Module 19 Small Modular Nuclear Power Plants (using slides supplied by H.Subki,IAEA)

Transcription

1 Module 19 Small Modular Nuclear Power Plants (using slides supplied by H.Subki,IAEA) Status Prof.Dr. Böck Technical University Vienna Atominstitut Stadionallee 2, 1020 Vienna, Austria ph:

2 Definitions of SMR IAEA definition since early 1990s: < 300 MWe as small MWe as medium (to cover AP600, SBWR & CANDU- 6 then) >700 MWe is large Updated definition of SMR : < 300 MWe mostly under development M for Modular The modularity aims for factory fabrication, rail/road transportable, and multi-module deployment Integral-PWRs There are some 45 SMR designs in 13 countries 2

3 Small and Medium Power Reactors

4 Miniature Nuclear Power Plants Until now NPP s increased constantly up to 1600 MWe to reduce cost per kw installed Such large NPP s are not suitable for small electrical grids in Asia, Africa and South America Large components have to be manufactured and assembled at the site Small units can be produced in modules and transported to the site and number of units can increased as required Possibility to place units underground for better protection against external events

5 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 5

6 6 Business case for SMRs? Lower capital cost offers better-affordability for newcomers Reduced financial risk for entry into deployment Better fit to electrical grid infrastructure in embarking countries Potential increased safety margin (passive safety designs) Shop fabricated: easier to ship components, domestic supply chain Potentially adaptable to non-electricity applications (e.g. desalination) Scalable small incremental capacity addition Most aging fossil power plants are < 500MWe Reduced land and water usage (increased site options) Opportunity for technology innovation Incorporate Gen-III+ and Gen-IV technology Incorporate Lessons-Learned from the Fukushima accident

7 Potential for Improving Thermal Efficiency of Nuclear Stations Improves overall efficiency Recover some Waste Heat Off Peak Power Utilization 34% 72% Losses Losses Potential heat recovery Net Electricity Net Electricity 7

8 Benefits of Non Electric Applications Improvement of efficiency Harnessing waste heat Improvement of economics (cogeneration + including sharing of infrastructures) Benefits of coupling (e.g., provide necessary industrial quality water to the NPP, make use of the off-peak power) Process heat for paper mills, petroleum, chemical and plastic industries 8

9 Drivers for Cogeneration Meet increased demand for other energy-intensive non-electric products at lower costs. Accommodate NPPs within moderately sized electrical grids. Secure the energy supply for industrial complexes Utilize additional capacity resulting from changing power consumption from seasonal variations. Reduce environmental impact (compared to two stand-alone plants) 9

10 Status of Countries on SMR Initiatives Which countries deploy SMRs? Technology developer countries (NPPs in operation) Countries with NPPs Newcomer countries Asia Europe Africa Latin America 10

11 What s New in Global SMR Development? mpower NuScale W-SMR Hi-SMUR SMART KLT-40s SVBR-100 BREST-300 SHELF Flexblue CAREM-25 B&W received US-DOE funding for mpower design. The total funding is 452M$/5 years for 2 out of 4 competing ipwr based- SMRs. Some have utilities to deploy in specific sites. US-DOE also announced the second round of SMR funding in March 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 was started in September 2011; construction started in S PFBR PHWRs: 220, 540 & 700, 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. 4 units of PHWR-700 under construction, 4 more units to follow. AHWR300-LEU at final detailed design stage and ready for 11 construction.

12 Reactors Under Construction in SMR category Country Argentin a China India Russian Federatio n Reactor Model CAREM-25 (a prototype) HTR-PM (GCR) PFBR (a prototype) KLT-40S (shipborne) Output (MWe) Designer Numbe r of units Site, Plant ID, and unit # Commercial Start 27 CNEA 1 CAREM ~ Tsinghua Univ./Harbi n 1 Shidaowan unit ~ IGCAR 1 Kalpakkam OKBM Afrikantov 2 Akademik Lomonosov

13 SMRs for Near-term Deployment Name Design Organization Country of Origin Electrical Capacity, MWe Design Status 1 SVBR-100 JSC AKME Engineering Russian Federation 100 Detailed design for prototype construction 2 System Integrated Modular Advanced Reactor (SMART) Korea Atomic Energy Research Institute Republic of Korea 100 Standard Design Approval Received 4 July mpower Babcock & Wilcox 4 NuScale NuScale Power Inc. 5 Westinghouse SMR Westinghouse 6 VBER-300 OKBM Afrikantov 7 Super-Safe, Small and Simple (4S) United States of America United States of America United States of America Russian Federation 180/module 45/module 225 Detailed design, to apply for certification mid 2014 Detailed design, to apply for certification - mid 2014 Detailed design, to apply for certification - mid Detailed design Toshiba Japan 10 Detailed design

14 Country Current Newcomer Countries Plan Grid Capacity in GWe Current Deployment Plan Bangladesh x 1000 MWe PWRs in Rooppur in 2018 Vietnam x 1000 MWe PWRs in Ninh Thuan #1 by x 1000 MWe PWRs in Ninh Thuan #2 by 2025 Jordan x MWe PWR in + possible interest in SMR UAE x 1400 MWe PWR in Braka by 2018 Belarus x 1200 MWe PWR in Ostrovets by 2018 Turkey x 1200 MWe PWR in Akkuyu by 2022 Malaysia x 1000 MWe LWRs, 1 st unit by 2021 Indonesia x 1000 LWRs, with potential interest of deploying Small Reactors for industrial process and non-electric applications by 2024

15 Practical Categorization of SMRs Advanced SMRs including modular reactors and integrated PWRs Innovative SMRs including non-water coolant/moderator SMRs Converted and Modified SMRs Including barge-mounted floating NPP and seabed-moored submarine-like reactors Conventional SMRs Those of 1970/80s technologies and still being deployed Innovative Application of SMRs with Non-Nuclear Including Nuclear-Renewable Hybrid System, and SMRs coupled with Non-Electric Applications (Desalination, H 2 production) 15

16 Practical Categorization of SMRs Advanced SMRs (incl. Modular and integrated-pwrs) CAREM-25 Argentina SMART Korea, Republic of VBER-300 Russia WWER-300 Russia ABV-6 Russia HTR-PM China mpower USA NuScale USA Westinghouse SMR - USA CEFR China 4S Japan PFBR-500 India 16

17 (cont d) Practical Categorization of SMRs Advanced SMRs (incl. Modular and integrated- PWRs) Each module has a dedicated turbine generator Modularity permits scaling to any size Generator Steam Turbine Condenser Water-Filled Pool Below Ground Containment NSSS J. Nylander and M. Cohen Courtesy of NuScale Power, USA. 17

18 (cont d) Practical Categorization of SMRs Innovative SMRs IMR Japan AHWR300-LEU India GT-MHR USA PRISM USA EM 2 USA PBMR South Africa 18

19 (cont d) Practical Categorization of SMRs Converted/Modified SMRs KLT-40s Russian Federation SVBR-100 Russian Federation Flexblue France 19

20 (cont d) Practical Categorization of SMRs Conventional SMRs 20

21 (cont d) Practical Categorization of SMRs Innovative Application of SMRs with Non- Max Output of 1061 MWe Nuclear to the power GRID Composite Wind Farms Variable Electricity Node Regional Biomass (80 Km radius or ~2 million hectares) t/dm/yr 1018 MWe Nuclear reactor 347 MWe (755 MWth) Offsetting SMR Electricity Reactor Heat Dynamic Energy Switching Hydrogen Electrolysis 104 GWh heat at 200 C 1169 GWh heat at 500 C t H 2 /yr Drying and Torrefaction Processes + Pyrolysis +Synfuel Production Torrified Product Pyrolyzed oil + char + offgas Source: J. Carlsson, EC - JRC 753m 3 /day bio-diesel 597m 3 /day bio-gasoline 21

22 U.S. LWR-based SMR designs: PWRs 1200 MWe PWR 180 MWe mpower 45 MWe NuScale 225 MWe W-SMR 160 MWe SMR-160 Electrical Output (MW) Vessel Diameter (m) Gen II PWR mpower NuScale W-SMR SMR Vessel Height (m) Surface Area/Volume (1/m) Surface Area/Power (relative to PWR)

23 SMR for Near-term Deployment 4S 2011 TOSHIBA CORPORATION Steam Generator Reactor Turbine/ Generator 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

24 SMART Concept of Integral PWR based SMRs CRDM pressurizer Westinghouse SMR pumps Steam generators Steam generators CRDM core + vessel pumps core + vessel 24

25 Integral Primary System Configuration Courtesy: Westinghouse Electric Company LLC, All Rights Reserved 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) 25

26 FUJI (Internat.Consortium JP, RU,USA) minifuji: power 7-10 MWe, core 1,8 x 2,1 m, 90% graphite moderator 10% liquid fuel, small breeder reactor, possibilty to use Th for breeding reaction FUJI: Molten salt reactor MWe, preproject to GEN IV MSR Inherently safe, no core melt, chemical inert, possibilty for transmutation July 2010 consortium founded, aim to construct minifuji within 5-6 years

27 mpower (Babcock&Wilcox) PWR pressure vessel and steam generator in one unit Underground containment Including fuel storage for whole life time of 60 years Power 125 MWe 3 years construction time Refuelling time 4,5 years Each module operates independently First module exspected by

28 mpower Modular Reactor (BabcockWilcox)

29 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: 530 MW(t) / 180 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 expected by 3 rd Quarter of 2014

30 NuScale ATW 2011 p 409 Small modular reactor, each module 45 MWe Each module containment 18m x 4,5 m diameter Pressure vessel length 14 m, diameter 3 m Steam generator and pressurizer inside PV Passive ECCS Refuelling cycle 2 years Construction time for 12 modules: 3 years All components workshop manufactured and transported to site

31 NuScale Modular Reactor Applications: Electricity Co-generation Process steam or heat

32 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: Design Certification application expected in 4th Quarter of 2014

33 Westinghouse SMR Small modular reactor, simple and compact Power: 800 MWth, 200 MWe Integral PWR with all primary components in pressure vessel Passive safety systems <5% enrichment 24 month refuelling No operator intervention for 7 days

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35 SMART System-integrated Modular Advanced Reactor (Korea) 330 MWth, 100 MWe, m3 desalinated water Life time: 60 years Load following capability Core height: 2 m 57 fuel assemblies with 17 x17 fuel rods using UO2 less than 5 % enriched 24 control rod 6 years in-core time 8 steam generators, 4 pumps, 1 pressurizer all inside pressure vessel More details:

36 SMART Pressure Vessel

37 2011 KAERI Republic of Korea 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: Standard Design Approval just granted on 4 July 2012

38 KLT-40S Originating from Russian icebreakers Floating PWR on island 144 m x 30 m Factory built and shipped to site Two NPP s each 35 MWe or 150 MWth Passive safety systems Fuel cycle 3-4 years 40 years life time Resistant to major external event

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40 EM2 (General Atomics) He cooled FBR 225 MWe or 500 MWth Sited underground Four modules factory built and assembled locally Pressure vessel: D: 4,6 m H: 12 m Possibility to transmute spent LWR fuel

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42 CAREM

43 CAREM Argentina Modular 100 MWt (27 MWe gross) PWR 12 integral steam generators For electricity generation or as a research reactor or for water desalination Entire primary coolant system within the reactor pressure vessel, self-pressurized and relying entirely on convection Fuel is standard 3.4% enriched PWR fuel in hexagonal fuel assemblies, with burnable poison

44 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 completed, construction started in 2012

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55 Presently 16 units 220 MWe and 2 units 540 MWe in operation

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60 Summary SMR is an attractive option to enhance energy supply security in newcomer countries with small grids and less-developed infrastructure and in advanced countries requiring power supplies in remote areas and/or specific purpose; Innovative SMR concepts have common technology development challenges: licensability, competitiveness, control room staffing for multi-modules plant, and so forth. Domestic deployment in technology-developers countries is very important to encourage newcomer countries to adopt SMR (i.e. operability/safety record, provenness) Needs to address relevant lessons-learned from the Fukushima accident into the design development and plant deployment 60

61 References -> search for Generation IV ADVANCED REACTORS Miniature Nuclear Power Plants Atomwirtschaft 2011, p.407 Small and Medium Sized Reactors Atomwirtschaft 2012, p IAEA Nuclear Technology Review Small and Medium Sized Reactor Designs

62 //ehron.jrc.ec.europa.eu OECD/NEA and EU estimates Up to 2050: for new NPPs at 1400 MWe-up to 130 engineers/year for new NPPs at 1000 Mwe up to 185 engineers/year Estimated overall manpower to 2050: to Nuclear experts to in 2050 Technicians to in 2050