9th GIF-IAEA Interface Meeting IAEA Headquarters, Vienna. 4-5 March 2015

Reactor technology development status report:

Hadid Subki Technology Development Section (NPTDS) Division of Nuclear Power, Department of Nuclear Energy

IAEA International Atomic Energy Agency Outline

• Definition, motivation, driving forces • SMRs under construction • SMRs for near term deployment • SMRs specific design features • SMRs safety, safeguards, security • Key barriers, challenges to deployment • Elements to facilitate deployments • On-going activities: publications & meetings

IAEA 2 Page 3 of 37 Small Modular Reactors Advanced Reactors that produce electric power up to 300 MW, built in factories and shipped as modules to utilities and sites for installation as demand arises.

IAEA Land-based, marine-based, factory fuelled transportable SMRs Motivation – Driving Forces …

• The need for flexible power generation for wider range of users and applications; • Replacement of aging fossil-fired units; • 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

IAEA 4 Page 5 of 37 SMRs Under Construction for Immediate Deployment – the front runners …

Country Reactor Output Designer Number Site, Plant ID, Commercial Model (MWe) of units and unit # Start Argentina CAREM-25 27 CNEA 1 Near the Atucha-2 site 2017 ~ 2018

China HTR-PM 250 Tsinghua 2 mods, Shidaowan unit-1 2017 ~ 2018 Univ./Harbin 1 turbine Russian KLT-40S 70 OKBM 2 Akademik Lomonosov units 1 & 2 2016~2017 Federation (ship-borne) Afrikantov modules RITM-200 50 OKBM 2 RITM-200 nuclear-propelled 2017 ~ 2018 (Icebreaker) Afrikantov modules icebreaker ship

CAREM-25 HTR-PM KLT-40S

IAEA SMRs under development for Near-term Deployment Page 6 of 37 - Some samples … Electrical Name Design Country of Capacity, Design Status Organization Origin MWe System Integrated Standard Design Approval 1 Modular Advanced Korea Atomic Energy Republic of Korea 100 Reactor (SMART) Research Institute Received 4 July 2012 B&W United States of Preparing for Design 2 mPower Generation mPower America 180/module Certification Application United States of 50/module Preparing for Design 3 NuScale NuScale Power Inc. America (gross) Certification Application Detailed Design, 4 ACP100 CNNC/NPIC China 100 Construction Starts in 2016 mPower NuScale ACP100 SMART

IAEA Page 7 of 37 Design Features offered by SMR

• 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

IAEA Page 8 of 37 Design Features offered by SMR

• 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, CAREM, mPower) • Active injection System (SMART) • Flooded containment with recirculation valve

IAEA Page 9 of 37 Design Features offered by SMR

• 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)

IAEA Page 10 of 37 SMRs in terms of Safety Performance

• Further improve passive safety technology • Incorporates lessons-learned from major accidents to enhance performance of engineered safety features: • Separation of reactor trip logic and ESF initiator, diversity in core cooling and high pressure depressurization means; station blackout mitigation systems; filtered venting • Resilience and robustness to multiple external events

IAEA 10 Key Design Characteristics of Page 11 of 37 Advanced Passive Water-Cooled Reactors

1 Independent of AC Power 2 Less reliance on operator action • Require no AC power to actuate Provides 3 to more than 7 days of reactor cooling /operate Engineered Safety without AC power or operator action Features; • Only gravity flow, condensation natural circulation forces needed 4 Incorporating lessons-learned from the to safely cool the reactor core Fukushima Dai-ichi nuclear accident • Passively safe shutdown the • Enhanced robustness to extreme external events reactor, cools the core, and by addressing potential vulnerabilities removes decay heat out of • Alternate AC independent water additions in containment Accident Management – SBO mitigation • Ambient air as alternate Ultimate Heat Sink • Filtered containment venting 3 Design simplification • Diversity in Emergency Core Cooling System

• Fewer number of plant systems and components • Reducing plant construction and O&M costs

IAEA 11

Images Courtesy of Westinghouse and GE Nuclear Energy Page 12 of 37 Incorporating Lessons Learned from Major Accidents to Advanced Reactor and SMR Developments

Resilience towards Extreme external events (regions and sites specific)

• Assure safety on multiple reactors or modules plant • Diversity in emergency core cooling systems following loss of all AC power onsite • Ensure diversity in depressurization means for high pressure transient • Confirm independence in reactor trip and ECCS for sensors, power supplies and actuation systems.

• Hydrogen control for DBA & severe accidents • Filtered venting system • Enhanced instrumentation and monitoring system for DBA & severe accidents • Diversity in spent fuel cooling (reliability) • Effective use of PSA • Emergency preparedness and response IAEA SMR – iPWR type: integration of NSSS

Integration of ACP CAREM NuScale SMART mPower WEC IRIS IMR components 100

Pressurizer O O out O O O O O Steam Generators O O O O O out O O

Pumps NC NC O NC

CRDMs O O O O

SIZE MWth 100 160 310 330 530 800 1000 1000 MWe 25 45 100 100 180 225 335 350

IAEA 13 2 SMR – iPWRs: needs for testings

• Integrated components: pumps, steam generators,

CRDMs, pressurizer

• Safety systems: (usually) passive, natural circulation, Separate Effect Test (SET) two-phase flow systems

• Integral layout: integration of components, safety systems, (containment) Integral Effect Test (IET)

Main goals: i) to test safety effectiveness, performance ii) to validate codes & models IAEA 14 Page 15 of 37 SMRs in terms of Safeguards (1) • Collaborations of IAEA with Brookhaven NL and Pacific Northwest NL, USA • In-house IAEA collaborations of SG, INPRO and NPTDS • Supporting non-proliferation through safeguards by design for small modular reactors • Summary of Approaches for Evaluation of Proliferation Resistance and Safeguardability for SMRs • GIF: analytical framework, threats, pathways, outcomes • INPRO: user requirements, check list, rules of good practice • How they can be used together to enhanceIAEA SMR safeguardability Page 16 of 37 SMRs in terms of Safeguards (2)

• Small power  small radio logical inventory  smaller release during off-normal conditions • Small physical footprint  smaller security force  fewer surveillance • Higher enrichment levels for some SMRs • Remote locations of facilities present new challenges for inspection

IAEA 16 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 IAEA 17 Page 18 of 37 Key Barriers/Challenges to Deployment

• Limited near-term commercial availability of SMR designs for embarking countries • Capacity building in embarking countries’ nuclear regulatory authority for advanced reactors depends on the preparedness of vendor countries’ regulatory and licensing infrastructures • Technology developers to enhance the ability to secure significant additional EPC contracts from investors to provide the financial support for design development and deployment: first domestic, then international markets • Lower price of natural gas in some countries including the US limits the need of utilities to adopt nuclear power. • Unless the development and deployment were fully state-funded • Economic competitiveness over alternatives • Regulatory, licensing and safety issues in Post Fukushima. IAEA Page 19 of 37 Elements to Facilitate SMR Deployment

SMRs with lower generating cost 1 SMRs inexpensive to build Multi-modules SMR and operate deployment 2

3 SMRs with flexibility for Passive safety systems cogeneration 4

5

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 Most Important) IAEA scheme Key On-going IAEA Activities on SMR in 2014 – 2015 (Publications)

No. Activities Notes • Contribution to IAEA Action Considerations to Enhance the Performance of Plan on Nuclear Safety, #12: Engineered Safety Features in Water-Cooled SMR in Utilizing Effective R&D 1 coping with Extreme Natural Hazards • CM to Finalize the TECDOC is An IAEA Technical Document (TECDOC) taking place this week, 2 -5 March 2015 • US-PUI funded activity. Technology Roadmap for Small Modular Reactor • Lead by a US-CFE in NPTDS 2 Deployments (Nuclear Energy series report) • CM to Finalize the NE Series: Polimi, Milano, 14-16 April

Environmental Impact Assessment for SMR Deployments • US-PUI funded activity. 3 • US NRC & CNSC the chairs (NE series report) - COMPLETED • 14 Member States contributing • ORNL & CNSC the chairs Instrumentation and Control Systems for Small Modular • 9 Member States contributing 4 Reactors (NE series report) • CM to Finalize the NE Series: IAEA, Vienna, 16-20 March Options to Enhance Energy Supply Security using Hybrid • EC-JRC & NE/PESS the chairs 5 Energy Systems based on SMR – Synergizing nuclear and • 9 Member States contributing renewables (NE series report) - COMPLETED Engineering Designs and Operations of Integral-PWR type • Not started yet 6 IAEA 20 Small Modular Reactors (IAEA-TECDOC) • DPP approved in 2014 Key On-going IAEA Activities on SMR in 2014 – 2015 (Technical Meetings)

No. Technical Meetings (TM) Place, Dates TM on Economic Analyses for High Temperature Gas- • IAEA, Vienna, Austria 1 Cooled Reactors and Small Modular Reactors • 24 – 28 August 2015 TM on Technology Roadmap for Small Modular Reactor • IAEA, Vienna, Austria 2 Development for Near Term Deployment • 12 – 15 October 2015 TM on Technology Assessment of integral-PWR type • CNNC, Beijing, China 3 Small Modular Reactors for Near Term Deployment in • Being postponed to Embarking Countries 11 – 14 January 2016

IAEA 21 THANK YOU VERY MUCH New Publication on SMR that covers Up-to-Date Water-Cooled and High Temperature Gas-Cooled SMR Designs Information Please download from: http://www.iaea.org/NuclearPower/SMR

For inquiries on SMR, contact: IAEA Dr. M. Hadid Subki