Clays in Geological Disposal Systems

Similar documents
The use of Underground Research Facilities in the development of deep geological disposal

Collaborating partners: NAGRA (CH), L3S (FR), G3S (FR), KUL (B), EPFL (CH), SOLEXPERTS (CH)

Experimental program in the URL

IAEA Network Courses

General strategy: integration and prospective

Hydro-Mechanical Modeling of a Shaft Seal in a Deep Geological Repository

Hydrogeology of Deep Borehole Disposal for High-Level Radioactive Waste

CNSC Review of the Long-Term Safety Case for a Deep Geologic Repository

WITPRESS WIT Press publishes leading books in Science and Technology. Visit our website for the current list of titles.

Collaborating partners Smet Tunnelling

1. Introduction. 2. Model Description and Assumptions

PROBABILISTIC TRANSPORT PATH ANALYSIS THROUGH THREE-DIMENSIONAL DISCRETE FRACTURE NETWORKS FOR UNDERGROUND RADIOACTIVE WASTE DISPOSAL FACILITIES

Implications of Host Rock Selection for a HLW Repository System in Germany - Consequences for Repository Design and Safety - Wilhelm Bollingerfehr

Impact of permafrost on repository safety

Deep Borehole Disposal Performance Assessment and Criteria for Site Selection

Safety assessment for disposal of hazardous waste in abandoned underground mines

SELF-HEALING OF FRACTURES WITHIN THE EDZ AT THE MT. TERRI ROCK LABORATORY : RESULTS AFTER ONE YEAR OF EXPERIMENTAL WORK

ENGINEERING GEOLOGY AND ROCK ENGINEERING ASPECTS OF OPERATION AND CLOSURE OF KBS-3

A TSO research programme on safety of geological disposal and its necessary evolution along the development of a national industrial project

Peter Elder, Vice-President and Chief Science Officer Technical Support Branch October 10, 2017 Kingston, ON. DECOVALEX-2019 Workshop.

THE SWISS CONCEPT FOR THE DISPOSAL OF SPENT FUEL AND VITRIFIED HLW

Treatment of Colloids in the Safety Case

Vanderbilt University. Image from: /wipppix.html

Summary of the BELBaR project

Thermo-Hydro-Mechanical-Chemical (THMC) Modelling of the Bentonite Barrier in Final Disposal of High Level Nuclear Waste

nuclear science and technology

Underground nuclear waste storage

Geoscientific Verification Plan

AN OVERVIEW OF RESPONSES TO THE AMIGO QUESTIONNAIRE ON THE USE OF GEOSCIENCE DATA IN SAFETY CASES. M. Jensen 1, B Goodwin 2

Underground Storage & Disposal - The Salt Concept. Thomas Brasser - GRS

Impact of bentonite colloids on radionuclide transport in fractured systems results from field experiments and modelling

MODELING OF GAS MIGRATION THROUGH LOW-PERMEABILITY CLAY USING INFORMATION ON PRESSURE AND DEFORMATION FROM FAST AIR INJECTION TESTS

Cementitious materials/components for HLW/ILW repository : priorities of the future R&D in the French context

Experimental study of the hydromechanical coupling in argillaceous rocks: the example of Boom clay

Groundwater dating applied for geological disposal of radioactive waste

For Official Use NEA/RWM/CLAYCLUB/A(2010)1. Integration Group for the Safety Case (IGSC) 13-Jul-2010

Belgian Nuclear Research Centre (SCK CEN), Institute for Environment, Health and Safety, Boeretang 200, B-2400 Mol, Belgium

MECHANICAL AND HYDROMECHANICAL BEHAVIOR OF HOST SEDIMENTARY ROCKS FOR DEEP GEOLOGICAL REPOSITORY FOR. Hadj Abdi. Thesis submitted to the

Tournemire Underground Laboratory: Geophysical Monitoring of Claystone Desaturation in a Ventilated Borehole.

Chemical erosion of bentonite: a challenge or a threat?

nuclear science and technology

Li Yu Eef Weetjens Xavier Sillen Tim Vietor Xiangling Li Pierre Delage Vincent Labiouse Robert Charlier

The volunteer process of site selection for radwaste disposal in Canada:

Abstract. Roland Pusch 1, Sven Knutsson 1, Laith Al-Taie 1

M. Cushing 1, A. Revil 2,3, C.. Gélis 1, D. Jougnot 3, F. Lemeille 1, J. Cabrera 1, A. De Hoyos 1, M. Rocher 1. Introduction

WM 00 Conference, February 27 March 2, 2000, Tucson, AZ DIFFUSION COEFFICIENTS OF CRITICAL RADIONUCLIDES FROM RADIOACTIVE WASTE IN GEOLOGICAL MEDIUM

Features, Events and Processes Evaluation Catalogue for Argillaceous Media

Assessment of releases from a nuclear waste repository in crystalline rock

Deep Borehole Disposal of Spent Fuel and Other Radioactive Wastes An International Overview

In-situ Experiments on Excavation Disturbance in JNC s Geoscientific Research Programme

Borehole radar measurements aid structure geological interpretations

Natural Tracer Profiles

Deep Borehole Field Test Overview. Presentation Overview

NUMERICAL STUDY OF NUCLIDE MIGRATION IN A NONUNIFORM HORIZONTAL FLOW FIELD OF A HIGH-LEVEL RADIOACTIVE WASTE REPOSITORY WITH MULTIPLE CANISTERS

A Feasibility Study On The Horizontal Emplacement Concept In Terms Of Operational Aspects

RADIONUCLIDE DIFFUSION IN GEOLOGICAL MEDIA

Geological Repositories. Michael Voegele

Feature. Clay as sealing material in nuclear waste repositories

Numerical Simulations of Radionuclide Transport through Clay and Confining Units in a Geological Repository using COMSOL

UDC contribution to Working Group 3: High temperature clay interactions

Initial Borehole Drilling and Testing in Central Huron,

Rock Suitability Classification for POPLU

Labor für Endlagersicherheit

NAWG-15 Workshop. UJV-Rez, Prague th May, 2017

IAEA-TECDOC-447 RADIOACTIVE WASTE MANAGEMENT GLOSSARY. Second Edition

More realistic treatment of long-term cement degradation: support from ancient natural cements

P11 A Methodology to Rescale the Vertical Coordinate into Geological Time Using a Geostatistical Analysis of Log Data

Initial Borehole Drilling in the Hornepayne and Manitouwadge Area

Initial Borehole Drilling and Testing in or Near Ignace

Evaluation of Colloid Transport Issues and Recommendations for SKI Performance Assessments

Opalinus Clay Project

Newsletter CROCK (Crystalline Rock Retention Processes) project

Answers to questions raised by Gerhard Schmidt concerning the planning process for a Danish nuclear waste repository

Development of the NUMO pre-selection, site-specific safety case

4-2 CHARACTERIZING THE GEOSPHERE IN HIGH-LEVEL RADIOACTIVE WASTE MANAGEMENT

Case study 2: Using seismic reflection to design a mine

International Journal of Rock Mechanics & Mining Sciences

Use of natural analogues to support radionuclide transport models for deep geological repositories for long lived radioactive wastes

WASTE MANAGEMENT GLOSSARY

Japanese Regulations for Waste Management

NUCLEAR WASTE DISPOSAL (44)

A25 Very High Resolution Hard Rock Seismic Imaging for Excavation Damage Zone Characterisation

Evaluation of the Thermal Effect in a KBS-3 Type Repository

Underground waste disposal Authors: Kemal Yildizdag & Prof. Dr. habil. Heinz Konietzky (TU Bergakademie Freiberg, Geotechnical Institute)

Sandia National Laboratories

Numerical modelling of hydromechanical coupling : permeability dependence on strain path

PROPOSED DEEP GEOLOGIC REPOSITORY FOR LOW AND INTERMEDIATE-LEVEL RADIOACTIVE WASTE AT THE BRUCE SITE, TIVERTON, ONTARIO

Thermal and Mechanical Influence of a Deep Geological Repository in Crystalline Rock on the Ground Surface

M035 High Resolution 3D Tunnel Seismic Reflection at Olkiluoto, Finland

the Quarrying Industry Dewatering and the Quarrying Industry the Quarrying Industry

THE ROLE OF STRUCTURAL RELIABILITY OF GEOTECHNICAL BARRIERS OF AN HLW/SF REPOSITORY IN SALT ROCK WITHIN THE SAFETY CASE

Convective drying : experimental campaign and numerical modelling

Using Thermodynamic Sorption Models

A. Millard, A. Rejeb, M. Chijimatsu, L. Jing, J. De Jonge, M. Kohlmeier, T.S. Nguyen, J. Rutqvist, M. Souley, Y. Sugita

Evaluation of Radiation Characteristics of Spent RBMK-1500 Nuclear Fuel Storage Casks during Very Long Term Storage

Qualitative Performance Assessment of a Borehole Disposal System

Modelling the excavation damaged zone in Callovo-Oxfordian claystone with strain localisation

Postclosure Safety Assessment: Groundwater Modelling

Radioactive Wastes and Disposal Options

Safety of the Geological Disposal Project 2010

Transcription:

Clays in Natural and Engineered Barriers for Radioactive Waste Confinement Clays in Geological Disposal Systems A brochure edited by ONDRAF/NIRAS (Belgium) and Andra (France), in collaboration with COVRA (The Netherlands), Nagra (Switzerland), NWMO (Canada), POSIVA (Finland) and SKB (Sweden), and published on the occasion of the 6th International conference Clays in Natural and Engineered Barriers for Radioactive Waste Confinement, Brussels, Belgium, March 23-26, 2015.

Many countries have chosen to dispose of all or part of their radioactive waste in facilities constructed in stable geological formations. Geological disposal as a safe solution for the long-term management of radioactive waste is in line with international recommendations and practices. The development of a geological disposal facility on a specific site requires a systematic and integrated approach taking into account the characteristics of the waste to be emplaced, of the enclosing engineered barriers and host rock (the three together being called the geological disposal system ) and of the geological setting of the host rock. Three main rock types are usually considered for geological disposal: crystalline rocks, salt and clays. Each type includes bedrock formations with a relatively broad spectrum of geological properties. The engineered barriers contain different types of materials, such as metals, concrete and natural materials like clay. This brochure highlights the importance of clays and clayey material in the development of almost all geological disposal systems. Figure 1 Different types of clay. Top: Boom Clay (Belgium) (source: EURIDICE). Bottom: Opalinus Clay, survey during excavation of a drift for the Full Scale Emplacement Experiment (Mont Terri Underground Rock Laboratory, Switzerland) ( Comet Photoshopping). Figure 2 Opalinus Clay of the Benken borehole in Northern Switzerland (core diameter: 10 cm; depth: from 591.6 to 592.0 meters) (source: Nagra). 2

Introduction Clays exhibit many interesting properties, which are exploited in the development of most geological disposal systems. Clays are used both as host rock and as material for engineered barriers. Whatever their use, clays present various characteristics that make them high-quality barriers to the migration of radionuclides and chemical contaminants towards the surface environment. As host rocks, clays are in addition hydrogeologically, geochemically and mechanically stable over geological timescales, i.e., millions of years (Figures 1 and 2). The disposal system as a whole The disposal system consists of the waste, the engineered barriers and the host rock (Figures 3 and 4). Each of these elements fulfils, separately or in complementary fashion, multiple safety functions. The defence-in-depth principle requires multiple levels of protection, which are designed to enhance safety through their diversity and redundancy. It is the whole system that must be taken into account in safety assessments and not each system component separately. Figure 3 Illustrative diagram of geological disposal. Geological disposal provides protection of people and the environment without human intervention being necessary once the facility is closed (source: ONDRAF/NIRAS). Figure 4 Schematic overview of an operational geological disposal facility (contains Environment Agency information Environment Agency and database right). 3

Clays as host rocks France and Switzerland have chosen to dispose of their high-level and long-lived intermediate-level radioactive waste in indurated clays, respectively in the Callovo-Oxfordian and Opalinus Clay formations; in Switzerland, Opalinus Clay is also the proposed host rock for low- and intermediate-level waste. In Belgium, the technical solution recommended for the long-term management of high-level and long-lived low- and intermediate-level waste is geological disposal in poorly indurated clay (Boom Clay or Ypresian clays). In the Netherlands, clays are considered as a potential host rock for the disposal of all types of radioactive waste. Other countries also plan to use clays as host rock. The research and development studies performed in France, Switzerland and Belgium over several decades have highlighted the clays favourable properties: Very little water movement: thanks to their low permeability, there is practically no water movement in clays. Radionuclide and chemical contaminant transport via this medium is thus strongly delayed. Diffusive transport: given the limited water movement, transport in clays is essentially diffusive, which means species migrate primarily under the influence of their concentration gradient, and very little under the influence of the pore-water movement. Retention capacity: clays have a strong retention capacity for many radionuclides and chemical contaminants. Their migration through clays is thus considerably delayed. Buffer effect: clays display a significant buffer effect with regard to chemical perturbations. The thickness of the clay that is chemically perturbed by the disposal facility is therefore very limited. Self-sealing capacity: clays show a high capacity for self-sealing. Any fractures and fissures that occur, in particular those created by excavation activities, close quite rapidly (Figure 5). Stability: the selected clay host rocks and therefore their favourable properties have remained unchanged over millions of years. The migration of natural chemical species through these clay host rocks has remained diffusive during at least the last million years. Vertical homogeneity: radionuclide and chemical contaminant transport properties are very homogeneous almost throughout the entire thickness of the selected clay host rocks. Lateral continuity: clays are present within simple geological structures, with a significant lateral continuity, which facilitates their large-scale characterisation. Figure 5 Illustration of the self-sealing capacity of Boom Clay. Left: clay sample in which a fracture has been induced; right: the same sample four hours after hydraulic saturation: the fracture has been sealed (source: ONDRAF/NIRAS). 4

Clays may also contribute to the safety of disposal systems whose host rock is not clay, by being present in their geological environment: In Germany, the disposal facility for low- and intermediate-level waste is under construction in an old iron mine (limestone) located under a clay formation. In Canada, the host rock proposed for the disposal of low- and intermediate-level waste is limestone situated beneath a sequence of clay formations. Underground research laboratories help to build knowledge and to carry out demonstration experiments. Excavation of a drift in Opalinus Clay for the Full Scale Emplacement Experiment (Mont Terri Underground Rock Laboratory, Switzerland) ( Comet Photoshopping). Excavation of a drift in Callovo-Oxfordian clay (Bure, France) (source: Andra). Construction of a shaft (left) and excavation of a drift (right) in Boom Clay (Belgium) (source: EURIDICE). 5

Clay as material for engineered barriers The favourable properties of clay (low permeability, self-sealing, stability) make it a material of choice for engineered barriers. Clay is mainly used as: Buffer material: the empty space between the disposal package and the host rock is filled with clay. For instance, bentonite, a swelling clay, is used as buffer material filling the voidage between the disposal packages and the host rock in the disposal facility designs selected in Canada, Finland, Sweden and Switzerland (Figures 6 and 7). Bentonite Clay Rock Figure 6 Examples of placement of disposal packages in a geological disposal facility. Voidage is filled with bentonite (source: NWMO). Figure 7 Sampling of bentonite in the Swedish Prototype Repository project (source: SKB). Backfill material: clay (for instance in the form of blocks or pellets) is used to fill excavated spaces (placement rooms, access ways) (Figure 8), sometimes in combination with other materials. Nominal tunnel cross section Rock surface Block filled volume Pellet filled volume Bottom bed Figure 8 Cross section of a drift backfilled with clay blocks and pellets (Sweden) (source: SKB). 6

Sealing material: clay, sometimes in combination with other materials, is used to isolate parts of the disposal facility. Seals are works of limited dimensions with specific purpose placed at key locations of the disposal facility. For instance, in France, the seals aim to limit water flow within the underground facilities (Figures 9 and 10). Containment plugs (low ph concrete) Backfill Swelling clay core Liner (low ph concrete) Backfill Figure 9 Reference drift sealing and backfilling concept (France). The seal is composed of a swelling clay core (bentonite) with two low ph concrete containment plugs, one at each end. The remaining part of the drift is backfilled with the original excavated material (argillites) (source: Andra, C.IM.AETI.11.0152.B-Ref). Figure 10 Full-scale seal experiment (France). This experiment is a technological demonstration performed above surface by Andra with the scientific support of Nagra, within the DOPAS European project. The test box is 36.1 meters long, with an inside diameter of 7.6 meters. A seal has been installed inside the test box (after the picture was taken), according to the sealing concept presented in Figure 9. The containment plugs are 5 meters long and the swelling clay core is 13.5 meters long (B.TINOCO Andra). 7

The geological disposal facilities in operation or under development in many countries thus contain clay, whatever the selected host rock. The table hereafter lists some of these facilities, sorted according to the progress of the geological disposal programmes. Uses of clay as material for engineered barriers Buffer Backfill Sealing Operational disposal facilities United States of America Waste types: long-lived low- and intermediate-level military waste Host rock: salt Hungary Waste types: short-lived low- and intermediate-level waste Host rock: crystalline rock (granite) Applications submitted for disposal facility construction licence Canada Waste types: low- and intermediate-level waste Host rock: limestone overlain by clay Sweden Waste type: irradiated fuel Host rock: crystalline rock (granite) Finland Waste type: irradiated fuel Host rock: crystalline rock (granite) Host rock selected France Waste types: long-lived intermediate-level and high-level waste Host rock: clay Switzerland Waste types: irradiated fuel and long-lived low- and intermediate-level waste Host rock: clay Host rock not selected yet Canada Waste type: irradiated fuel Publisher: Jean-Paul Minon, Avenue des Combattants 107A, 1470 Genappe, Belgium NIROND-TR 2015-01 E, March 2015 Cover: Boom Clay from the HADES underground research laboratory, Belgium BIB SEM (source: Desbois et al., 2009) Cette brochure est également disponible en français. Deze brochure is eveneens beschikbaar in het Nederlands.