radioactive waste and spent fuel management activities in...
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IAEA International Atomic Energy Agency
Radioactive Waste and Spent Fuel
Management activities in the IAEA
Gérard Bruno
Radioactive Waste and Spent Fuel Management Unit
Department of Nuclear Safety and Security
IAEA
Global need for RWM: Sources of waste
• Waste and spent fuel generation from NPPs
• Operation will continue in next decades (about 30 countries)
• 7-15 new countries will start to generate waste by 2030
• Decommissioning of nuclear facilities
• Medical applications and research
• Remediation activities on-going in several countries,
• Activities after Fukushima accident will result in large volumes of
waste from on-site and off-site decommissioning and remediation
• Numerous sites with a large amount of legacy waste
• Radium industry
• Uranium mining
• Military programs
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IAEA
Waste Management at the IAEA
• Department of Nuclear Safety and Security
• Nuclear Installation Safety
• Radiation, Transport and Waste Safety
• Waste and Environmental Safety Section
• Department of Nuclear Energy
• Nuclear Power
• Nuclear Fuel Cycle and
Waste Technology
• Waste Technology Section
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IAEA
Article III, Functions Paragraph A.6.
“ To establish or adopt, in consultation and, where
appropriate, in collaboration with the competent
organs of the United Nations and with the specialized
agencies concerned,
standards of safety for protection of health and
minimization of danger to life and property (including
such standards for labour conditions), and
to provide for the application of these standards to
its own operation as well as to the operations making
use of materials, services, equipment, facilities, and
information made available by the Agency …; “
IAEA Statutory Obligations (1957)
Statute 1957
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Global Safety Regime
• Legal Instruments
• Safety Standards
• International Peer Review Services
• Knowledge Networks
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IAEA and Radioactive Waste Management
• The IAEA programme on Radioactive Waste and Spent Fuel
Management
• Support to the IAEA Member States in establishing a proper safety
framework for the management of radioactive waste and spent fuel.
• Activities
• Development of IAEA safety standards for predisposal management and
disposal of radioactive waste and spent fuel,
• Assistance to the Member States on the implementation and application of
the Safety Standards,
• Coordination of the Waste Safety Standards Committee.
• Joints convention
• Meetings of Contracting Parties of the Joint Convention on the Safety of
Spent Fuel Management and on the Safety of Radioactive Waste
Management.
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• Program initiated 31 March 1960 (INFCIRC/18).
• IAEA maintains about 120 safety standards.
• Nuclear, radiation, transport and waste safety.
• Not legally binding on the Member States, but they can
adopt them at their own discretion.
• Legally binding on the activities of the IAEA Secretariat.
• Published in the “IAEA Safety Standards Series”,
• To be purchased as hardcopy
• Free-of-charge download
IAEA Safety Standards
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Under
development
Under
development
Under
development
Under
development
Recently
Published
Under
development
Structure of Safety Standards
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IAEA Safety Standards Categories
Fundamental Safety Principles
Requirements – Legal, Technical,
& Procedural Safety Imperatives
Guidance on Best Practice
to Meet Requirements
Safety Guides
Safety Requirements
Safety Fundamentals
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IAEA
• Policy document of the IAEA Safety Standards Series:
• States the basic objectives, concepts and
principles involved in ensuring protection
and safety
• Comprised of 10 safety principles
• Principle 7: Protection of present and future generations. People and the environment, present and future, must be protected against radiation risks
Safety Fundamentals
IAEA
Safety fundamentals
• Responsibility for safety
• Role of government
• Leadership and management for
safety
• Justification of facilities and activities
• Optimisation of protection
• Limitation of risks to individuals
• Protection of present and future
generations
• Prevention of accidents
• Emergency preparedness and
response
• Protective actions to reduce existing
or unregulated radiation risks
SF-1
IAEA
• Elaborate on the basic objectives and concepts of SF-1 as they apply to a specific activity or facility
• Should be concise and reflect the ‘What’ and ‘Who’ of safety management associated explanatory text should describe ‘Why’ the requirements exist
• Use “shall” statements
Safety Requirements
IAEA
Safety Guides
• Focus on ‘How’ safety
requirements can be met
• Guidance on best practices
to meet requirements
• Use “should” statements
IAEA
Status of Safety Standards
• IAEA Safety standards are
• Binding for IAEA’s own activities
• Not binding on the Member States (but may be
adopted by them) EXCEPT in relation to
operations assisted by the IAEA:
• Integrated Regulatory Review Service
• Technical Cooperation Fund work
• States wishing to enter into project
agreements with the IAEA
IAEA
CSS
COMMISSION ON SAFETY
STANDARDS
NUSSC RASSC WASSC TRANSSC
Safety Standards Committees
Commission and committees
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Development of Safety Standards
Outline and work plan Prepared by the Secretariat
Review by the Safety Standards Committees and the Commission on Safety Standards
Drafting or revising of safety standard
by the Secretariat and Consultants
Review by the Safety Standards
Committee(s)
Endorsement by Commission on Safety Standards
Member States
Approval by the IAEA’s Director General or BoG *
MS involved
* SF and SRs approved by BoG
* SGs approved by DG
Review period:
about every 5 years
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IAEA
Safety Standards: Predisposal of RW
DS 448
Predisposal
Management of
RW from
Reactors
Radiation Protection
Storage DS 447
Predisposal
Management of
RW from FCFs
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Under revision
to include
lessons leant
from
Fukushima
accident
DS 477
Revision
DS 489
IAEA
Safety Standards for Disposal
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Revision
DS 477
IAEA
Safety Standards - Decommissioning
Under revision
1999 1999
2001
DS402 DS403
DS404
2006 2008 2004
To be combined (DS452)
IAEA
Feedback and Review
• Feedback • Review
• About every 5 years
• Revision of DPPs
• Following the process of
standards' development
(Committees, CSS, BOG,
etc)
Safety standards survey:
-Questionnaire (form)
- Email:
http://www-
ns.iaea.org/standards/feedback.htm
IAEA
…. where you can find the status of
SS…
Important
to note
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JOINT CONVENTION ON THE SAFETY OF SPENT FUEL
MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE
MANAGEMENT
• A legally binding agreement between CPs
• The first international binding legislation in the area of safety of spent fuel and radioactive waste management
• Based on the IAEA Safety Fundamentals for RWM (1995)
• An “Incentive” convention
• A “sister” convention of the Nuclear Safety Convention
IAEA
Joint Convention on the Safety of Spent Fuel
Management and on the Safety of Radioactive Waste
Management
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Objectives
• To achieve and maintain a high level of safety
worldwide in spent fuel and radioactive waste
management
• To ensure that there are effective defences against
potential hazards so that individuals, society and the
environment are protected, now and in the future
• To prevent accidents and mitigate their consequences
should they occur
IAEA
• Applications
• Applies to facilities and activities of civil programmes
• Defence programmes when transferred permanently to civil control
• Reporting and Meetings
• National report prepared every three years
• Review meetings are organized every 3 years
• Cooperation with the EU
• “Waste Directive” (Council Directive 2011/70/EURATOM) is aligned
with JC.
• Almost all EU countries are contracting parties to the JC.
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Joint Convention
IAEA
Joint Convention on the Safety of Spent Fuel Management
and on the Safety of Radioactive Waste Management
• Secretariat of the Joint Convention
• Organization of the JC meetings: Organizational, Review
Meetings, Officers meetings, General Committee
meetings, regional promotional meetings and related
activities
• 69 Contracting Parties as of October 2013
• Review meetings: 1st review meeting: November 2003 2nd review meeting: May 2006 3rd review meeting: May 2009 4th review meeting: May 2012 5th Review Meeting: 11-22 MAY 2015
http://www-ns.iaea.org/conventions/waste-jointconvention.htm
IAEA International Atomic Energy Agency
International Harmonization Projects
& Working Groups related to
Demonstration of Safety
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Standards Application
Progress on the DeSa Project
B. Batandjieva, WSS, NSRW
3rd EMRAS Project Meeting
21-25 November 2005, IAEA, Vienna
Generation
Disposal
SADRWMS
CRAFT
DeSa/
FaSa
ISAM/
ASAM/
PRISM
EMRAS
I and II
MODARIA
Assessment
performance
Models inter-
comparison Impacts
evaluation
Safety Demonstration Framework for Management of
Radioactive Waste and Decommissioning
GEOSAF
IAEA International Atomic Energy Agency
International and Harmonization Projects organized by
WES
• CRAFT (successor to SADRWMS) • Application of GSG-3, SADRWMS methodology & SAFRAN Tool
• Illustrative examples to complement SG (DS284)
• PRISMA • Develop Model Safety case development / implementation for near-surface
disposal
• GEOSAF I / II • Safety on geological disposal
• Regulatory expectations throughout development and operation
• Assessment – engineering, site, radiological impact, integration
• Working Group for the Dual Use Cask for Spent Nuclear Fuel • Safety case covering both transportation / storage
• Extended periods of storage and meeting transport requirements
• HIDRA • Human intrusion for both geological / near-surface disposal facilities
• Relationship with siting/ designing/ waste acceptance criteria
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Long-term Project • 1st Plenary Meeting in 2003
• Final Plenary in 2010
Objectives: 1. EXAMINE the application of safety
assessment methodology (ISAM,
ASAM)
2. DEVELOP, document
• Safety Assessment
Methodology
• Regulatory Review
• ---> GSG-3
3. INTEGRATE methodology into
software tool (SAFRAN)
SADRWMS Project Safety Assessment Driving Radioactive Waste Management Solutions
IAEA
Project for development of complementary guidance
• GSG-3: The Safety Case and Safety Assessment for the Predisposal
Management of Radioactive Waste
• Required by WASSC, to cover the range of applications in GSG-3
Applications
• Long Term Storage Facilities
• Existing Storage Facilities
• Waste Processing Facilities
• Provide support on the different application of SAFRAN tool, and review the
SAFRAN forum for any developments or necessary changes.
4 Year Project
• 1st Plenary May 2011
• 2nd, 3rd Plenaries 2012, 2013
• Final Plenary October 2014
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CRAFT – Project Complementary Safety Reports, Development and application to Waste Management Facilities
IAEA
PRISMA - Practical Illustration and Use of the Safety Case Concept in the Management of Near-Surface Disposal Application
Focus of PRISM:
• Components and expectations of the safety case
• Evolution over the lifecycle of a near-surface radioactive waste disposal facility
• Decision making at different stages in the facility lifecycle, using the safety case
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Objective of PRISMA: • Development of a generic safety case following the PRISM approach
Meeting
• 1st plenary October 2013
• 2nd plenary October 2014
IAEA
GEOSAF project (2008-2011) Demonstration of SAFety of GEOlogical disposal
GEOSAF
European Pilot Study review
The Questionnaire
‘Long Term Safety’
The operational
safety companion
report
Review of the Draft Safety Guide on The Safety Case
and Safety Assessment for
Radioactive Waste Disposal
A forum to exchange ideas and
experience in developing / reviewing SC
a platform for knowledge transfer
Harmonization in approaches to
demonstrating the safety of geological
disposal
To identify issues related to the
development of the SC that need
clarification or further development
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GEOSAF II (2012-2014/2015):
Objective
Integration of post-closure safety and
operational safety into the Safety Case
Post Closure Safety
Operational Safety
Integrated Safety Case
‘Initial state’ of the Geological Disposal
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GEOSAF II : main topics
Integrated Safety Case
Definition of the
‘Initial State’ of the
facility, where
Operational phase
ends and Post-
closure phase
starts.
Contradicting
operational safety
and post-closure
safety requirements
Operational Safety:
Information
gathering and key
findings on national
GD programmes
Classification of
SSCs and its
implication on
operational safety
and post-closure
safety
+ Integration
Operational safety
• Safety in operation
– protection of workers
• Impact of operations on long
term safety
Long term safety
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Objectives: to address the safety demonstration for dual purpose casks in
terms of extended periods of storage and to meet transport requirements at
end of storage period
Scope of the document:
Storage period – 50 years (short term) / 100 years (long term)
Metallic casks (consideration for canisters being added later)
Expected outcomes:
• IAEA Safety Report containing recommendations and guidance for the
structure and contents of an Integrated Safety Case w consideration of
the interface issues between storage and transport casks.
• Recommendations for changes to be made to existing IAEA
requirements and guidance relevant to the licensing and use of Storage
and Transport Casks for SNF
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Joint Working Group on Guidance for an Integrated
Safety Case for Dual Purpose Casks for SNF
IAEA
HIDRA - Human Intrusion in the context of Disposal of
Radioactive Waste
• Addressing human intrusion in context of the safety case
• Near surface and geologic radioactive waste disposal facilities,
• VLLW facilities,
• Facilities for short- and/or long-lived L/IL,
• Facilities for HLW, Spent Fuel and boreholes.
• Results
• Guidance on optimization of siting, design and waste acceptance
criteria within the context of a safety case.
• Catalogue of “measures” that can be used to reduce the likelihood and/or
consequences associated with human intrusion
• Input for the further development of IAEA Safety Standards
1st plenary meeting November 2013
Annual plenary meeting & Task group activities
3 task groups: Technical / Societal / Design aspects
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International Networks
• URF: Underground Research Facilities
• IAEA Network of Centres of Excellence
• To establish the network of international expertise for the efficient
development of safe nuclear waste isolation systems
• DISPONET: International Low Level Waste Disposal Network
• To coordinate support Member States with less advanced programmes for
disposal of low level waste
• Forum for exchange of information and experience
• LABONET: Intern. Network of Laboratories for Nuclear Waste
Characterization
• To support Member States with less advanced nuclear programmes for
characterization of radioactive waste,
• To develop a training and demonstration activities
• Forum to share experience and information on good practice
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• Yucca Mountain Site
Characterisation Project (USA)
• Near Surface Disposal
(Australia)
• IAEA-EC-Ukraine (WWER review,
Ukraine)
• Site Characterisation (South
Korea) and selection (Lithuania)
• COVRA activities (Netherlands)
• Disposal (Russia, planned), etc.
Peer Reviews
IAEA
IAEA Technical Co-operation Programme
• TC-cycle 2014-2015
• More than 80 TC projects related to RWM in 37
countries in all regions
• Related to waste processing, storage and disposal of
LLW
• Assistance for geological disposal of SF and
HLW
• Mostly focused on development of adequate policy and
long-term strategy/programme for SF/HLW
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IAEA Lecture 1 - International Safety Standards, IAEA Course, Clausthal 2010 (B Batandjieva) 40
• Safety of Radioactive
Waste Management
• Safety Assessment for
Near Surface Disposal
• Waste Acceptance
Criteria
• Legal and Regulatory
framework
• Decommissioning
• Discharge Control
• Remediation
Training Courses and Workshops
Training Material (30 Modules) and
Reference Syllabus
IAEA Lectu
re 1-
1 -
Intern
ation
al
Safet
y
Fund
amen
tals,
Stan
dards
, and
Guid
ance
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Information Exchange
http://www-
pub.iaea.org/MTCD/meetings/meetings.
asp
IAEA
Other current and future activities
• ARTEMIS - IAEA Radioactive Waste Management
Integrated Review Service
• Performed on request of Member States
• Independent expert opinion and advice on RW and SNF management
• Covers both safety and technical considerations
• ILW disposal
• Cooperation with Fukushima prefecture
• Radiation protection, Remediation, Waste management (off-site)
• Revision of waste management related safety standards
• SSG-15 on storage of SNF in the light of Fukushima
• Predisposal RWM in the Aftermath of Severe Nuclear
Accident
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Future Activities
• Contribution to the IAEA Spent Nuclear Fuel
Management Conference (2015)
• Proposal for an International Conference on
the Safety of Radioactive Waste
Management (2016)
• International Conference on
Decommissioning of Nuclear Facilities and
Environmental Remediation of Nuclear Sites
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2014 Scientific Forum
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Waste Classification
Purpose - for safety, engineering and regulatory aspects:
• Radioactive waste management strategies, planning and
designing waste management facilities
• Facilitating record keeping and giving a broad indication of
the potential hazards involved in the various types of
waste at the operational level
• Communication between interested parties by providing
well understood terminology (e.g., Joint Convention)
IAEA 46
Classification Systems Vs WACriteria
Waste classification system ≠ WAC
• Waste classification systems:
national system of classification for managing all
types of radioactive waste.
Do not specify criteria for individual facilities
• WAC –
Specifications for waste to meet to be accepted in a
particular facility.
IAEA 47
Different ways to classify waste
• By origin: Nuclear fuel cycle, isotope production,..
• By physical state: Solid, liquid, gaseous
• By activity concentration: LLW, ILW, HLW
• By half-life: Short-lived waste, long-lived waste
• By Operational or disposal purposes, heat emitting or
not…
IAEA
The IAEA Waste Classification - GSG
Link between types of waste and management options
• Exempt waste (EW)
• Very low level waste (VLLW)
• Very short lived waste (VSLW)
• Low level waste (LLW)
• Intermediate level waste (ILW)
• High level waste (HLW)
IAEA
Waste that meets the criteria for
clearance, exemption or exclusion
from regulation control for radiation
purposes as described in Safety
Guide RS-G-1.7 “Application of the
Concepts of Exclusion, Exemption
and Clearance” (2004)
Exempt Waste (EW)
IAEA
• Does not necessarily meet the criteria of exempt waste
• Does not need a high level of containment and isolation
• Suitable for disposal in near surface landfill type facilities
with limited regulatory control
• Typical waste includes soil and rubble with low levels of
activity concentration
• Concentrations of longer lived radionuclides are generally
very limited
Very Low Level Waste (VLLW)
IAEA
• Waste that can be stored for decay over a limited period of
up to a few years and subsequently cleared from
regulatory control for uncontrolled disposal, use or
discharge.
• This class includes waste containing primarily
radionuclides with very short half-lives often used for
research and medical purposes.
Very Short Lived Waste (VSLW)
IAEA
• Above clearance levels, but with limited amounts of long
lived activity
• Requires robust isolation and containment for periods of up
to a few hundred years
• Suitable for disposal in engineered near surface facilities
• LLW cover a broad range of materials and may include:
• SL radionuclides at higher levels of activity concentration and
• LL radionuclides but at relatively low levels of activity concentration
Low Level Waste (LLW)
IAEA
• Greater degree of containment and isolation than that
provided by near surface disposal
• But no provision for heat dissipation during storage and
disposal
• May contain LL radionuclides, in particular alpha
emitting radionuclides
• Will not decay, during the IC period, to level of activity conc.
acceptable for NS disposal
• Disposal at greater depths than near surface disposal
Intermediate level waste (ILW)
IAEA
• Levels of activity concentrations high enough to generate significant quantities of heat by the radioactive decay process
or
• Large amounts of long lived radionuclides that need to be considered in the design of a disposal facility for such waste
• Disposal in deep, stable geological formations, usually several hundreds m or more is the generally recognized
option for disposal
High Level Waste (HLW)
IAEA
Half-life
Activity
content
VSLW
very short lived
waste
(decay storage)
HLW
high level waste
(deep geologic disposal)
ILW
intermediate level waste
(intermediate depth disposal)
LLW
low level waste
(near surface disposal)
VLLW
very low level waste
(landfill disposal)
EW
exempt waste
(exemption / clearance)
IAEA
WASTE TYPES & RELEVANT DISPOSAL
OPTIONS
Activity, half-life
VSLW VLLW LLW ILW HLW