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7 Summary of Global SMR Development Forum for Nuclear Cooperation in Asia (FNCA) The 6 th Study Panel on the Approaches toward Infrastructure Development for Nuclear Power Hanoi, Vietnam, August 2014 (video conference) Small Modular Reactors in terms of Safety, Economy, Waste Management and Non-proliferation Dr. M. Hadid Subki Technical Lead: SMR Technology Development Division of Nuclear Power, Department of Nuclear Energy mpower NuScale W-SMR SMR-160 EM 2, GTMHR SMART KLT-40s SVBR-100 BREST-300 SHELF Flexblue CAREM-25 US-DOE provides funding for mpower and NuScale designs. The total funding is 452M$/5 years for 2 out of 4 competing ipwr based-smrs. Some have utilities to deploy in specific sites. On 4 July 2012, the Korean Nuclear Safety and Security Commission issued the Standard Design Approval for the 100 MWe SMART the first ipwr received certification. Construction of 2 modules of barge-mounted KLT-40s near completion; Lead Bismuth cooled SVBR-100 & Lead-cooled BREST-300 to deploy by 2018, SHELF seabed-based conceptual design DCNS originated Flexblue capsule, MWe, m seabed-moored, 5-15 km from the coast, off-shore and local control rooms Site excavation for CAREM-25 completed; licensed for construction, first concrete pouring ~ November 2013, now under construction International Atomic Energy Agency 4S PFBR-500 AHWR300-LEU Toshiba had promoted the 4S for a design certification with the US NRC for application in Alaska and newcomer countries. The Prototype FBR ready for commissioning and start-up test. AHWR300-LEU at detailed design. 11 Map of Global SMR Technology Development Summary of Global SMR Development (cont d) CEFR HTR-PM ACP-100 CAP-150 IRIS 2 modules of HTR-PM under construction; CNNC developing ACP-100 which will be constructed by 2018 SNPTC developing CAP-150 and CAP-S Politecnico di Milano (POLIMI) and universities in Croatia & Japan are continuing the development of IRIS design - previously lead by the Westinghouse Consortium ACP-100, CNNC, China CAP-150, SNERDI, China Flexblue, DCNS, France 12 Motivation Driving Forces Reactors Under Construction under SMR category front runners 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 Country Reactor Output Designer Number Site, Plant ID, Commercial Model (MWe) of units and unit # Start Argentina CAREM CNEA 1 Near the Atucha-2 site 2017 ~ 2018 China HTR-PM 250 Tsinghua 2 mods, Shidaowan unit ~ 2018 Univ./Harbin 1 turbine India PFBR IGCAR 1 Kalpakkam 2014 Russian Federation KLT-40S (ship-borne) 70 OKBM Afrikantov 2 modules Akademik Lomonosov units 1 & ~

8 Water-cooled SMRs for Near-term Deployment Integral-PWR Small Modular Reactors Name Design Organization Country of Origin Electrical Capacity, MWe Design Status System Integrated 1 Modular Advanced Korea Atomic Energy Standard Design Approval Reactor (SMART) Research Institute Republic of Korea 100 Received 4 July mpower B&W Generation mpower United States of America 180/module Design Certification Application NuScale NuScale Power Inc. United States of America 45/module Design Certification Application mid ACP100 CNNC/NPIC China 100 Detailed Design, Construction Starts in 2016 SMART mpower Gas Cooled SMRs PBMR South Africa HTR-PM China GT-MHR USA NuScale ACP EM 2 USA Issues on licensing and safety in deploying SMR The need to develop legal and institutional frameworks, particularly for deployment in foreign market; Lack of human resource, skills and capacity, limited operating experience in advanced SMRs; Public acceptance, lack of persistent support from governments, and no laws and regulations for both NPP and SMR in new entrants; The need to assure that SMR regulatory framework is applied commensurate with attended risk, so deployment can be accomplished in a cost-effective manner and competitive with alternative energies; Long lead-time to prepare for and receive regulatory review; The need to get sufficient regulatory credit for inherent safety and security in the design; For SMR with innovative features: review code & standards that impact licensing. Could take 2 5 years to develop and approve revisions. Embarking countries lack of infrastructure and HR to conduct technology assessment and R&D for HR development; 6th INPRO Dialogue Forum on 29 July - 2 August Licensing and Safety Issues of SMRs 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. CEFR SVBR 100 4S PRISM Full name China Experimental Lead-Bismuth Eutectic Super-Safe, Small Power Reactor Fast Reactor Fast Reactor 100 & Simple Innovative Small Mod. Designer China Nuclear Energy AKME Engineering TOSHIBA, CRIEPI GE Hitachi Industry Corporation RUSSIAN Federation JAPAN USA Reactor type Liquid metal cooled Liquid metal cooled Liquid metal-cooled Liquid metal cooled fast reactor fast reactor fast reactor fast breeder reactor Thermal power 65 MW 280 MW 30 MW 840 MW Electrical power 20 MW 101 MW 10 MW 311 MW Coolant Sodium Lead-Bismuth Sodium Sodium S. Pressure Low pressure 6.7 MPa Non pressurized Low pressure S. Temperature 530 o C 500 o C 510 o C 485 o C Key features Fast neutrons for Indirect Rankine Indirect Rankine cycle Uses heterogeneous irradiation testing; Cycle, Passive safety metal alloy core Design status Detailed Detail Detail Detail Deployment Liquid-Metal Cooled, Fast Spectrum SMRs Connected to grid 2011 ~ 2019 ~ 2022 Study for UK Major Findings (1) Global status for SMR development and deployment 9 countries developing ~40 SMR designs with different time scales of deployment and 4 units under construction (CAREM25, HTR-PM, KLT-40s, PFBR500) Most embarking countries understand SMR benefits and acknowledged SMRs as a viable option for future nuclear energy The number of SMR designs is overwhelming and there is interest in modular and integral plants In most countries, no differences on licensing process and basic safety requirements between SMRs and large NPP Some countries are applying pre-application review process by interaction with vendors to reduce licensing risk 34 Technological Issues Non-Technological Issues Potential Advantages & Perceived Challenges by Investors & Users Advantages Shorter construction period (modularization) Potential for enhanced safety and reliability Design simplicity Suitability for non-electric application (desalination, etc.). Replacement for aging fossil plants, reducing GHG emissions Fitness for smaller electricity grids Options to match demand growth by incremental capacity increase Site flexibility Reduced emergency planning zone Lower upfront capital cost (better affordability) Easier financing scheme Challenges Licensability (due to innovative or first-of-a-kind engineering structure, systems and components) Non-LWR technologies Operability performance/record Human factor engineering; operator staffing for multiple-modules plant Post Fukushima action items on design and safety Economic competitiveness First of a kind cost estimate Regulatory infrastructure (in both expanding and newcomer countries) Availability of design for newcomers Infrastructure requirements Post Fukushima action items on institutional issues and public acceptance 24 Major Findings (2) Key issues identified: Concerns on International Design Certification and international cooperation to address Plug and Play approach Need to consider how to select an optimum design among diverse technologies and put the highest priority on proven technology Consensus on importance of public participation and perception in SMR licensing process and deployment program Different approaches to safety assessment of stationary based SMRs Infrastructure issues in the newcomer country for TNPP Regulatory positions on cyber security, I&C design, severe accident mitigation, acceptable passive features and forms of inherent safety, SMR related terminology, and emergency planning Reduced EPZ for SMRs, reduction of plant operating staff. 35

9 .1 Summary SMR is an attractive option to enhance energy supply security in advanced countries requiring power supplies in remote areas and/or specific purpose and in newcomer countries with small grids and less-developed infrastructure ; Innovative SMR concepts have common technology development challenges: licensability, competitiveness, control room staffing for multi-modules plant, and so forth Needs to find measures to secure more EPC contracts from investors to financially support development and deployment Facilitate capacity building in newcomer countries Capability to perform technology assessment Domestic deployment in vendors countries is important to encourage newcomer countries to adopt SMR Technique features (2) ACP100 technique features CF2 shortened fuel assemblies, the 1717 square pitch arranged fuel assemblies developed independently by CNNC, are adopted. Refueling cycle is 24 months. ML-B CRDMs, the magnetism lifting type CRDM developed independently by CNNC, are adopted. 37 ACP100 technique features Technique Features, Potential Advantages and Challenges of ACP100 SMR of China XU Bin (xubilly@163.com) National Key Laboratory of Science and Technology on Reactor System Design Technology, Nuclear Power Institute of China Forum for Nuclear Corporation in Asia (FNCA) The 6 th Meeting of Study Panel on the Approach toward Infrastructure Development for Nuclear Power August 26-27, 2014, Hanoi, Vietnam Technique features (3) The Compositive Head Package (CHP), which unites the RPV head, lifting rigs, in-core instrumentations and anti-seismic structure, is introduced. RPV support modules reliably support RPV onto the reinforced concrete structure. ACP100 technique features Reactor type & Technique route ACP100 technique features Technique features (4) Adopt integrative layout in stead of the traditional distributed layout. Eliminate large LOCA accident by design. Eliminate the technique risk to the most extent, by utilizing existing PWR technique storage and industry foundation, and verified new techniques. Passive core cooling system is composed of core makeup tank, accumulator and in-containment refueling water storage tank, by which core residual heat is exported, and finally long term cooling is realized by reactor cavity flooding recycle. Passive residual heat removal system is used for transferring heat from primary side to incontainment refueling water storage tank. Technique features (1) ACP100 technique features OTSGs are placed inside RPV. Main coolant pumps sit on the pump headers of RPV. PZR links with RPV by a surge line. In-core instrumentations are introduced from the top head of RPV, and there is no penetration on the bottom head of RPV. Reactor coolant pumps are canned pumps. Progress of ACP100 No. Item Status Plan 1 Top general design Finished Oct Conceptual design Finished May Optimized conceptual design Finished Nov Preliminary standard design Finished Dec Pre-PSAR Submitted Jun Key tests Will be finished Dec PSAR Will be approved Dec Project application condition Will be satisfied Dec 2014

10 Progress of ACP100 Key tests No. Name Period 1 Control rod drive line cold and hot testing Passive emergency core cooling system integration testing CMT and passive residual heat removal system testing Fuel assembly critical heat flux testing Rector internals vibration testing Control rod drive line anti seismic testing Passive emergency core cooling system Thermal hydraulic testing hall Progress of ACP100 Licensing A contract of ACP100 combined research with NSC in 2011, and developed the following works: the concept design was approved; witness passive integration test research, and the test program was approved; conduct integral system tests; evaluate design improvements. Standard design safety analysis research with NSC in year Several specific research programmers and standard design safety analysis combined research with NSC in year The design of ACP100 is estimated be approved in the end of Progress of ACP100 Demonstration project The demonstration ACP100 nuclear power plant, with two 310Mwth reactors, will be located in Putian, Fujian Province in the east coast area of China. Fuzhou Putian Taibei ACP100 Demonstration Site Xiamen Conclusions Conclusions ACP100 is a multipurpose SMR, which could be used to supply electricity, heating, water, or their combinations; ACP100 utilize much existing and proven techniques of PWR, to lower the potential risks, to shorten the period of R&D, and to satisfy the application condition soon; ACP100 is much safer than traditional PWR, for adopting integrative layout reactor and passive concepts, and establishing favorable prevention and mitigation methods for severe accidents; Serilization of CNNC s ACP SMR has been scheduled; Development of SMR must balance safety and economy.

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12 Japan s SMR (Small Modular Reactor) Designs Kazuaki Matsui The Institute of Applied Energy, Tokyo, Japan May 8, 2014 Infrastructure Development Working Group Romania, IFNEC Economics of Small Nuclear Reactors by OECD/NEA Studies (1991) Small and Medium Reactors Volume I. Status and Prospects Volume II. Technical Supplement (2011) Current Status, Technical Feasibility and Economics Of Small Nuclear Reactors Brief characterization of SMR available for commercial deployment Characterization of advanced SMR designs Small and modular reactors ( mini reactors) and their attributes Factors affecting the competitiveness of the SMR Assessment of the deployment potential of the various proposed SMR designs Safety designs of advanced SMR Licensing issues (2013) Economics and Market of Small Reactors According to the presentation of Alexey Lokhov, OECD/NEA-NDD, 2013 USS Seawolf (SSN-575) The second nuclear submarine, and the only U.S. submarine built with a sodium cooled nuclear reactor. (SSN-575)_underway.JPG Nautilus and Seawolf USS NAUTILUS (SSN-571) The world's first nuclear-powered submarine which sailed beneath the Arctic icepack to the North Pole and broadcast the famous message "Nautilus 90 North." What is different in SMR compared with large reactors? Economy of scale vs. Economy of serial production The absolute cost of one reactor is smaller than for large reactors i.e. expected to be easier to finance Modular construction -> Tasks that used to be performed in sequence are done in parallel with factory-built modules Already implemented in some large reactors (e.g. ABWR, AP1000) But in case of SMR the module could be the entire reactor system Redundancy of production unit: Better flexibility (outages) Potential co-generation (water desalination, heat production) The power output of SMRs suits well existing heat and water distribution network Multiple modules -> redundancy -> guarantee of continued supply Decommissioning: Potentially smaller costs if modules are replaceable and factory disassembled/decommissioned According to the presentation of Alexey Lokhov, OECD/NEA-NDD, 2013 Possible motivation or driving forces of SMR 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 according to the presentation of Dr. Subki of, 2013 SMRs target two general classes of applications Traditional deployment and direct competition for electricity production with large NPP and other sources of power, and heat or steam supply with co-generation. Relatively small upfront capital investment for one unit of a SMR provides more flexibility in staging capacity increases, resulting in smaller financial risks. Niche applications in remote or isolated areas where large generating capacities are not needed, the electrical grids are poorly developed or absent, and where the non-electrical products (heat or desalinated water) are as important as the electricity. Modified the presentation of Alexey Lokhov, OECD/NEA-NDD, 2013

13 LCOE estimates for SMRs and alternative sources, at 5% real discount rate) According to the presentation of Alexey Lokhov, OECD/NEA-NDD, 2013 Development of small nuclear reactors (SMRs) Example of niche application in remote areas in Russia Modified the presentation of Alexey Lokhov, OECD/NEA-NDD, 2013 two modified KLT-40 (70 MWe) in 2016 Illegal occupation Japan s leading edge technologies in HTGR Reactor IHX HTTR (30MW, 950 o C) HTGR Test Reactor of JAEA at Oarai Japan Ceramic cladding of fuel UO mm Isotropic Graphite Heat-resistant Superalloy Quartet coating technology for cladding to have heat resistance Confinement of radioactive materials for about three times longer than of LWR Temperatures up to 1600 o C Hot-pressurizing technology for graphite to have isotropy High strength, thermal conductivity, and radioactive-resistance Temperatures up to 2400 o C Fortifying technology for metal to have heat resistance High-temp. structural technology for components Helium-handling technology for coolant to reduce leakage (Chemical, mechanical and nuclear-physical stability) Utilization of heat at high temperature of 950 o C 11 CCRCompact Containment Boiling Water Reactor Economical and Safety SMR MWe Economic competitiveness Simplified direct cycle & natural circulation Passive safety systems High pressure resistible Compact PCV design pressure : 4MPa Short construction period : 24months Comprehensive safety Large reactor coolant inventory Bottom-located core Passive Reactor cooling Simplified RPV bottom with no pipings or nozzles This material may contain proprietary subject to JAPC and TOSHIBA. Disclosing, copying, distributing or alteration on the contents of this information without written permission is strictly prohibited. Compact PCV Top entry CRD Cylindrical dryer Natural circulation Bottom located Core IC: Isolation Condenser CCR-400 (423MWe) Features of SMR designs High Temperature Gas Cooled Reactor Inherent Robust Safety Solid confinement of fuel and radioactivity Strong resistance to loss of coolant flow, SBO Possible elimination of core melt accident Utilization of high temperature to industrial application; hydrogen, etc. Possible utilization of Thorium LWR Based on proven LWR technologies Common fuel and fuel cladding Simplification by application of passive safety system Possible utilization of large water pool for long term cooling Fast Reactor Long life core without refueling Possible application for proliferation resistant system with closed fuel cycle (IFR) Possible elimination of core destructive accident Possible utilization of natural convection cooling Integrate the primary system into the reactor Vessel Safety: LOCA avoidance Economic: Small and simple The volume of containment is 1/10 of the this classes PWR Electric output Coolant Fuel type Modular unit [Note] IMRIntegrated Modular Reactor 350MWe light water PWR fuel assembly Power uprate by multiple modules The conceptual design was performed by MHI and JAPC. Approx.17m Control rod drive mechanism Reactor vessel Steam generator Core internal structure Riser Steel containment vessel Main steam pipe RV decompression valve Feed water pipe Core JAPC: The Japan Atomic Power Company (Electric utility) LOCA: Loss of coolant accident RV shielding wall Thermal neutron, graphite-moderated and helium gas-cooled HTGR 4S 4S (Super-Safe, Small & Simple) Features of HTGR High temperature heat of 950 o C High thermal efficiency of 50% High level inherent safety Small-sized reactor No water for cooling Typical specification Coolant temperature : 950 o C Thermal Output : Max. 600MW Heat utilization ratio : 70-80% with waste heat recovery Reactor Waste heat 200 o C Multi-purpose use as Decentralized energy plant Gen-IV reactor Hydrogen production Process heat Electricity generation Gas turbine District heating Seawater desalination Agriculture, Aquatic product industry 950 o C HTGR 300 o C LWR 10 Distributed Power Supply Sodium-Cooled Fast Reactor (10MWe50MWe) No Refueling for 30 Years Metallic Fuel & Long Cylindrical core with small diameter Passive Safety Negative reactivity feedback of metallic core & Decay Heat Removal System Utilizing Natural Air Draught Law Maintenance Requirement by Passive Components and Minimal Moving Parts by EMP High Security & Safeguards Reactor building is below grade

14 Development of small nuclear reactors (SMRs) SMRs, including multi-module plants, generally have higher generation costs than NPP with large reactors. The generation costs for SMR might decrease in case of large scale serial production which is very important for proving competitiveness of SMR Large initial order is needed to launch the process. Who can be the first customer? How many SMR designs will be really deployed? Need to fortify specific features of each concept and designs for segregation and competition In summary, SMR could be competitive with many non-nuclear technologies for generating electricity in the cases when NPP with large reactors are, for whatever reason, unable to compete The challenges facing SMRs are: Licensing, siting, multiple units/modules on the same site, the number of reactors required to meet energy needs (and to be competitive), and the general public acceptability of new nuclear development. Modified the presentation of Alexey Lokhov, OECD/NEA-NDD, 2013

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