Small Modular Reactors Update on International Technology Development Activities

The 13th INPRO Dialogue Forum on Legal and Institutional Issues in the Global Deployment of SMRs 18-21 October 2016, IAEA Headquarters, Vienna

Dr. M. Hadid Subki SMR Technology Development Nuclear Power Technology Development Section Division of Nuclear Power, Department of Nuclear Energy Outline

Definition, motivation and target application

SMRs for immediate & near term deployment

SMR estimated time of deployment

SMR design characteristics

Perceived advantages and potential challenges

Prospects for the Asia Pacific Region

Elements to Facilitate SMR Deployments

2 Definition and Target Applications

Advanced Reactors that produce electric power up to 300 MW, built in factories and transported as modules to utilities and sites for installation as demand arises.

A nuclear option to meet the need for flexible power generation for wider range of users and applications Replacement of aging fossil-fired units Cogeneration needs in remote and off-grid areas Potential for enhanced safety margin through inherent and/or passive safety features Economic consideration – better affordability Potential for innovative energy systems: • Cogeneration & non-electric applications • Hybrid energy systems of nuclear with renewables

3 Driving Forces for SMRs

Scalability of Power Enhanced Safety

Modularity, Constructability Flexibility of Utilization

Images courtesy of US-DOE, NuScale, KAERI, CNEA, mPower & CNNC

4 Key expected advantages

Economic • Lower Upfront capital cost Better Affordability • Economy of serial production Modularization • Multi-module Shorter construction time • Modular Construction Flexible Application • Remote regions Wider range of Users • Small grids Smaller footprint • Reduced Emergency Site flexibility planning zone Replacement for aging fossil-fired plants Reduced CO2 production

Potential Hybrid Energy System Integration with Renewables

5 6 SMRs for immediate & near term deployment Samples for land-based SMRs

Water cooled SMRs Gas cooled SMRs Liquid metal cooled SMRs

7 SMRs Estimated Timeline of Deployment

8 Power Range of SMRs

9 Page 10 of 37 SMR Key Design Features

• Multi modules configuration – Two or more modules located in one location/reactor building and controlled by single control room •  reduced staff •  new approach for I&C system

Images reproduced courtesy of NuScale Power Inc. and BWX Technology, Inc., USA. 10 Design Features offered by SMR • Integral typed PWR – Major components within nuclear steam supply system installed inside the reactor vessel (CAREM, SMART, mPOWER, NuScale, W- SMR, ACP100, etc) •  No Large LOCA – Pressurizer within the vessel (mPower, W-SMR, NuScale, SMART) – Pressurizer outside the vessel (ACP100) – Enable multi-module plant arrangement

11 Concept of Integral PWR based SMRs Westinghou SMART se SMR

pressurize r CRDM

Steam pump generator s s Steam generator CRDM s

core + pump vessel s core + vessel

12 Integral Primary System Configuration

Benefits of integral vessel configuration: • eliminates loop piping and external components, thus enabling compact containment and plant size  reduced cost • Eliminates large break loss of coolant accident (improved safety)

13 SMR Key Design Features

• Modularization (construction technology) – Factory manufactured, tested and Q.A. – Heavy truck, rail, and barge shipping – Faster construction – Incremental increase of capacity addition as needed

Images reproduced courtesy of NuScale Power Inc. and BWX Technology, Inc., USA. 14 Design Features offered by SMR • Underground and marine based deployment – Underground sites offer: • Better protection against the impacts of severe weathers • Better seismic strength • Enhanced protection against fission product release • Improved physical security, aircraft impacts and conventional warfare – Marine based deployments offer: • Infinite heat sink (sea) • Site flexibility

15 SMR Site Specific Considerations • Site size requirements, boundary conditions, population, neighbours and environs • Site structure plan; single or multi-unit site requirements

 What site specific issues could affect the site preparation schedule and costs?  What is the footprint of the major facilities on the site?

16 Page 17 of 37 Design Features offered by iPWR- SMRs • Enhanced performance engineered safety features: Natural circulation primary flow (CAREM, NuScale)  No LOFA – Reactivity control • Internal CRDM (IRIS, mPower, Westinghouse SMR, CAREM) – No rod ejection accident • Gravity driven secondary shutdown system (CAREM, IRIS, West. SMR) – Residual heat removal system • Passive Residual Heat Removal System (CAREM, mPower, West. SMR) • Passive Residual heat removal through SG and HX submerged in water pool (IRIS, SMART, NuScale) – Safety injection System • Passive Injection System (CAREM, mPower) • Active injection System (SMART) • Flooded containment with recirculation valve

17 Page 18 of 37 Design Features offered by iPWR- SMRs • Containment – Passively cooled Containment : • Submerged Containment (Convection and condensation of steam inside containment, the heat transferred to external pool) (NuScale, W-SMR) • Steel containment (mPower) – Concrete containment with spray system (SMART) – Pressure suppression containment (CAREM, IRIS) • Severe Accident Feature – In-vessel Corium retention (IRIS, Westinghouse SMR, mPower, NuScale, CAREM) – Hydrogen passive autocatalytic recombiner (CAREM, SMART) – Inerted containment (IRIS)

18 Advantages, Issues & Challenges

Advantages Issues and Challenges

• Shorter construction period • Licensability (first-of-a-kind (modularization) structure, systems and components) • Potential for enhanced safety and • Non-LWR technologies reliability • Operability and Maintainability • Design simplicity • Staffing for multi-module plant; • Suitability for non-electric Human factor engineering; application (desalination, etc.). • Supply Chain for multi-modules • Replacement for aging fossil • Advanced R&D needs Technology Issues Technology plants, reducing GHG emissions • Fitness for smaller electricity grids • Economic competitiveness • Options to match demand growth • Plant cost estimate by incremental capacity increase • Regulatory infrastructure • Site flexibility • Availability of design for newcomers • Reduced emergency planning zone • Physical Security

Techno Issues Techno • Lower upfront capital cost (better • Post Fukushima action items on - affordability) institutional issues and public

Non • Easier financing scheme acceptance

19 SMR for Non-Electric Applications

Very high temperature reactors

Gas-cooled fast reactors

Molten Salt reactors

Supercritical water-cooled reactors

Sodium-cooled fast reactors

Liquid metal cooled reactors

Water cooled reactors 100 200 300 400 500 600 700 800 900 1000 1100 1200 District heating (oC)

Seawater desalination

Pulp & paper manufacture

Methanol production

Heavy oil desulfurization

Petroleum refining

Methane reforming hydrogen production

Thermochemical hydrogen production

Coal gasification

Blast furnace steel making 20 Identified R&D needs for SMRs

Human factor engineering, control room staffing and operational procedures for multi-module SMRs plant

Reliability, Uncertainty and Core flow stability for natural Sensitivity Analyses for circulation iPWR based integrated Control Rod Drive SMRs Mechanism in iPWRs R&D

Hybrid engineered safety system PSA for a multi-module SMR Plants development for iPWR type SMRs considering Common Cause Failures

21 Marine-based SMR Nuclear Power Plants Marine-based SMRs (Examples) KLT-40S ACPR50S FLEXBLUE SHELF

Floating Power Units (FPU) FPU and Fixed Platform Transportable, immersed Transportable, immersed NPP Compact-loop PWR Compact-loop PWR nuclear power plant Integral-PWR • 6.4 MW(e) / 28 MW(th) • 35 MW(e) / 150 MW(th) • 60 MW(e) / 200 MW(th) PWR for Naval application • 40,000 hours continuous • Core Outlet Temp.: 316oC • Core Outlet Temp.: 322oC operation period • Fuel Enrichment: 18.6% • Fuel Enrichment: < 5% • 160 MW(e) / 530 MW(th) o • Fuel Enrichment: < 30% • FPU for cogeneration • FPU for cogeneration • Core Outlet Temp.: 318 C • Combined active and passive • Without Onsite Refuelling • Once through SG, passive • Fuel Enrichment 4.95% safety features • Fuel cycle: 36 months safety features • Fuel Cycle: 38 months • Power source for users in • Spent fuel take back • Fuel cycle: 30 months • passive safety features remote and hard-to-reach • Advanced stage of • To be moored to coastal or • Transportable NPP, locations; construction, planned offshore facilities submerged operation • Can be used for both floating commercial start: • Completion of conceptual • Up to 6 module per on and submerged NPPs 2019 – 2020 design programme shore main control room

Images reproduced courtesy of OKBM Afrikantov, CGNPC, DCNS, and NIKIET

23 Small-sized Innovative Generation-IV reactors Small GEN IV reactors (Examples) PRISM 4S SVBR100 Integral MSR

Power Reactor Innovative Super Safe Small Simple Heavy Metal Liquid Cooled Integral Molten Salt Reactor Small Modular Sodium-cooled Fast Reactor Fast Reactor 100 MW Molten Salt Reactor Liquid Sodium-cooled Fast • Fuel Cycle: 30 years Lead Bismuth Eutectic • Lowest core damage Breeder Reactor cooled Fast Reactor frequency of any Generation • 10 MW(e) / 30 MW(th) • 311 MW(e) / 840 MW(th) o III reactor • Core Outlet Temp.: 510 C • 101 MW(e) / 280 MW(th) • Core Outlet Temp.: 485oC • Extensive operational • Fuel Enrichment < 20% • Core Outlet Temp.: 490oC • Fuel Enrichment: 26% Pu, experience since 1996 • Negative sodium void • Fuel Enrichment 16.5% 10% Zr • Licensed in US, Taiwan, reactivity • Fuel Cycle: 8 years • Underground containment Japan • Hybrid of active and • Hybrid of active and on seismic isolators • First concrete to first fuel … passive safety features passive safety features • For complete recycling of 39 to 45 months • Designed for remote • Prototype nuclear plutonium and spent locations and isolated cogeneration plant to be nuclear fuel islands, close to towns built in Dimitrovgrad,

Ulyanovsk

25 Floating NPP based on FPU with two KLT-40s

The design of the small cogeneration nuclear power plant (CNPP) is pilot. The FPU is being constructed at the Baltiysky Zavod, St. Petersburg, Russian Federation RP equipment supply is being completed. The NPP startup date is 2013 (the city of Vilyuchinsk, Kamchatka Region, Russian Federation). Supply to consumers is as follows Electric power 20 - 70 MWe Heat 50 - 146 gcal/h © 2011 OKBM Afrikantov

Small CNPP FPU with KLT-40S RPs UNDERWATER TRENCH 145X45 DEPTH 9 M SPENT FUEL AND RADWASTE REACTOR STORAGE PLANTS STEAM-TURBINE PLANTS

HYDRO ENGINEERING FACILITIES

HEAT POINT DEVICES FOR DISTRIBUTING AND TRANSFERRING ELECTRIC POWER TO CONSUMERS

3 3 1000 m 1000 m SALT WET STORAGE HOT WATER CONTAINER CONTAINERS

TYPE - SMOOTH-DECK NON-SELF-PROPELLED SHIP

LENGTH, m 140,0 WIDTH, m 30,0 BOARD HEIGHT, m 10,0 DRAUGHT, m 5,6 DISPLACEMENT, t 21 000 FPU SERVICE LIFE, YEARS 40

Thermal power 150 MW LOCALIZING VALVES Primary operational pressure 12.7 MPa Steam output 240 t/h STEAM LINES Steam parameters: Temperature 290°С

CRDM Pressure (abs.) 3.82 MPa Period of continuos work 26 000 h MAIN CIRCULATION PUMP Service life 40 years

STEAM GENERATO Specified lifetime 300 000 h R Refueling interval ~ 2.5-3 ys Head core lifetime output 2.1 TW·h Fuel enrichment < 20% Containment internal pressure 0.4 MPa Containment leak tightness 1% volume/day

РЕАКТОР REACTOR PRESSURIZER

EXCHANGER OF i- iii CIRCUITS HYDRAULIC TANK HYDRAULIC ACCUMULATO R

28 4S

© 2011 TOSHIBA CORPORATION • 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: Detailed Design 29 4S for Small Scale Nuclear Systems

 Independent 4S System (base applications)  Electricity/heat supply for remote area community  Electricity supply for mining site  Hot steam supply for oil sands/oil shale recovery  Electricity supply for seawater desalination  Electricity/heat supply for hydrogen production  Hybrid System by Combination of 4S, Smart Grid and Energy Storage System  Flexible energy supply for remote area  Secured energy supply for "critical" area  Electricity/heat/water/hydrogen supply as a social infrastructure

30 4S for Remote Areas

◎Barrow

◎Point Hope

◎Red Dog Ft. Wainwright ◎ ◎G. Fairbanks ◎Nome ◎Galena ◎PS. 9 Ft. Greely ◎ ◎Donlin Creek ◎Bethel ◎Seward

◎Unalaska (Map: http://www.threecordministries.org/ArcticMaps.htm)

(Map: State of Alaska, Japan Office) Current electricity price Current electricity price at Nunavut Communities at remote area In Canada in Alaska $0.39 - $0.94 per kwh $0.30 – over $1 per kwh (Radix Corporation, ANS annual meeting 2010, San Diego)

(Doyon, Limited Report, January, 2009)

31 Hybrid System (4S + Smart Grid + Energy Storage)

Community electricity Transportation heat water Smart Grid hydrogen electricity heat

electricity electricity 4S heat Energy Desalination Storage

• 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

33 Regional Co-Generation Plant with SVBR

Example of possible Location Industry Construction of terminals, port “Taman" Transportation (Krasnodarsky region) Oil and gas and chemical complex Oil & Gas (Primorsky kray.) Zheleznorudniy Ore Mining and Processing Metal industry Industrial Complex (Buryatiya) “Peschanka” gold-copper field development Mining (Chukotsky region)

Small Scale Nuclear System for Coastal Desalination • Gradual construction of regional small and medium NPPs Comprising 2 types of • 100, 200, … to 600 MWe onshore desalination plants: multi-layered • Located close to cities and distillation and reverse energy-intensive industries; osmosis, due to • sites in developing countries with flexibility and efficiency small grids for transmission and to operate in co- distribution generation mode. • remote areas, island locations, etc. Example of an onshore desalination complex Max. output – 200 000 tons/day per 1 unit

34 Integral MSR

© 2015 Terrestrial Energy • Full name: Integral Molten Salt Reactor • Designer: Terrestrial Energy, Canada • Reactor type: Molten Salt • Neutron Spectrum: Thermal Neutrons • Thermal/Electrical Capacity: 80, 300 and 600 MW(th) • Fuel Cycle: 18 months • Salient Features: Underground containment on seismic isolators with a passive air cooling ultimate heat sink; recycling center for plutonium and spent nuclear fuel

35 Risk-Informed approach and EPZ reduction

• Risk-Informed approach to “No (or reduced) Emergency Planning Zone” – Elimination or substantial reduction (NPP fences) of the Emergency Planning Zone – New procedure developed: Deterministic + Probabilistic needed to evaluate EPZ (function of radiation dose limit and NPP safety level) – Procedure developed within a IAEA CRP; discussed with NRC

CAORSO site

IRIS: 1 km

France Evacuation Zone: 5 km

US Emergency Planning Zone: 10 miles 36 Prospects of SMR for Asia Pacific Region Energy Overview of Southeast Asia

Source: Southeast Asia Energy Outlook, OECD/IEA 2015

Potential for Southeast Asia: (1) Developing an Integrated Regional Energy Market; (2) Transitioning to a Low Carbon Economy; (3) Synergy of renewables with small nuclear reactors for remote regions and small islands. 38 Total Primary Energy Demand and GDP in selected Southeast Asian countries, 1971-2013

Source: Southeast Asia Energy Outlook, OECD/IEA 2015

39 Case: SMR for Saudi Arabia Source: K.A.CARE Presentation at the IAEA’s 59th General Conference Side Event on SMR Deployment Gradual Offsetting of Fossil 50% by 2040

• Bilateral nuclear cooperation agreement signed between governments of Saudi Arabia and Republic of Korea in November 2011

• Pre-Project Engineering for 2x100 MWe SMART plant construction

• An on-going cooperation between K.A.CARE and KAERI; MoU signed in September 2015

• Desire for full IP ownership of NSSS technology

• Future SMR export market in MENA Day-night load variation for Saudi Arabia

• Nuclear cogeneration for remote cities & industry

• Coastal and inland SMR site availability

40 Case: SMR for Indonesia Source: National Nuclear Energy Agency of Indonesia (BATAN) Serpong’s national R&D complex

• Through an open-bidding, an experimental HTR-type SMR was selected in March 2015 for a basic design work aiming for a deployment in 2022 – 2023.

• Time constraint for land acquisition and licensing.

• Site: National R&D Complex in Serpong where 30 MWe in operation Spread of Minerals in Indonesia

• BATAN works with the regulatory body on licensing • Potential SMR for cogeneration, i.e. for mineral processing following 2014 ban on export of unprocessed minerals. To be promoted as international project.

41 Ranges of LCOE associated with new construction at 7% Discount Rate

Source: IAEA Climate Change and Nuclear Power 201542 Attributes and Indicators to assess SMR Deployment Potential Financial and Physical and Legal Carbon Reduction Demand and Energy Economic Infrastructure Incentives

Gross Domestic Product Gross Domestic Product Total Installed Electric Carbon Dioxide Growth Rate (PPP) Capacity Emissions Per Capita Fossil Fuel Energy Growth Rate Primary Per Capita GDP Infrastructure Index Consumption Energy Consumption (PPP) (% of Total) Per Capita Energy International Trade Ease of Doing Business Oil, Gas, Coal Consumption (% of GDP) Index (% of Electric Capacity) Foreign Direct Percent Rural Energy Imports Investment, Net Inflow (% Rule of Law Index Population (% Total Energy Use) of GDP) Political Stability and Credit Rating / Desalination Capacity Absence of Violence Uranium Resources External Debt Stock Index District Heating

Demand Legend Purple denotes SMR or Size specific Indicator Energy Intensive Green denotes nuclear specific indicator Industries * Used in current baseline assessment 43 Key Economic Considerations for SMRs

Key issues Large Nuclear Power Plants SMRs Calculated levelized o Proven lower ¢/kW.h generating Potential lower levelized costs costs cost compared to SMRs (economy of multiples) o Still struggling to compete with natural gas Capital cost o Huge upfront capital cost o Fractional upfront capital cost o Economy of scale o Easier to finance o Economy of serial production O&M cost Stable (Less variation) o Potential lower cost o Could fluctuate due to uncertainty in plant staffing for multi-module plant and security force Fuel cost o Inherently low; (9 – 15)% of total o Could have the same fraction to cost; technology dependent total cost as large NPPs o On going R&Ds on advanced o Many CHF tests for new safer and more economical fuel truncated LWR fuels for licensing Decommissioning o High decommissioning cost Smaller cost of decommissioning: costs o More time required o Replaceable modules o Factory disassembled/ decommissioned

44 Capital costs for SMRs

Key Topics Prospects Issues Potential decrease in case of large Require large initial order Capital component of levelized cost of power scale and serial production Design saving Standardization of new structure, Comparison of material quantities system, components and materials o Reduced construction time for First of a kind deployment of multi- proven design module plant with modularization Impact of local labour and productivity o Lesser work force required with construction technology vs stick- modular construction build Based on LWRs technology - easier First of a kind; Time required for Cost of licensing licensing modifying the existing regulatory and legal frameworks Better flexibility to incorporate Plant design and costs include Fukushima Additional cost required for lessons-learned from the Fukushima- related safety improvements R&D on new safety system type accident Learning effect: the higher the number Cost impact by delayed component Ensuring all necessary equipment is of SMR built on the same site is, the delivery or defect during shipping included in the cost estimate, e.g. there is no better the cost effectiveness of ‘missing equipment’ construction activities on site Assurance of reliable estimates of Similar among vendors Manufacturing of FOAK technology holder equipment prices components

45 SMR Operation & maintenance (O&M) costs

Key Topics Prospects Issues

Evaluation of projected O&M with Operating experience may lead to Need to gain O&M experience comparisons to experience efficient SMR operation Staffing Regulatory-based well agreed Staffing of multi-module plant need number of staffs required to be addressed Plant design features to reduce O&M cost Design simplicity and proven Design simplicity yet FOAK

Impact of localization versus O&M contract Applicable in countries with capable o In contrary with the principle of industries applying stick-built modularization o Embarking countries with limited industries Opportunities and costs for shared spare o Modular construction with o Sustainability of components parts pool factory built modules supply chain o Multi-module plant Reliance on passive design and redundant High level of passive or inherent o Cost for R&D and V&V for system trains to optimize operation and safety features with better O&M FOAK technology maintenance on-line cost Optimized outage schedules based on Multi-module plant: o Plant specific outage scheme equipment performance and trending data, o Redundancy of production unit proposed, but yet to be proven real and historic (Better flexibility)

 What is the technology holder’s estimate of the O&M cost advantage or penalty for the proposed facility (cost/kW·h) versus the O&M costs reported for today’s fleet? 46 Cost of Specific Utilization

Keys Topics Prospects Issues Flexible operation “Load follow” is an imbedded Varied from technical to capability of all SMRs safety to O&M cost for high frequency/amplitude flexible operation Cogeneration (e.g. o SMR power output suits well • How many large NPPs desalination, district with existing heat and with desalination heating, hydrogen desalination plants cogeneration? – production) o Multi-module: guarantee of operating/utilization continuous supply experience • Near-term SMR designs are certified for electricity production plant only.

Remote grids o Can be connected to small o Site specific and weak grids, where large o Proper infrastructures NPPs are not feasible required which may not o Where non-electric products be available in remote (heat or desalinated water) are areas as important as the electricity

47 Elements to Facilitate Deployment

Design Development and Deployment Issues Average Ranking SMRs with lower generating cost 1 SMRs inexpensive to build Multi-modules SMR and operate 2 deployment

3 SMRs with flexibility for Passive safety systems cogeneration 4

SMRs with automated Modification to regulatory, operation feature licensing

SMRs with enhanced prolif Transportable SMRs with resistance sealed-fueled Average Ranking (1 Is Build-Own-Operate project scheme Most Important) 48 Publication on SMRs Published Published

Features of the Publication: • Present technical lessons-learned from sequence of events of the accident relevant with SMRs; • Provide technical considerations to enhance the design of engineered safety features of SMRs; Features of the Publication: • Water cooled SMR designs apply stringent Defence-in-Depth to cope with Severe Accidents; • Multi-module SMRs shall have mitigation measures of Cascading Effects of a Severe Accident; • IAEA provides guidelines to incorporate SMR specific design features and deployment conditions. https://aris.iaea.org/Publications/SMR-Book_2016.pdf 49 http://www-pub.iaea.org/MTCD/Publications/PDF/TE-1785_web.pdf Publication on SMRs Upcoming

Nuclear Energy Series NP.T.3-1x: Technology Roadmap of SMRs for Near Term Deployment: • Management Tool to avoid and resolve barriers to product deployment • Present “model” roadmaps for Designers and Licensees for strategic planning • OECD/NEA countries contributed • To be published in Q1 2017

50 Summary  IAEA is engaged to support Member States in SMR Technology Development and Deployment  SMR is an attractive option to enhance energy supply security  In newcomer countries with smaller grids and less-developed infrastructure  In advanced countries for power supplies in remote areas and/or specific applications  Innovative SMR concepts have common technology development challenges, including regulatory and licensing frameworks  Studies needed to evaluate the potential benefits of deploying SMRs in grid systems that contain large percentages of renewable energy.  Studies needed to assess SMR “target costs” in future cogeneration markets, the benefits from coupling with renewables to stabilize the power grid, and impacts on sustainability measures from deployment.

51 Thank you!

For inquiries on SMR, please contact: Dr. M. Hadid Subki IAEA Nuclear Power Technology Development Section [email protected]