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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 - 2 LWR Plant System 2 - Safety Related System- July 27 Forth Period July 27 , Forth 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 Overview of ABWR Systems ABWR Power Generation St Safety Systems Auxiliary Systems S ys t ems thi i d thi i d Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved. 2 thi s per i o d thi s per i o d 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 2 Q: Do you remember the 3 principles of Safety design? Shut down of Safety design? Ans : 1 : Shut down Cool down Ans . : 1 : 2 : Contain 3 : How does ABWR acheive it? Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved. 3 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 4.Safety Systems of ABWR 4-1 Systems to “Shut down” a reactor (CRD, SLC) 4-2 Systems to “Cool down” a reactor (ECCS) 4-3 Structures or Systems to “Contain” a reactor (PCV, FCS, R/B, SGTS, AC) 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 4-1 Systems to “Shut down” the Reactor CRD and SLC shut off the nuclear reaction CRD and SLC shut off the nuclear reaction . PCV RPV HPCF Core HPCF Boron solution CRs SLC Pumps SLC storage tank 1.ControlRod Di (CRD) 2 Standby Liquid S/P S/P D r i ve (CRD) 2 . Standby  Liquid  ControlSystem(SLC) Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved. 5 PCV: Primary Containment Vessel RPV: Reactor Pressure Vessel S/P: Suppression Pool 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 4.Safety Systems of ABWR 4-1 Systems to “Shut down” a reactor (CRD, SLC) 4-2 Systems to “Cool down” a reactor (ECCS) 4-3 Structures or Systems to “Contain” a reactor (PCV, FCS, R/B, SGTS, AC) 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 4-2 Systems to “Cool down” the Reactor Why does the core need to be “ Cooled Why does the core need to be Cooled down” even after the “Shut down”? RETRAN code Equation by Todreas Decay heat compare to the design thermal fth energy o f th e core Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved. 7 Because of the continuous Decay heat after the nuclear fission. 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 4-2 Systems to “Cool down” the Reactor ECCS consists of 3 functions ECCS consists of 3 functions . Pressure: approx.7MPa inoperatingcondition 1:HighPressure CoreInjection PCV RPV Cool water source Core To Turbine Cool water Cool water source 3:LowPressure CoreInjection 2: Depressurization f S/P S/P o f RPV Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved. 8 PCV: Primary Containment Vessel RPV: Reactor Pressure Vessel S/P: Suppression Pool 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 4-2 Systems to “Cool down” the Reactor Redundancy and Independence of ECCS Redundancy and Independence of ECCS secure the margin of safety. Redundancy ABC Redundancy 1.High pressure core injection HPCF HPCF RCIC 2.De p ressurization ADS ( 8 SRVs have the function. ) 3 functions of p of RPV ( ) 3.Low pressure core injection LPFL(RHR) LPFL(RHR) LPFL(RHR) ECCS injection Independence Emergency power source: D/G (Diesel Generator) D/G D/G Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved. HPCF: High Pressure Core Flooder RCIC: Reactor Core Isolation Cooling ADS: Automatic Depressurization System LPFL: Low Pressure Flooder RHR: Residual Heat Removal 9 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 4-2 Systems to “Cool down” the Reactor (ECCS) High Pressure Core Flooder (HPCF) High Pressure Core Flooder (HPCF) HighPressure HPCFinjectswaterintoRPVathigh pressure to keep the Reactor water level PCV RPV Cool water pressure  to  keep  the  Reactor  water  level . CST Core Cool water Reactor water level HPCF pump ( motor driven ) Hi g h p ressure Firstwater source S/P S/P () Second g p injection Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd. All Rights Reserved. Second  watersource PCV: Primary Containment Vessel RPV: Reactor Pressure Vessel CST：Condensate Storage Tank S/P: Suppression Pool 10 [...]... “Low” Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd All Rights Reserved 5-1 4 Nuclear P N l Power Engineering at Electric Power University E i i t El t i P U i it 4.Safety Systems of ABWR 4-1 Systems to “Shut down” a reactor (CRD, SLC) 4-2 Systems to “Cool down” a reactor (ECCS) 4-3 Structures or Systems to “Contain” a reactor (PCV, FCS, R/B, SGTS, AC) Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd All... 5.Auxiliary Systems of ABWR 5-1 Systems to cleanup the reactor water (CUW) 5-2 System to cool down the Spent Fuel Storage Pool (FPC) 5-3 Ultimate Heat Sink (RCW, RSW) Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd All Rights Reserved 24 Nuclear P N l Power Engineering at Electric Power University E i i t El t i P U i it 5-1 .Reactor Water Cleanup System (CUW) PCV Feed Water Line RPV Re-generate type Heat Exchanger... E i i t El t i P U i it 5.Auxiliary Systems of ABWR 5-1 Systems to cleanup the reactor water (CUW) 5-2 System to cool down the Spent Fuel Storage Pool (FPC) 5-3 Ultimate Heat Sink (RCW, RSW) Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd All Rights Reserved 26 Nuclear P N l Power Engineering at Electric Power University E i i t El t i P U i it 5-2 System to cool down the spent fuel pool Why does the... General Description」 Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd All Rights Reserved 28 Nuclear P N l Power Engineering at Electric Power University E i i t El t i P U i it 5.Auxiliary Systems of ABWR 5-1 Systems to cleanup the reactor water (CUW) 5-2 System to cool down the Spent Fuel Storage Pool (FPC) 5-3 Ultimate Heat Sink (RCW, RSW) Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd All Rights Reserved... Systems of ABWR 5 A ili S t f 5-1 Systems to cleanup the reactor water CUW 5-2 System to cool down the Spent Fuel Storage Pool 5 2S ld h S F lS P l FPC 5-3 Ultimate Heat Sink RCW, RCW RSW Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd All Rights Reserved 31 Nuclear P N l Power Engineering at Electric Power University E i i t El t i P U i it • supplement Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd All... the UHS (Ultimate Heat Sink) Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd All Rights Reserved 30 Nuclear P N l Power Engineering at Electric Power University E i i t El t i P U i it Summary (key words) 4.Safety Systems of ABWR 4-1 Systems to “Shut down” a reactor y CRD, SLC 4-2 Systems to “Cool down” a reactor ECCS, HPCF, RCIC, ADS, LPFL(RHR) 4-3 Structures or Systems to “Contain” a reactor PCV,... Treatment System Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd All Rights Reserved 20 Nuclear P N l Power Engineering at Electric Power University E i i t El t i P U i it 4-3 Constructions and systems to “Contain” a reactor Standby Gas Treatment System (SGTS) Design Philosophies • Radiological release to the environment is prevented by maintaining R/B pressure negative ( -6 3Pa) • Radioactive substance in PCV... secondary containment air to outside via filter.) FCS: Flammable gas Control System SGTS: Standby Gas Treatment System Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd All Rights Reserved 16 Nuclear P N l Power Engineering at Electric Power University E i i t El t i P U i it 4-3 Constructions and systems to “Contain” a reactor Primary Containment Vessel (PCV) Design Philosophies PCV shuts FP in the controlled... Containment Vessel RPV: Reactor Pressure Vessel RHR：Residual Heat Removal S/P RHR heat exchanger S/P: Suppression Pool Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd All Rights Reserved 5-1 8 Nuclear P N l Power Engineering at Electric Power University E i i t El t i P U i it 4-3 Constructions and systems to “Contain” a reactor Flammable Gas Control System (FCS) FCS controls the mixture of  Hydrogen and Oxygen gas in PCV, ... Filter device Number : 1 set Filter Efficiency : y ; Flow of atmosphere over 99.99% for Iodine *Capacity of ABWR Copyright © 2011 Hitachi-GE Nuclear Energy, Ltd All Rights Reserved 21 Nuclear P N l Power Engineering at Electric Power University E i i t El t i P U i it 4-3 Constructions and systems to “Contain” a reactor Atmospheric Control System (AC) Removes the radioactive substance in PCV Stack SGTS . U n i vers it y LWR Plant System - 2 LWR Plant System 2 - Safety Related System- July 27 Forth Period July 27 , Forth Period T k hi SUMIKAWA T a k as hi SUMIKAWA Kazuhiro YOSHIKAWA Hitachi - GE Nuclear. ABWR 4-1 Systems to “Shut down” a reactor (CRD, SLC) 4-2 Systems to “Cool down” a reactor (ECCS) 4-3 Structures or Systems to “Contain” a reactor (PCV, FCS, R/B, SGTS, AC) Copyright © 2011 Hitachi-GE. ABWR 4-1 Systems to “Shut down” a reactor (CRD, SLC) 4-2 Systems to “Cool down” a reactor (ECCS) 4-3 Structures or Systems to “Contain” a reactor (PCV, FCS, R/B, SGTS, AC) Copyright © 2011 Hitachi-GE