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    Design Principles and Approaches for Radioactive Waste Repositories
    Design Principles and Approaches for Radioactive Waste Repositories
    Design Principles and Approaches for Radioactive Waste Repositories
    Ebook206 pages1 hour

    Design Principles and Approaches for Radioactive Waste Repositories

    By IAEA

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    About this ebook

    A considerable level of international experience has been gained over the last decades in designing radioactive waste disposal facilities. This publication is intended to assist Member States in planning for the disposal of radioactive waste. Specifically, this publication describes the approaches and principles to be considered by the responsible organizations within a Member State involved in the planning and design of radioactive waste disposal facilities. Examples are provided for all waste classes requiring disposal. The examples are based on successfully implemented designs or on design concepts that are sufficiently advanced to demonstrate their overall feasibility for the safe disposal of radioactive waste. Alternate disposal options are also discussed, describing solutions that rely on the conversion of existing facilities, such as mines or other underground openings as well as the potential for disposal in boreholes.
    LanguageEnglish
    PublisherInternational Atomic Energy Agency
    Release dateDec 10, 2020
    ISBN9789201131201
    Design Principles and Approaches for Radioactive Waste Repositories

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      Book preview

      Design Principles and Approaches for Radioactive Waste Repositories - IAEA

      1.png

      Design Principles

      and Approaches

      for Radioactive Waste

      Repositories

      IAEA NUCLEAR ENERGY SERIES No. NW-T-1.27

      Design Principles

      and Approaches

      for Radioactive Waste

      Repositories

      INTERNATIONAL ATOMIC ENERGY AGENCY

      VIENNA, 2020

      COPYRIGHT NOTICE

      All IAEA scientific and technical publications are protected by the terms of the Universal Copyright Convention as adopted in 1952 (Berne) and as revised in 1972 (Paris). The copyright has since been extended by the World Intellectual Property Organization (Geneva) to include electronic and virtual intellectual property. Permission to use whole or parts of texts contained in IAEA publications in printed or electronic form must be obtained and is usually subject to royalty agreements. Proposals for non-commercial reproductions and translations are welcomed and considered on a case-by-case basis. Enquiries should be addressed to the IAEA Publishing Section at:

      Marketing and Sales Unit, Publishing Section

      International Atomic Energy Agency

      Vienna International Centre

      PO Box 100

      1400 Vienna, Austria

      fax: +43 1 26007 22529

      tel.: +43 1 2600 22417

      email: [email protected]

      www.iaea.org/publications

      © IAEA, 2020

      Printed by the IAEA in Austria

      December 2020

      STI/PUB/1908

      IAEA Library Cataloguing in Publication Data

      Names: International Atomic Energy Agency.

      Title: Design principles and approaches for radioactive waste repositories / International Atomic Energy Agency.

      Description: Vienna : International Atomic Energy Agency, 2020. | Series: IAEA nuclear energy series, ISSN 1995-7807 ; no. NW-T-1.27 | Includes bibliographical references.

      Identifiers: IAEAL 20-01361 | ISBN 978–92–0–112920–8 (paperback : alk. paper) | ISBN 978–92–0–113020–4 (pdf) | ISBN 978–92–0–113120–1 (epub) | ISBN 978–92–0–113220–8 (mobipocket)

      Subjects: LCSH: Radioactive waste repositories. | Radioactive waste management. | Radioactive wastes — Storage.

      Classification: UDC 621.039.7 | STI/PUB/1908

      FOREWORD

      The IAEA’s statutory role is to seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world. Among other functions, the Agency is authorized to foster the exchange of scientific and technical information on peaceful uses of atomic energy. One way this is achieved is through a range of technical publications including the IAEA Nuclear Energy Series.

      The IAEA Nuclear Energy Series comprises publications designed to further the use of nuclear technologies in support of sustainable development, to advance nuclear science and technology, catalyse innovation and build capacity to support the existing and expanded use of nuclear power and nuclear science applications. The publications include information covering all policy, technological and management aspects of the definition and implementation of activities involving the peaceful use of nuclear technology.

      The IAEA safety standards establish fundamental principles, requirements and recommendations to ensure nuclear safety and serve as a global reference for protecting people and the environment from harmful effects of ionizing radiation.

      When IAEA Nuclear Energy Series publications address safety, it is ensured that the IAEA safety standards are referred to as the current boundary conditions for the application of nuclear technology.

      This publication provides Member States with an overview of repository design principles and approaches that may be used to address their radioactive waste disposal needs. Furthermore, it describes a range of well studied disposal concepts that have either been successfully implemented or developed to an advanced stage of design. Examples of potential design solutions are provided for both near surface disposal facilities and geological repositories situated at various depths. Near surface facilities, suitable for the disposal of very low and low level waste, include trenches, vaults, shafts and direct access silos, as well as natural and engineered subsurface structures such as caverns, drifts and tunnels. Geological repository concepts, suitable for the disposal of intermediate level and high level waste (including spent nuclear fuel when declared as waste), mainly comprise mined disposal facilities situated at various depths and in a range of rock formations. They typically comprise access tunnels, shafts or both, as well as waste deposition tunnels, chambers and vaults. They may also include shallow boreholes and silos constructed within such engineered features. Alternate disposal options are also discussed describing solutions that rely on the conversion of existing facilities such as mines or other underground openings. The potential for radioactive waste disposal in boreholes, including the use of a very deep borehole concept, is also considered.

      This IAEA publication was developed specifically to assist Member States in meeting their radioactive waste disposal obligations. Radioactive waste requiring disposal is generated from many different activities in Member States, including from the production of energy, research, health care and various industrial activities.

      The IAEA officers responsible for this publication were G.H. Nieder-Westermann and J. Faltejsek of the Division of Nuclear Fuel Cycle and Waste Technology.

      EDITORAL NOTE

      This publication has been edited by the editorial staff of the IAEA to the extent considered necessary for the reader’s assistance. It does not address questions of responsibility, legal or otherwise, for acts or omissions on the part of any person.

      Although great care has been taken to maintain the accuracy of information contained in this publication, neither the IAEA nor its Member States assume any responsibility for consequences which may arise from its use.

      Guidance provided here, describing good practices, represents expert opinion but does not constitute recommendations made on the basis of a consensus of Member States.

      The use of particular designations of countries or territories does not imply any judgement by the publisher, the IAEA, as to the legal status of such countries or territories, of their authorities and institutions or of the delimitation of their boundaries.

      The mention of names of specific companies or products (whether or not indicated as registered) does not imply any intention to infringe proprietary rights, nor should it be construed as an endorsement or recommendation on the part of the IAEA.

      The IAEA has no responsibility for the persistence or accuracy of URLs for external or third party Internet web sites referred to in this book and does not guarantee that any content on such web sites is, or will remain, accurate or appropriate.

      The authoritative version of this publication is the hard copy issued at the same time and available as pdf on www.iaea.org/publications. To create this version for e-readers, certain changes have been made, including a the movement of some figures and tables.

      CONTENTS

      1. Introduction

      1.1. Background

      1.2. Scope

      1.3. Objective

      1.4. Structure

      2. THE REPOSITORY Design process

      2.1. Basic considerations

      2.2. Repository design and evaluation cycle

      2.3. Waste inventory

      2.3.1. Waste classification

      2.3.2. Predisposal waste processing and packaging

      2.4. Repository design inputs and outputs

      2.5. Repository functional systems and layout

      3. Design principles and stages

      3.1. Design principles

      3.1.1. Requirements driven design basis

      3.1.2. Multiple barrier safety concept

      3.1.3. Safe, reliable, available and maintainable technology

      3.1.4. Iteratively developed and optimized designs

      3.1.5. Maintenance of design integrity

      3.1.6. Transparent and traceable design

      3.1.7. Nuclear safeguards and security integrated design

      3.2. Design stages

      3.2.1. Generic designs

      3.2.2. Conceptual designs for siting

      3.2.3. Technical design for construction licensing

      3.2.4. Detailed design for construction and operation

      3.2.5. Continued detailed design for repository operation and expansion

      3.2.6. Design for closure

      4. Examples of operational or advanced repository designs

      4.1. Earthen trenches

      4.1.1. General considerations

      4.1.2. Disposal concept

      4.1.3. Representative examples

      4.2. Near surface engineered structures

      4.2.1. General considerations

      4.2.2. Disposal concept

      4.2.3. Representative examples

      4.3. Subsurface disposal systems at intermediate depths

      4.3.1. General considerations

      4.3.2. Disposal concept

      4.3.3. Representative examples

      4.4. Disposal in deep stable geological formations

      4.4.1. General considerations

      4.4.2. Disposal concept

      4.4.3. Representative examples

      4.5. Other disposal solutions

      4.5.1. Adapting existing underground facilities

      4.5.2. Borehole disposal

      5. CONCLUSION

      REFERENCES

      ABREVIATIONS

      CONTRIBUTORS TO DRAFTING AND REVIEW

      STRUCTURE OF THE IAEA NUCLEAR ENERGY SERIES

      1. Introduction

      1.1. Background

      Radioactive waste in various forms is generated in industrial, research and medical facilities worldwide. For those countries with nuclear power programmes, these wastes are predominantly derived from energy production in nuclear power plants. Almost all countries produce smaller quantities of radioactive waste from research activities and medical and industrial applications. Each IAEA Member State thus possesses different types of radioactive waste in varying quantities that will eventually require disposal, in conditioned, solid form, in one or more purpose designed disposal facilities.

      The path to disposal for each type of waste will depend upon its inventory of radionuclides, its physical and chemical form, its quantity, and other waste specific characteristics. Depending on the category of waste, quantities within a national inventory can range from a few cubic metres to hundreds of thousands. The radiological hazard will also vary, depending on the nature and amounts of radionuclides associated with each type of waste. Radioactive waste can remain hazardous to human health and the environment for a period lasting from a few decades to many thousands of years, depending on the radionuclides of concern and their concentrations. Unless the quantity is considered below defined clearance levels or exempted by national law based on very low radiation levels, all radioactive waste is considered hazardous, no matter the actual quantity, and is therefore subject to controlled and regulated disposal. The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management [1] requires that each Contracting Party to the Convention provide assurance that society and the environment are protected from harmful effects of ionizing radiation, now and in the future… The recognized means by which assurance is provided is the safe management of radioactive waste through disposal in a purpose built repository. Member States are ultimately responsible for providing adequate resources and ensuring their efficient use to manage radioactive waste from initial generation to eventual disposal.

      Significant experience in the disposal of radioactive waste has been gained over the last several decades. Numerous facilities have been constructed and operated in many Member States and disposal solutions for many waste forms and classes are available. Based on this and other experience, a Member State beginning the development of a new disposal facility will need to

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