IAEA International Atomic Energy Agency
Small and Medium-sized Reactor Technology for Small Electricity Grids
Dr. M. Hadid Subki Technical Lead, SMR Technology Development
Nuclear Power Technology Development Section Nuclear Division of Nuclear Power
Department of Nuclear Energy
IAEA - INIG Workshop on Topical Issues of Infrastructure Development, 24 – 27 January 2012
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Outline • Newcomer Countries Considerations • Role of IAEA on SMR Technology Development • Global Status of SMR Development and Deployment • Perceived Advantages and Challenges • Innovative Concepts of SMR Application • Common User Considerations (CUC) • Lessons Learned on Safety • IAEA Response to the Global Trend • Conclusions
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Newcomer Countries Considerations
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Introduction of the first Nuclear Power Plant
Nuclear Energy Policy
Domestic Industry
Participation
Proliferation resistance &
physical protection
Public acceptance
Safety
Radwaste Management
Viable financing scheme
Economic Competitive
ness
Affordable (Capital cost,
electricity cost
Security of Supply
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Role of IAEA on SMR Development
• Coordinates efforts of Member States by taking a systematic approach to identify key enabling technologies, and by addressing common issues of deployment
• Establishes and maintains an international network with Member States, industries, utilities, stakeholders
• Ensures coordination of Member State experts by planning and implementing training and by transferring knowledge
• Develops international recommendations and guidance focusing on specific needs of developing countries
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Definition • IAEA:
• Small-sized reactors: < 300 MW(e) • Medium-sized reactors: 300 700 MW(e) • Regardless of being modular or non-modular • Covers all reactors in-operation and under-development
with power < 700 MWe • Covers 1970s technology 2000s innovative
technology • Several developed countries:
• Small-sized reactors: < 300 MW(e) • Emphasize the benefits of being small and modular • Focus on innovative reactor designs under-development
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Global Development and Deployment
• Dozens of concepts for innovative SMRs are under development in many IAEA Member States: • Argentina, Brazil, Canada, China, France, India, Japan, Republic of
Korea, Russia, South Africa, USA, and some emerging countries. • A number of companies are developing SMRs; each has
unique features and varying megawatt capacity. • Many SMRs (with 1970s, 1980s technologies) are
operating and many are under construction (as of Feb 2011):
• None of the innovative SMRs are commercially available
In Operation 125 Under construction 17 Number of countries with SMRs 28 Generating Capacity, GW(e) 57.1
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Light water-cooled SMRs
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CAREM-25 Argentina
IMR Japan
SMART Korea, Republic of
VBER-300 Russia
WWER-300 Russia
KLT-40s Russia
mPower USA
NuScale USA
Westinghouse SMR - USA
CNP-300 China, People Republic of
ABV-6 Russia
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Heavy-water cooled SMRs
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EC6 Canada
PHWR-220, 540, & 700 India
AHWR300-LEU India
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Liquid-Metal cooled Fast SMRs
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CCFR China
4S Japan
PFBR-500 India
SVBR-100 Russian Federation
PRISM USA
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Gas-cooled SMRs
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PBMR South Africa
HTR-PM China
GT-MHR USA
EM2 USA
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SMRs for Immediate Deployment
Name Design Organization Country of Origin Electrical
Capacity, MWe Design Status
1 PHWR-220 NPCIL India 220 16 units in operation
2 PHWR-540 NPCIL India 540 2 units in operation
3 PHWR-700 NPCIL India 700 4 units under construction
4 KLT-40S OKBM Afrikantov Russian Federation 70 2 units under construction
5 HTR-PM Tsinghua University China, Republic of 250 Detailed design,
2 modules under construction
6 CAREM-25 CNEA Argentina 27 Started site excavation in Sept 2011, construction in 2012
7 Prototype Fast Breed Reactor (PFBR-500) IGCAR India 500 Under construction –
Commissioning in mid 2012
9 CNP-300 CNNC China, Republic of 300 2 units in operation, 2 units under construction
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SMRs for Near-term Deployment
Name Design
Organization Country of
Origin Electrical Capacity,
MWe Design Status
1 System Integrated Modular Advanced Reactor (SMART)
Korea Atomic Energy Research Institute Republic of Korea 100 Standard Design Approval
2nd Quarter 2012
2 mPower Babcock & Wilcox United States of America 160/module Detailed design, to apply for
certification - end of 2012
3 NuScale NuScale Power Inc. United States of America 45/module Detailed design, to apply for
certification - end of 2012
4 VBER-300 OKBM Afrikantov Russian Federation 300 Detailed design
5 SVBR-100 JSC AKME Engineering Russian Federation 100 Detailed design for
prototype construction
6 Westinghouse SMR Westinghouse United States of
America 225 Detailed Design
7 Super-Safe, Small and Simple (4S) Toshiba Japan 10 Detailed design
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SMR for Immediate Deployment CAREM-25
• Full name: Central Argentina de Elementos Modulares
• Designer: National Atomic Energy Commission of Argentina (CNEA)
• Reactor type: Integral PWR • Coolant/Moderator : Light Water • Neutron Spectrum: Thermal Neutrons • Thermal/Electrical Capacity: 87.0 MW(t) /
27 MW(e) • Fuel Cycle: 14 months • Salient Features: primary coolant system
within the RPV, self-pressurized and relying entirely on natural convection.
• Design status: Site excavation started for construction in 2012
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SMR for Near-term Deployment 4S
• Full name: Super-Safe, Small and Simple
• Designer: Toshiba Corporation, Japan • Reactor type: Liquid Sodium cooled,
Fast Reactor – but not a breeder reactor
• Neutron Spectrum: Fast Neutrons • Thermal/Electrical Capacity:
30 MW(t)/10 MW(e) • Fuel Cycle: without on-site refueling
with core lifetime ~30 years. Movable reflector surrounding core gradually moves, compensating burn-up reactivity loss over 30 years.
• Salient Features: power can be controlled by the water/steam system without affecting the core operation
• Design status: Conceptual Design
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SMR for Near-term Deployment SMART
• Full name: System-Integrated Modular Advanced Reactor
• Designer: Korea Atomic Energy Research Institute (KAERI), Republic of Korea
• Reactor type: Integral PWR • Coolant/Moderator: Light Water • Neutron Spectrum: Thermal Neutrons • Thermal/Electrical Capacity:
330 MW(t) / 100 MW(e) • Fuel Cycle: 36 months • Salient Features: Passive decay heat
removal system in the secondary side; horizontally mounted RCPs; intended for sea water desalination and electricity supply in newcomer countries with small grid
• Design status: Detailed Design
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SMR for Immediate Deployment KLT-40S
• Designer: OKBM Afrikantov – Russian Federation
• Reactor type: PWR – Floating Nuclear Cogeneration Plant
• Coolant/Moderator: H20 • Neutron Spectrum: Thermal Neutrons • Thermal/Electric capacity: 150 MW(t) /
35 MW(e) • Fuel Cycle: Single-Loading of LEU fuel
with initial uranium enrichment <20% to enhance proliferation resistance
• Salient Features: based on long-term experience of nuclear icebreakers; cogeneration options for district heating and desalination
• Design status: 2 units under construction
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SMR for Immediate Deployment SVBR-100
• Designer: JSC AKME Engineering – Russian Federation
• Reactor type: Liquid metal cooled fast reactor
• Coolant/Moderator: Lead-bismuth • System temperature: 500oC • Neutron Spectrum: Fast Neutrons • Thermal/Electric capacity: 280 MW(t) /
101 MW(e) • Fuel Cycle: 7 – 8 years • Fuel enrichment: 16.3% • Distinguishing Features: Closed nuclear
fuel cycle with mixed oxide uranium plutonium fuel, operation in a fuel self-sufficient mode
• Design status: Detailed design
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SMR for Near-term Deployment NuScale
• Full name: NuScale • Designer: NuScale Power Inc., USA • Reactor type: Integral Pressurized
Water Reactor • Coolant/Moderator: Light Water • Neutron Spectrum: Thermal Neutrons • Thermal/Electrical Capacity:
165 MW(t)/45 MW(e) • Fuel Cycle: 24 months • Salient Features: Natural circulation
cooled; Decay heat removal using containment; built below ground
• Design status: Plan to apply for certification in end of 2012
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SMR for Near-term Deployment: mPower
• Full name: mPower • Designer: Babcock & Wilcox Modular
Nuclear Energy, LLC(B&W), United States of America
• Reactor type: Integral Pressurized Water Reactor
• Coolant/Moderator: Light Water • Neutron Spectrum: Thermal Neutrons • Thermal/Electrical Capacity:
500 MW(t) / 160 MW(e) • Fuel Cycle: 48-month or more • Salient Features: integral NSSS, CRDM
inside reactor vessel; Passive safety that does not require emergency diesel generator
• Design status: Design certification application later in 2012.
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Advantages Challenges
Technological Issues
• Shorter construction period (modularization)
• Potential for enhanced reliability and safety
• Reduced complexity in design and human factor
• Suitability for non-electric application (i.e. process heat and desalination)
• Replacement for aging fossil plants, reducing GHG emissions
• Licensability (delays due to design innovation)
• Non-LWR technologies • Impact of innovative design and fuel
cycle to proliferation resistance • Operability • Spent fuel management and waste
handling policy • Post Fukushima action items on
Design and Safety
Non-Technological
Issues
• Fitness for smaller electricity grids • Options to match demand growth
by incremental capacity increase • Site Flexibility • Reduced emergency planning zone • Lower upfront investment capital
cost per installed unit • Easier financing scheme
• Economic competitiveness • Regulation for fuel or NPP leasing • First of a kind cost estimate • Availability of design for newcomers • Infrastructure requirements • Post Fukushima action items on
Institutional Issues and Public Acceptance
Perceived Advantages and Challenges
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SUSTINE Approach (Ref: Dr. Rayman Sollychin, NEFW/RR)
electricity…. hot water…. cooling…. medical isotopes…. hydrogen for backup power
SUSTINE = “Sustainable Integrated Energy” • SUSTINE Systems are customized energy systems
based on optimum integration of a locally available renewable energy system(s), a locally supportable nuclear energy system (SMR), and a locally suitable excess-energy utilizing application or energy storage system.
• Example of the excess-energy utilizing applications are desalination and hydrogen production.
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Example of SUSTINE System
Single-axis Tracking Solar System
High-temperature Gas Cooled Reactor
7000
Demand-based Electricity Distribution Management System
Desalination Plant
Electricity Grid
Local Use
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A concept from EC/JRC(Ref: Dr. David Shropshire, Petten - NL)
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IAEA Programme on Non-Electric Applications
• Contact: Dr. Ibrahim Khamis (NENP/NPTDS) • IAEA TECDOC on Efficient Water Management in Water
Cooled Reactors, to be published mid 2012 • Workshop on Efficient Water Management in Water
Cooled Reactors, 12 – 16 November 2012 • Development of Toolkit on Water Management in NPPs • Assist Member States to:
• Estimate water need in NPP • Perform comparative assess-
ment of various cooling systems • To be released mid 2012
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Water in Nuclear Power Plant
Need water during: • Construction • Commissioning • Operation • Shutdown • Decommissioning
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Water use and consumption in NPPs (for typical 1000 MWe LWR)
Water use for different secondary cooling systems (m3/MWh)
Once
Through (Withdrawal)
Cooling pond
(consumption
)
Cooling towers (consumption
)
Nuclear 95–230
2–4 3–4
Fossil-fuelled
76–190 1–2 2
Natural gas/oil cc
29–76 / 1
Typical values of water consumption during construction (approx 4–5 years) in total are: 10 000 to 40 000 m3 during excavation depending on site characteristics; 70 000 to 120 000 m3 for concrete mixing; 300 000 to 600 000 m3 supply for the construction staff depending on the site.
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Common User Considerations (CUC)
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Common User Considerations (CUC) • Sustainability of the nuclear power programme • Demand for power generation capacity • Electrical grid characteristics • Site Characteristics • Environmental Impact • Nuclear safety, regulatory framework, and
licensability • Radiation protection • Nuclear fuel cycle policies • Nuclear Waste Management • Safeguards • Security and emergency planning • National participation, industrial development • Human resource development • Economics on the nuclear energy system (NES) • Financing of NES Projects
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Benefits of Introducing SMRs
0
5
10
15
20
25
30
35
Very Important
More Important
Important
Less Important
Not Important
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Impediments of Introducing SMRs
05
10152025303540
Very Important
More Important
Important
Less Important
Not Important
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Product Requirements
Examples of Key Requirements in SMR Descriptions: • Lower upfront capital cost
• Capital cost confidence
• Readily available supply chain • Off-the-shelf components • Fewer large components
• Shorter construction schedule • Factory constructed transportable modules
• Simpler to operate and maintain • Long cycles / short outages
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Important to define and quantify product requirements
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Technology Development
Considerations for Development of SMRs: • Different for the various reactor principal lines:
• Light water reactors • Heavy water reactors • Gas cooled reactors • Liquid metal fast reactors
• Different for the various systems and components • Active safety systems • Passive safety systems
• Different depending on construction technologies • Modularization • Embedment • Long cycles / short outages
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Technology development requires staffing, facilities, time, and regulatory preparedness
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Lessons Learned on Safety • Station blackout mitigation • Multiple external initiating events and common cause failures • Ultimate heat sink for core and containment cooling in post severe accident • Reliability of emergency power supply • Optimization of the grace period (i.e. operator coping time) • Enhanced containment seismic and hydrodynamic strength • Hybrid passive and active engineered safety features • Safety viability of multiple-modules – first of a kind engineering • Wider scenario of Beyond Design Basis Accident (DBA) • Accident management, emergency response capability and costs • Seismic and cooling provisions for spent fuel pool • Hydrogen generation from steam-zirconium reaction; recombiner system • Environmental impact assessment and expectation • Control room habitability in post accident transient
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IAEA Response to the Global Trend
• Project 1.1.5.5: Common Technologies and Issues for SMRs (P&B 2010 – 2011 and 2012 – 2013)
• Objective: To facilitate the development of key enabling technologies and the resolution of enabling infrastructure issues common to future SMRs
• Activities (2012 – 2013): • Formulate roadmap for technology development • Review newcomer countries requirements, regulatory infrastructure
and business issues • Define operability-performance, maintainability and constructability
indicators • Develop guidance to facilitate countries with planning for SMRs
technology implementation
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Summary • SMR is an attractive nuclear power option particularly for
developing countries with small grids and less-developed infrastructure
• Potential for near-term deployment but much work yet to be done by stake holders
• Innovative SMR concepts have common technology development challenges: • licensability, competitiveness, financing schemes, newcomer countries requirements
• Needs to implement lessons-learned from the Fukushima Accident into the design, safety, economics, financing, licensing, and public acceptance for SMRs
• KEY: Technology Development and Deployment that demonstrate commitment to safety
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For inquiries, please contact: Dr. M. Hadid Subki <[email protected]> 36
… Thank you for your attention.
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Safety and Licensing
Aspects relevant for Safety and Licensing: • Quality Assurance • Inherent protection / fission product barriers • New regulations / emerging issues
• Digital instrumentation and controls • Proliferation resistance and physical protection/security
• Protection against internal and external events • Defence-in-depth / Diversity
• Common cause failures
• Beyond Design Basis Accident
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Economic / Generation Costs
Consideration of Overall Power Generation Costs: • Plant capital cost • Operations and maintenance costs
• Fixed • Variables
• Fuel Cycle Cost • Carrying Charges • Decommissioning cost
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Line-of-sight to compete relative to alternate Energy Technologies
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Infrastructure and Services
Examples of Infrastructure and Service needs: • Emergency planning • Quality assurance
• Regulatory reporting
• Plant security • Health physics • Plant staffing
• Supervisors / Senior Operators / Operators / Technicians • Engineering / Procurement / Administrative Support
• Radwaste processing and disposal
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Infrastructure and services need drive toward sharing among units and/or modules
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Socio-Political Considerations
Examples of Socio-Political Considerations: • National nuclear energy policy optimum energy mix • Energy security • Environmental / carbon pricing • Sustainability • Spent fuel reprocessing / waste disposal • Proliferation risks
• Safeguards reporting
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In the Globalization, socio-political considerations can transcend country borders …
