PAGIS Performance Assessment of Geological Isolation Systems. Summary Report of Phase 1 : A common methodological approach based on European data and models.
168 pages
English

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PAGIS Performance Assessment of Geological Isolation Systems. Summary Report of Phase 1 : A common methodological approach based on European data and models.

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168 pages
English
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Commission of the European Communities Nuclear Science and Technology PAGIS Performance Assessment of Geological Isolation Systems Summary Report of Phase 1 A Common Methodological Approach Based on European Data and Models Joint Research Centre, Ispra Establishment Directorate General for Science, Research and Development EUR 9220 EN 1984 Commission of the European Communities AH Nuclear Science and Technology PAGIS Performance Assessment of Geological Isolation Systems Summary Report of Phase 1 A Common Methodological Approach Based on European Data and Models Prepared by : N. Cadelli, CEC/DG XII - Fuel Cycle Division G. Cottone,G XII - Fuel Cyclen G. Bertozzi, CEC/DG XII - JRC-lspra F. Girardi, CEC/DG XII -a and based on contribution from experts of ANDRA (France) CEN/SCK (Belgium) HMI (F.R.G.) NRPB (U.K.) This work was performed as part of the European Atomic Energy Community's R&D Programme (1980-84) on "Management and Storage of Radioactive Waste" — Action No. 9 : Performance and safety evaluation of radioactive waste disposal in geological formations.

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Commission of the European Communities
Nuclear Science and Technology
PAGIS
Performance Assessment of Geological Isolation Systems
Summary Report of Phase 1
A Common Methodological Approach Based on
European Data and Models
Joint Research Centre,
Ispra Establishment
Directorate General for Science, Research and Development
EUR 9220 EN 1984 Commission of the European Communities
AH
Nuclear Science and Technology
PAGIS
Performance Assessment of Geological Isolation Systems
Summary Report of Phase 1
A Common Methodological Approach Based on
European Data and Models
Prepared by :
N. Cadelli, CEC/DG XII - Fuel Cycle Division
G. Cottone,G XII - Fuel Cyclen
G. Bertozzi, CEC/DG XII - JRC-lspra
F. Girardi, CEC/DG XII -a
and based on contribution from experts of
ANDRA (France)
CEN/SCK (Belgium)
HMI (F.R.G.)
NRPB (U.K.)
This work was performed as part of the European Atomic Energy Community's R&D
Programme (1980-84) on "Management and Storage of Radioactive Waste" — Action No. 9 :
Performance and safety evaluation of radioactive waste disposal in geological formations.
Joint Research Centre,
Ispra Establishment
Directorate General for Science, Research and Development
EUR 9220 EN 1984 Published by the
COMMISSION OF THE EUROPEAN COMMUNITIES
Directorate-General
Information Market and Innovation
Bâtiment Jean Monnet
LUXEMBOURG
Neither the Commission of the European Communities nor any person
acting on behalf of the Commission is responsible for the use which might
be made of the following information.
Cataloguing data can be found at the end of this publication.
Luxembourg: Office for Official Publications of the European Communities, 1984
ISBN 92-825-5064-8 Catalogue number I
© ECSC - EEC - EAEC, Brussels-Luxembourg 1984
Printed in Italy Abstract
Since 1982 a joint study has been launched by the CEC with the participation of
national institutions in the E.C., aiming at a Performance Assessment of Geoligical
Isolation Systems (PAGIS) for HLW disposal.
This document is a summary of the first phase of the study which was devoted to
the collection of data and models and to the choice of an appropriate methodology.
To this purpose, real or notional sites have been chosen, which are representative
of three types of continental geological formations in the E.C. : clay, granite and
salt (although the choices imply no committment of any kind about their final use).
Moreover, sub-seabed areas have also been identified.
The study covers the following items :
- Basic data on waste characteristics, site data and repository designs;
- Methodology, which allows sensitivity and uncertainty analyses to be performed,
as well as the assessment of radiation doses to individuals and populations;
- Preliminary modelling of radionuclide release and migration through the geosphere
(near- and far-field) and the biosphere following their various pathways to man;
- Selection of the most relevant radionuclide release scenarios and their probability
of occurrence.
Reference values have been selected for the basic data as well as variants covering
the various options which are under consideration in the different Countries of the E.C.
Ill Contents
Executive Summary
Section A : INTRODUCTION
1. Background of the Project 9
2. Objectives and Scope of the Study
3. Planning of the Work 10
4. Organization of Phase1
Section Β : BASIC DATA
1. Waste Arisings and Characteristics5
1.1 Introductory Explanation
1.2 Common Reference Waste Data 1
1.2.1 General data
1.2.2 Glass characteristics9
1.2.3 Characteristics of the canister
1.3 Assumptions for Waste in Clay 21
1.4s for Waste in Granite
1.5 Assumptions for Waste in Salt2
1.6 Waste from other Reactor Types
2. Choice of Sites and Related Data4
2.1 Introductory Explanation 2
2.2 Common Guidelines for the Choice of Sites 25
2.3 Basic Data for the Clay Option6
2.3.1 Choice of sites
2.3.2 Site and regional data9
2.4 Basic Data for the Granite Option 34
2.4.1 Choice of sites
2.4.2 Site and regional data5
2.5 Basic Data for the Salt Option 42
2.5.1 Choice of sites
2.5.2 Site and regional data
2.6 Basic Data for the Sub-seabed Option 50
2.6.1 Choice of sites 5
2.6.2 Specific site and regional data3
2.6.3 Common site andl data6
3. Repository Design Data
3.1 Introductory Explanation
3.2 Common Guidelines
3.2.1 Construction
3.2.2 Post-closure phase7
3.3 Repository in Clay 5
3.3.1 Basic data8
3.3.2 Guidelines for the design
3.3.3 Repository characteristics
3.3.4 Influence of the repository on the host rock 60
3.3.5 Variants 6
V 3.4 Repository in Granite 63
3.4.1 Basic data
3.4.2 Guidelines for the design
3.4.3 Repository characteristics4
3.5 Repository in Salt9
3.5.1 Basic data
3.5.2 Guidelines for the design
3.5.3 Repository characteristics 70
3.5.4 Influence of the repository on the host rock 72
3.5.5 Variants 7
3.6 Emplacement Concepts for Sub-seabed
3.6.1 Basic data2
3.6.2 Guidelines for the emplacement geometry 73
3.6.3 Characteristics of thet techniques4
3.6.4 Influence of thet geometry on
the host media5
3.6.5 Variant emplacement technique 77
Section C : METHODOLOGY
1. Introductory Explanation 81
2. Choice of Methods
2.1 Classification of Scenarios
2.2 General Framework2
2.3 Specific Features3
2.3.1 Clay option4
2.3.2 Granite option5
2.3.3 Salt option
2.3.4 Sub-seabed option 86
3. Description of Scenarios
3.1 Common Features
3.2 Scenarios for Clay Formations7
3.3 Scenarios for Granites 92
3.4s for Salt Formations4
3.5 Scenarios for Sub-seabed5
Section D : MODELLING
1. Introductory Explanation 101
2. Near-field Modelling
2.1 Modelling Approach for Clay, Granite and Sub-seabed 10
2.2 Models and Data for Clay3
2.2.1 Normal evolution
2.2.2 Alteredn4
2.3 Models and Data for Granite5
2.3.1 Normal evolution
2.3.2 Altered evolution 106
2.4 Models and Data for Salt
2.4.1 Normal evolution
2.4.2 Alteredn7
2.5 Models and Data for Sub-seabed9
2.5.1 Normal evolution
2.5.2 Alteredn 110
3. Far-field Modelling2
3.1 Common Modelling Approach
3.2 Models and Data for Clay
3.2.1 Normal evolution
3.2.2 Alteredn4
3.3 Models and Data for Granite
3.3.1 Normal evolution 11
3.3.2 Alteredn6
3.4 Models and Data for Salt7
3.4.1 Normal evolution
3.4.2 Alteredn
VI 3.5 Models and Data for Sub-seabed 118
3.5.1 Normal evolution
3.5.2 Alteredn
4. Biosphere Modelling 120
4.1 Introductory Explanation
4.2 Common Approach
4.3 Models and Data for Continental Sites2
4.3.1 Description of the biosphere model and
general data
4.3.2 Application of the model to the clay option 123
4.3.3 Application of the model to the granite option 125
4.3.4n of thel to the salt option
4.4 Model and Data for Sub-seabed Sites 126
Section E : GENERAL CONCLUSIONS 131
Bibliography 137
Annex : Glossary 14
VII

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