Nl PEii tEl t i P U i it N uc l ear P ower E ng i neer i ng a t El ec t r i c P ower U n i vers it y LWR Plant System - 1 LWR Plant System 1 - BWR Development, ABWR Systems - July 27 Third Period July 27 , Third Period T k hi SUMIKAWA T a k as hi SUMIKAWA Kazuhiro YOSHIKAWA Hitachi - GE Nuclear Energy, Ltd. Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved. Hitachi GE Nuclear Energy, Ltd. 1 Nl PEii tEl t i P U i it N uc l ear P ower E ng i neer i ng a t El ec t r i c P ower U n i vers it y Quiz 1 Q: What does “BWR” stand for? Boiling W Ans.: B : W W ater Reactor W : R: Reactor Reactor R : Wh i h i f b ili Wh at i s t h e mer i t o f b o ili ng water “in” the Reactor? Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved. 2 Nl PEii tEl t i P U i it N uc l ear P ower E ng i neer i ng a t El ec t r i c P ower U n i vers it y 1(1).Steam is generated in BWR Reactor BWR PWR Steam PCV PCV Turbine Generator Fuel Turbine Generator Control Rod Pressurizer a lizer c irculation m p Generators Steam Steam 1 loop 2 loops Suppression Pool Condenser Water Control Rod (CR) Condenser Turbine Generator Water Fuel Deminer a Re c Pu m Feed water Pump Circ. Water Pump Feed water Pump Circ. Water Pump Demineralizer Reactor Reactor PCV: Primary Containment Vessel Merits of boiling water in the Reactor are …  Compact PCV; No Steam Generators  Simple Configuration; Direct cycle (only 1 loop) Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved. 3  Simple Configuration; Direct cycle (only 1 loop)  Easy Control; Void Effect can be used for Power Control Nl PEii tEl t i P U i it N uc l ear P ower E ng i neer i ng a t El ec t r i c P ower U n i vers it y 1(2).Features of BWR Allowance of Boiling in Reactor Pressure Vessel Small size Reactor Pressure Vessel ･No Steam Generators in PCV ･Suppression Pool  Si l fi ti  Si mp l e con fi gura ti on ･Direct cycle (only 1 loop) E i  E asy operat i on ･Void Effect is used for the Power Control Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved. 4 Nl PEii tEl t i P U i it N uc l ear P ower E ng i neer i ng a t El ec t r i c P ower U n i vers it y 2(1). Evolution of BWR We want BWR plant to be … • Extremely safe • Competitive in costs How should we improve BWR to achieve those? How should we improve BWR to achieve those? 1. Simpler configuration  Reduce trouble risk 2. Enhancing output power  Reduce trouble risk ⇒Extremely safe  Reduce material power ⇒ Competitive in costs Reduce material Shorten construction period ⇒Com p etitive in costs Competitive in costs Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved. 5 p Nl PEii tEl t i P U i it N uc l ear P ower E ng i neer i ng a t El ec t r i c P ower U n i vers it y 2(2). History of BWR (Sweden) (West Germany) Oskarshamn‐1,2 Forsmark‐1,2 Forsmark‐3 Oskarshamn‐3 Europe (West  Germany) (Wurgassen) Philippsburg‐1 Isar‐1 Gundremmingen‐B,C Krunmmel‐1 d Dresden‐1Oyster Creek Dresden ‐2 Vermont Yankee LaSalle‐2GrandGulf‐2 Unite d  States Japan Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved. 6 Nl PEii tEl t i P U i it N uc l ear P ower E ng i neer i ng a t El ec t r i c P ower U n i vers it y 2(3).BWR Reactor is being simpler. BWR 3/4/5 BWR ‐ 2 SaferandMorecost‐eff ective ABWR BWR ‐ 1 BWR ‐ 3/4/5 BWR ‐ 2  Steam Drum ABWR ABWR：Advanced Boiling WaterReactor BWR ‐ 1 ??? JetPump 6Recirculation InternalPump SteamGenerator loops MultipleCircles DeletedSteamGeneratorsand 2Recirculation loops Reductionof DeletedRecirculation Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved. 7 （Boiler&Steam Generator） aSteamDrum Recirculationloopsusing JetPumps loopsusingInternal Pumps Nl PEii tEl t i P U i it N uc l ear P ower E ng i neer i ng a t El ec t r i c P ower U n i vers it y 2(4).BWR is enhancing its output power while keeping its containment size. Morecost‐effective MARK‐Ⅰ (BWR‐3/4) RCCV：ReinforcedConcrete ContainmentVessel MARK‐Ⅱ (BWR‐5) RCCV (ABWR) PCV type ?? 70m 58m 61m Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved. 52m 8 57m 55m Output power 1100MWe 1300MWe(ABWR) 780MWe Nl PEii tEl t i P U i it N uc l ear P ower E ng i neer i ng a t El ec t r i c P ower U n i vers it y 2(5).BWR is enhancing its output power ) ABWR U T(MWe ) 1000 BWR-5 ABWR OUTP U BWR-3 BWR-4 BWR-2 Now let ’ s see the system of ABWR the 2000 YEAR 1960 1970 1980 1990 2010 Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved. 9 Now let s see the system of ABWR , the latest type of BWR in commerce. Nl PEii tEl t i P U i it N uc l ear P ower E ng i neer i ng a t El ec t r i c P ower U n i vers it y Overview of ABWR Systems ABWR Power Generation St Safety Systems Auxiliary Systems S ys t ems Nt id Nt id Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved. 10 N ex t per i o d N ex t per i o d [...]... 1 2 3 4 5 6 7 8 1 2 3 4 21m 5 6 7 8 9 11 10 12 13 14 15 18 16 19 17 20 21 22 24 23 Vent and Head Spray Steam Dryer Steam Outlet Flow Restrictor Steam Separators RPV Stabilizer Feedwater Sparger Shutdown Cooling Outlet Low Pressure Flooder (LPFL) and Shutdown Cooling Flooder g 9 High Pressure Core Flooder (HPCF) Sparger 10 HPCF Coupling 11 Top Guide 12 Fuel Assemblies 13 Core Shroud 14 Control Rod 15 ... Systems of ABWR 3 -1 How is steam generated in ABWR? (RPV) 3-2 How is electricity generated with steam in ABWR? (MS, Turbine, MSH, Condenser, FDW) 3-3 How is the output power controlled in ABWR? (CRD, RRS) Copyright © 2 011 Hitachi-GE Nuclear Energy, Ltd All Rights Reserved 11 Nuclear P N l Power Engineering at Electric P E i i t El t i Power U i University it 3.Power Generation Systems of ABWR 3 -1 How is steam... Core Plate 16 In-Core Instrument Guide 17 Control Rod Guide Tubes 18 Core Differential Pressure Line 19 Reactor Internal Pumps (RIP) 20 Thermal Insulation 21 Control Rod Drive Housings 22 Fine Motion Control Rod Drives 23 RIP Motor Casing 24 Local Power Range Monitor Steam Dryer y Steam Separator Core Shroud 出典：社団法人 火力原子力発電技術協会 「火原協会講座２８ 原子力発電 - 体計画と付属設 - （改訂版）」 Copyright © 2 011 Hitachi-GE Nuclear... Reserved Copyright 2 011 Hitachi-GE 13 Nuclear P N l Power Engineering at Electric P E i i t El t i Power U i University it 3 -1 How is steam generated in ABWR? Two functions of RPV are … Main Steam Normal Water Level Feed Water Core (Nuclear Fuel) Steam Generator Reactor Extracts heat from the core RPV (Reactor Pressure ©Vessel)Nuclear Energy, Ltd All Rights Reserved Copyright 2 011 Hitachi-GE 14 Nuclear P N... Copyright © 2 011 Hitachi-GE Nuclear Energy, Ltd All Rights Reserved 18 Nuclear P N l Power Engineering at Electric P E i i t El t i Power U i University it 3 -1 How is steam generated in ABWR? Shroud separates Downcomer flow and Core flow Steam Dryer Steam Separator 8m S oud Shroud Core (Fuel) Shroud Downcomer flow Core flow Copyright © 2 011 Hitachi-GE Nuclear Energy, Ltd All Rights Reserved 19 Nuclear... 3 -1 How is steam generated in ABWR? Steam Dryer removes moisture from steam Steam Dryer Steam Separator Dry Steam Wet Steam Drain Core (Fuel) 2m Steam Flow S Drain Steam Dryer Steam Dryer Copyright © 2 011 Hitachi-GE Nuclear Energy, Ltd All Rights Reserved 21 Nuclear P N l Power Engineering at Electric P E i i t El t i Power U i University it 3 -1 How is steam generated in ABWR? Reactor Internals 7.1m... University it 3 -1 How is steam generated in ABWR? Water is boiled in the Core Core Normal Water Level Steam and Hot water Boiling Let’s check out the detail of the Core! Core (Nuclear Fuel) Cool water RPV (Reactor Pressure ©Vessel)Nuclear Energy, Ltd All Rights Reserved Copyright 2 011 Hitachi-GE 15 Nuclear P N l Power Engineering at Electric P E i i t El t i Power U i University it 3 -1 How is steam... Core Cross-section view of Fuel Bundles and Control Rod Core Cross-section view of the Core □ Fuel Bundle × 872 + Control Rod × 205 Neutron M i : ○ P N Monitor Power R Range ■Startup R S Range △ Neutron Source RPV Fuel Bundle Control Rod Copyright © 2 011 Hitachi-GE Nuclear Energy, Ltd All Rights Reserved 16 Nuclear P N l Power Engineering at Electric P E i i t El t i Power U i University it 3 -1 How is... ABWR 3 -1 How is steam generated in ABWR? (RPV) 3-2 How is electricity generated with steam in ABWR? (MS, Turbine, MSH, Condenser, FDW) 3-3 How is the output power controlled in ABWR? (CRD, RRS) Copyright © 2 011 Hitachi-GE Nuclear Energy, Ltd All Rights Reserved 12 Nuclear P N l Power Engineering at Electric P E i i t El t i Power U i University it 3 -1 How is steam generated in ABWR? Two functions of... Generation Systems of ABWR 3 -1 How is steam generated in ABWR? (RPV) 3-2 How is electricity generated with steam in ABWR? (MS, Turbine, MSH, Condenser, FDW) 3-3 How is the output power controlled in ABWR? (CRD, RRS) Copyright © 2 011 Hitachi-GE Nuclear Energy, Ltd All Rights Reserved 23 Nuclear P N l Power Engineering at Electric P E i i t El t i Power U i University it 3-2 How is electricity generated . output power ) ABWR U T(MWe ) 10 00 BWR-5 ABWR OUTP U BWR-3 BWR-4 BWR-2 Now let ’ s see the system of ABWR the 2000 YEAR 19 60 19 70 19 80 19 90 2 010 Copyright © 2 011 Hitachi-GE Nuclear Energy, Ltd. All. size. Morecost‐effective MARK‐Ⅰ (BWR‐3/4) RCCV：ReinforcedConcrete ContainmentVessel MARK‐Ⅱ (BWR‐5) RCCV (ABWR) PCV type ?? 70m 58m 61m Copyright © 2 011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved. 52m 8 57m 55m Output power 11 00MWe 13 00MWe(ABWR) 780MWe Nl PEii tEl t i P U i. BWR (Sweden) (West Germany) Oskarshamn 1, 2 Forsmark 1, 2 Forsmark‐3 Oskarshamn‐3 Europe (West  Germany) (Wurgassen) Philippsburg 1 Isar 1 Gundremmingen‐B,C Krunmmel 1 d Dresden‐1Oyster Creek Dresden ‐2 Vermont Yankee LaSalle‐2GrandGulf‐2 Unite d  States Japan Copyright