Devonian includes units containing stagnant water having high concentrations of total dissolved solids that can exceed 300g/L. The Ordovician sediments are significantly under-pressured. The horizontal hydraulic conductivity for the Cobourg limestone is estimated to be 2 × 10−14 m/s based on straddle-packer hydraulic tests. The low advective velocities in the Cobourg and other Ordovician units result in solute transport that is diffusion dominant with Peclet numbers less than 0.003 for a characteristic length of unity. Long-term simulations that consider future glaciation scenarios include the impact of ice thickness and permafrost. Solute transport in the Ordovician limestone and shale was diffusion dominant in all simulations. The Salina formations of the Upper Silurian prevented the deeper penetration of basal meltwater.

Preliminary Safety Analysis of the Baita Bihor Radioactive Waste Repository, Romania

2007 ◽  
Author(s):  
Richard Little ◽  
Felicia Dragolici ◽  
Alex Bond ◽  
Ludovic Matyasi ◽  
Sandor Matyasi ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Environmental Monitoring ◽  
Conceptual Models ◽  
Intermediate Level ◽  
Current Estimate ◽  
Research Activities ◽  
New Information ◽  
Depth Analysis ◽  
Waste Repository ◽  
Intermediate Level Radioactive Waste

A project funded under the European Commission’s Phare Programme 2002 has undertaken an in-depth analysis of the operational and post-closure safety of the Baita Bihor repository. The repository has accepted low- and some intermediate-level radioactive waste from industry, medical establishments and research activities since 1985 and the current estimate is that disposals might continue for around another 20 to 35 years. The analysis of the operational and post-closure safety of the Baita Bihor repository was carried out in two iterations, with the second iteration resulting in reduced uncertainties, largely as a result taking into account new information on the hydrology and hydrogeology of the area, collected as part of the project. Impacts were evaluated for the maximum potential inventory that might be available for disposal to Baita Bihor for a number of operational and post-closure scenarios and associated conceptual models. The results showed that calculated impacts were below the relevant regulatory criteria. In light of the assessment, a number of recommendations relating to repository operation, optimisation of repository engineering and waste disposals, and environmental monitoring were made.

Safety Analysis for the Loviisa Low- and Intermediate-Level Radioactive Waste Repository

1997 ◽  
Vol 506 ◽  
Author(s):  
T. Eurajoki ◽  
S. Outa ◽  
T. Routamo
Keyword(s):  
Radioactive Waste ◽  
Sea Level ◽  
Safety Analysis ◽  
Intermediate Level ◽  
Radioactive Waste Repository ◽  
Waste Repository ◽  
Intermediate Level Radioactive Waste

ABSTRACTThe Loviisa low and intermediate level radioactive waste repository is located in southern Finland, at Loviisa NPP site on Hästholmen island, where two VVER-440 reactor units are operated by Imatran Voima Oy (IVO). The repository is excavated in the bedrock, 110 meters below the sea level.

Hydro-geochemical processes in the emplacement cavern of a low and intermediate-level waste repository in an indurated clay-rock

2021 ◽  
Author(s):  
Vanessa Montoya ◽  
Jaime Garibay-Rodriguez ◽  
Olaf Kolditz
Keyword(s):  
Chemical Evolution ◽  
Nuclear Waste ◽  
Host Rock ◽  
Numerical Models ◽  
Intermediate Level ◽  
High Level Waste ◽  
Nuclear Waste Repository ◽  
Case Scenario ◽  
Damaged Zone ◽  
Waste Repository

<p>By 2080, Germany will have to store around 600 000 m<sup>3</sup> of low and intermediate-level nuclear waste (L-ILW) with negligible heat generation. This kind of waste is largely made up of used parts of nuclear power stations such as pumps, pipelines, filters, etc. placed in various types of waste containers made from either steel, cast iron, or reinforced concrete in different designs and sizes (i.e. cylindrical or box shaped). It is already decided that a total of 303 000 of the 600 000 m<sup>3</sup> L-ILW will be disposed in a final storage facility in the former iron ore mine Schacht Konrad which is under construction. However, it is still not clear where the L-ILW emplaced in in the old salt mine Asse (200 000 m<sup>3</sup>) will be stored in the future. The situation is particularly critical, as the waste have to be retrieved from the instable mine shafts partially flooded with groundwater, causing strong socio-political concerns as radioactive waste could contaminate the water nearby. For this reason, the new search for a nuclear waste repository for high-level waste (HLW), started in 2017, should also consider the possibility to accommodate the waste from Asse. Obviously, this is still subject to critics as this will make finding a final repository more difficult as storing HLW and L-ILW together requires different concepts and designs for each other and, above all, much more space.</p><p>In this context, in this contribution we have defined conceptual and numerical models to assess the hydro-chemical evolution of a L-ILW disposal cell in indurated clay rocks, involving the interaction of different components/materials and the expected hydraulic and/or chemical gradients over 100 000 years. The L-ILW disposal cell leverages a multi-barrier concept buried 400 m below the surface. The multi-barrier system is comprised of the waste matrix (i.e. backfilling the waste drums), the disposal container, the mortar backfill in the emplacement tunnel (where the disposal containers are located) and the clay host rock. The dimensions and design of the emplacement tunnel (e.g. 11 × 13 m) and disposal cells represent and consider some aspects taken into account in the designs of some European countries. In addition, tunnel walls reinforced with a shotcrete liner and the Excavation Damaged Zone is considered in the concept. The model is implemented in OpenGeoSys-6, an open-source version-controlled scientific software based on Finite Element Method which is capable of handling fully coupled hydro-chemical models by coupling OpenGeoSys to iPHREEQC. First calculation results, demonstrate that the most important processes affecting the near-field chemical evolution are i) the degradation of the concrete and cementitious grouts with porewater migrating inwards from the host rock and ii) the significant quantities of reactive and non-reactive gases (i.e. hydrogen, carbon dioxide and methane) that are generated as a result of: i) the anaerobic corrosion of metals present in the waste and containers and ii) the degradation of organic compounds by microbial and chemical processes. As a first approximation, some assumptions and simplifications have been considered, probably resulting in a wort case scenario.</p>

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