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The Status of Different SMR Technologies and the Role of the IAEA to Support Its Member States in SMR Technology Development

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The Status of Different SMR Technologies and the Role of the IAEA to Support Its Member States in SMR Technology Development The status of different SMR technologies and the role of the IAEA to support its Member States in SMR Technology Development Frederik Reitsma Team Leader (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 Prospects for SMRs Cogeneration and Integration with Renewables SMR design characteristics Perceived advantages and potential challenges IAEA Activities 2 SMR: definition & rationale of developments Advanced Reactors to produce up to 300 MW(e), built in factories and transported as modules to sites for installation as demand arises. A nuclear option to meet the need for flexible power generation for wider range of users and applications 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 3 SMRs for immediate & near term deployment - SMR designs overview - Selection of SMRs considered ready for near term deployment IAEA SMR Booklet 2018 Edition • Main Features . Design description and main features of 56 SMR designs . SMRs are categorized in six(06) types based on coolant type/neutron spectrum: Land Based WCRs Marine Based WCRs HTGRs Fast Reactors MSRs Others MANY designs not included / not submitted 5 Page 6 of 37 SMRs Under Construction for Immediate Deployment – the front runners … Country Reactor Output Designer Number Site, Plant ID, Startup Model (MWe) of units and unit # Commissioning Argentina CAREM-25 27 CNEA 1 Near the Atucha-2 site 2022 China HTR-PM 210 INET, 2 mods, Shidaowan unit-1 2019 Tsinghua 1 turbine Russian KLT-40S 70 OKBM 2 mod x Akademik Lomonosov units 1 & 2 2019 Federation (ship-borne) Afrikantov 35 MWe RITM-200 50 OKBM RITM-200 nuclear-propelled 2019 (Icebreaker) Afrikantov icebreaker ship CAREM-25 HTR-PM KLT-40S 6 SMRs: Under Construction CAREM KLT-40S HTR-PM Image Courtesy of CNEA, Argentina Image Courtesy of Afrikantov, Russia Image Courtesy of Tsinghua University, China Under Construction Under Commissioning Under Construction Integral PWR type SMR Floating PWR type SMR HTGR type SMR Naturally circulation Forced circulation Forced circulation • 30 MW(e) / 100 MW(th) • 35 MW(e) / 150 MW(th) • 210 MW(e) / 2x250 MW(th) • Core Outlet Temp: 326oC • Core Outlet Temp: 316oC • Core Outlet Temp: 750oC • Fuel Enrichment: 3.1% UO2 • Fuel Enrichment: 18.6% UO2 • Fuel Enrichment: 8.5% TRISO • In-vessel control rod drive • Floating power unit for coated particle fuel mechanisms cogeneration of heat and • Inherent safety, no need for • Self-pressurized system electricity; onsite refuelling not offsite safety measures • Pressure suppression required; spent fuel take back to • Multiple reactor modules can containment system the supplier be coupled with single steam • First Criticality: 2022 • Commercial Start-up: 2019-20 turbine • Commercial operation: 2019 • The HTR-PM 600 (6 modules) are under design and several potential sites identified 7 SMRs: Near Term Deployable NuScale SMART ACP-100 Image Courtesy of NuScale Power, USA Image Courtesy of KAERI, Republic of Korea Image Courtesy of CNNC(NPIC/CNPE), China Under regulatory review Standard design approval (2012) Basic Design Completed Integral PWR type SMR Integral PWR type SMR Integral PWR type SMR Forced circulation Forced circulation Naturally circulation • 100 MW(e) / 330 MW(th) • 125 MW(e) / 385 MW(th) • 50 MW(e) / 160 MW(th) per • Core Outlet Temp: 323oC • Core Outlet Temp: 319oC module - upgraded to 60 MW(e) • Fuel Enrichment: <5% UO • Fuel Enrichment: <4.95% UO2 o 2 • Core Outlet Temp: 314 C • Coupling with desalination and • In-vessel control rod drive • Fuel Enrichment: <4.95% UO2 process heat application mechanisms • 0.5g peak ground accelerations • Pre-project engineering • nuclear island underground • Modules per plant: 12 agreement between Korea and • Preliminary safety assessment • Containment vessel immersed in Kingdom of Saudi Arabia for the report (PSAR) finished reactor pool that provide deployment of SMART in the Gulf • An industrial demonstration unlimited coping time for core country plant with one 385 MW(t) unit cooling • Design update (increased power is planned in Hainan Province • Multi-purpose Energy use: and more passive safety • IAEA conducted a generic Electricity and process heat features) to be submitted for safety review applications design approval 8 SMRs: Generation-IV Designs SEALER EM2 IMSR Image Courtesy of LeadCold, Sweden Image Courtesy of General Atomics, USA Image Courtesy of Terrestrial Energy Inc., Canada Conceptual Design Conceptual Design Conceptual / Basic Design Small lead-cooled battery Modular high temperature gas- Molten Salt Reactor cooled fast reactor Forced circulation Forced circulation • 3 MW(e) / 8 MW(th) Forced cooling with helium • 190 MW(e) / 400 MW(th) per • Core Outlet Temp: 432oC • 265 MW(e) / 500 MW(th) module o o • Fuel Enrichment: <20% UO2 • Core Outlet Temp: 850 C • Core Outlet Temp: ~700 C • Non-pressurized • Fuel Enrichment: 14.5% UO2 • Fuel Enrichment: < 5% • The primary market for • Silicon carbide composite • Completely sealed reactor SEALER is constituted by Arctic cladding and fission gas vessel with integrated pumps, communities and mining collection system heat exchangers and operations which today • Use a combined power shutdown rods; core-unit is depend on diesel generators conversion cycle - direct helium replaced completely as a for production of power and Brayton cycle and a Rankine single unit every seven years heat bottoming cycle • Conceptual design complete – • Modules per plant: 4 basic engineering in progress 9 Water Cooled SMR Designs for district heating DHR-400 RUTA-70 Image Courtesy of CNNC, China Image Courtesy of , NIKIET, Russian Federation Basic Design Conceptual Design Pool Type SMR Pool type SMR Forced circulation Natural / Forced circulation 0 MW(e) /400 MW(th) • • 0 MW(e) / 70 MW(th) Core Outlet Temp: 98oC • • Core Outlet Temp: 102oC Fuel Enrichment: <5% UO • 2 • Fuel Enrichment: 3% UO Designed to replace traditional coal 2 • • Designed for low temperature plants for district heating process heat, coupling with Multi-purpose applications including • desalination system, radioisotope district heating, sea water desalination production or other applications & radioisotope production • Seeking a construction license in 2019 • First plant that is expected to be built in Xudapu, Liaoning, China. 10 SMR Designs Based on Power Range • IMR • UKSMR • IRIS > 301 • VBER-300 • Westinghouse LFR • DMS • SC-HTGR 251-300 • BREST-OD-300 • GT-MHR • Stable Salt Reactor • Westinghouse SMR • MHR-T 201-250 • ThorCorn ) • LFTR • Em2 • mPower Primary Pumps Primary Heat Exchangers • FUJI Graphite Moderator • IMS R 151-200 IMSR Core-Unit • CAP200 Guard Vessel Silo • PBMR-400 • France SMR Control channels • HTR-PM Supporting truss • CMSR Reactor 101-150 monoblock (RMB) • SVBR100 Equipment of reactor cavity • SUPERSTAR Power Power MW(eRange • ACP100 • nuScale • S MART 51-100 • ACPR50S • MHR100 • MK1-PBFHR • CAREM25 • LFR-TL-X • CA Waste Burner 0-50 • A-HTR-100 • S EALER Scheme of LFR-TL-5, LFR-TL-10, LFR-TL-20 • eVinci Reactor Designs 11 SMR Technology Development RUSSIA VK-300 SVBR-100 VBER-300 RITM-200 UNITERM ELENA KLT-40S BREST300-OD VVER-300 ABV6-M SHELF CANADA RUTA-70 IMSR MHRs SWEDEN FRANCE SEALER DENMARK SMR CMSR KOREA CA WB SMART UK USA UK SMR LUXEMBOURG mPower SSR JAPAN LFR-AS-200 DMS NuScale ITALY 4S W-SMR IRIS IMR SMR-160 CHINA 2 EM HTR-PM ACPR50S GT-MHR ACP100 CAP150 SUPERSTAR Xe-100 SC-HTGR W-LFR INDONESIA ThorCorn SOUTH AFRICA AHTR-100 ARGENTINA HTMR-100 -25 CAREM PBMR-400 12 Prospects for SMRs - Some Technology Developer Member State activities - New-comers interest Status and major accomplishment in Technology Developer Countries Countries Recent Milestone Argentina CAREM25 is in advanced stage of construction. Aiming for fuel loading & start-up commissioning in 2019 CNSC is performing design reviews for several innovative SMR designs, mostly non-water cooled, including molten Canada salt reactors (MSR) • HTR-PM is in advanced stage of construction. Commissioning expected in 2018. • ACP100 completed IAEA generic reactor safety review. CNNC plans to build ACP100 demo-plant in Hainan China Provence in the site where NPPs are already in operation. • China has 3 floating SMR designs (ACP100S, ACPR50S and CAP-F) France • Propose a new French SMR design (Consortium of TechnicAtome, CEA, EDF, Naval Group, Investir L`Avenir) SMART (100 MWe) by KAERI certified in 2012. • SMART undertakes a pre-project engineering in Saudi Arabia, for near-term construction of 2 units. Republic of Korea • Updated design with increased power and more passive safety features developed • New design will be submitted for certification in Korea in parallel with KSA licensing application • Akademik Lomonosov floating NPP with 2 modules of KLT40S is in advanced stage of construction and Russian Federation commissioning. Aiming for commissioning in 2019. • AKME Engineering will develop a deployment plan for SVBR100, a eutectic lead bismuth cooled, fast reactor. • Rolls-Royce recently introduced UK-SMR, a 450 MW(e) PWR-based design; many organizations
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