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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
Safety, constructability,and operational
performance of the ABWRand ESBWR designs
Douglas McDonald
Vice President, Nuclear Power Plant
Sales Middle East and Africa
IAEA Technical Meeting on TechnologyAssessment for Embarking Countries
June 24-28, 2013
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
Wilmington, NCUSA
Nuclear Power Plants: ABWR,ESBWR and PRISM
Nuclear Services
Nuclear Fuel Fabrication.BWR and CANDU
CANDU ServicesFuel Engineering and Support
Services
Peterborough, ONCanada
Wilmington, NCYokosuka, Japan
UraniumEnrichment ThirdGenerationTechnology
Wilmington, NCUSA
Tokyo,Japan
GE Hitachi Nuclear Alliance
1
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
Vallecitos USA
Dresden 1 USA
Laguna Verde - Mexico
Tarapur 1&2 India
Dodewaard - Netherlands KKM - Switzerland
Garigliano - Italy
Santa Mara de Garoa - SpainLungmen - Taiwan
K6/K7 - Japan
KRB - Germany
BWRs around the world
84 operating BWRs
2
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
ABWR PRISM
GE Hitachis new reactor portfolio
ESBWR
Operational Gen IIItechnology
Lowest core damagefrequency of anyGeneration III reactor
Extensive operationalexperience since 1996
Licensed in US, Taiwan,and Japan
Evolutionary Gen III+technology
Lowest core damage frequencyof any Generation III+ reactor
Passive cooling for >7 days
without AC power or operatoraction
Lowest projected operations,maintenance, and staffing costs1
25% fewer pumps, valves, andmotors than active safetynuclear plants
Revolutionary technology
with a rich, 40-year heritage
Passive air-cooling with nooperator or mechanical actionsneeded
The answer to the used fueldilemma - can reduce nuclearwaste to ~300-year radiotoxicity2
while providing new electricitygeneration
3
1 Claims based on the U.S. DOE commissioned Study of Construction Technologies and Schedules,
O&M Staffing and Cost, and Decommissioning Costs and Funding Requirements for Advanced ReactorDesigns and an ESBWR staffing study performed by a leading independent firm2 To reach the same level of radiotoxicity as natural uranium
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
PWRs and BWRs the basics
Typical Pressurized Water Reactor Typical Boiling Water Reactor
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
Operation of a BWR
Saturated water/steammixture cooling fuel
Direct cycle (No externalsteam generators)
Water moderator modifiedby steam voids (bubbles)
Saturated Steam
Saturated Water
Subcooled Water
To Turbine
FeedWater
Core
Rx InternalPumps(ABWR)
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
The Boiling Water Reactor
99.9% Steam550
F / 288C
420F / 216F
100% Water
BWR Fuel Assembly
- 90 fuel rods encasedin a channel
- 2 water rods- part-length rods- burnable absorbers
Reactor Pressure Vessel
SteamDryer
SteamSeparator
Control Rod Drives
Control Rod Blades
ReactorInternal Pumps (ABWR)
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
0
Source: IAEA PRIS Database and 3/2013 EPRI Fuel Reliability Update
A benchmark for operational performance
BWR PWR
100%
90%
80%
89.83%90.96%
1% BWRadvantageprovides 8
additionalmonths ofrevenue over60-yearlifetime
Data represents top quartile for 2002-2012
Zero BWR fuel failures inNorth America
Capacity factors Average U.S. Cycle Length Trends
BWRs 20 months
PWRs 16.7 months
Fuel performanceAverage Outage length
2002-2012 N. American outages includinginspection, maintenance or repair with refueling
35.5days
45 days
BWR
PWR
10 fewer days inBWR outagesin North America
BWR
PWR
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
Safety and simplicity
III+ III+
U.S. PWRs2 E-5 (avg.)
U.S. BWRs8 E-6 (avg.)
APR14002 E-6
APWR1.2 E-6
EPR2.8 E-7
AP10002.4 E-7
ABWR1.6 E-7
ESBWR1.7 E-8
PRAofCore
DamageFrequ
ency
References: Plant licensing DCDs and publically available information
Note: PRA of CDF is represented in at-power internal events (per year)Note: NSSS diagrams are for visualization purposes only
Generation IIIGeneration II
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
Responses needed to maintain core cooling
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EPR and
GEN II WaterOperatorAction ElectricPower
72 HRS.
>7 days
ABWR
AP1000
ESBWR
~36 HRS.*
*ABWR DCD credits water addition at 8 HRS.References: AP1000: US DCD rev. 18 Section 8.5.2.1, EPR: US DCD Rev. 1 Section 8.4
Responses to extended loss of all AC power
Gen III+ passive plants allow fora much longer coping time
Decay heat level impacts urgency
DECAY HEAT
30 MIN.
24 HRS.30 MIN. 2 HRS.
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
Advanced Boiling Water Reactor
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
ABWR Design Objectives
Improved operability
Improved capacity factor12-24 month fuel cycle
~95% on a 10 year rolling average
Improved safety and reliabilityNo core uncovery during design basis
accidents
Reduced occupational exposure
Reduced costsPredictable Construction Time and Costs
Operations and Maintenance (O&M)
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
Emergency Core Cooling System
13
HPCF
RCICADSLPF
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
Key ABWR differentiators for extreme events
Separate and passive
containment venting toprevent hydrogenexplosion
Reactor depressurizationcapability for >7 days due tobattery segregation andpneumatic controls
Seismic AC independent water
injection into core
Containmentheat removal
Core cooling
shutdown
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
ABWR Station Blackout prevention and
mitigation3 x 100% nominal safety
divisions
Emergency Diesel Generators 3 located in Reactor Building
Each has a 7-day fuel tank that isburied in a concrete vault outsidethe Reactor Building
Combustion Turbine Generator
Air-cooled Service Water notneeded
Safety-related batteries arelocated in the ControlBuilding - just below the
Main Control RoomAC Independent Water
Addition (ACIWA) System Hard-piped connections to reactor
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
In Operation
Under Construction
4 Units
4 Units
Hamaoka-5 ABWR
Kashiwazaki-Kariwa 6/7 ABWR
: BWR Power Plant Site
Japan
Taiwan
Under ConstructionCOD TBD
Ohma ABWR
Shimane-3 ABWRShika-2 ABWR
Japan
Higashidori-1
Kaminoseki-1
COD 1996/1997
COD 2006
COD 2005
Lungmen-1/2 ABWR
Under ConstructionCOD 2014 (estimated)
Under ConstructionCOD TBD
Recent experience and project status
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
Construction lessons learned:
Efficient, repeatable execution model
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
ABWR modularization proven in JapanRoof Truss Steels
RCCV Top Slab
RCCV liner
Central Mat
Base Mat HCU Room Offgas Equipment Lower Condenser Block
T-G Pedestal Piping Unit
Upper Condenser
Condensate Demin. Piping
Condensate DemineralizerUpper Drywell Module
RPV Pedestal
MSIV/CV RWCU Reheat Exchanger
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
Detailed engineering before on-site work
Walk-through simulation
Full 3D CAD design
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
ModularizationProven experience in operating Gen III plants
Central Mat RCCV RebarsTop Slab
RCCV liner Roof Truss Steel
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
Building Commissioning
RI : Rock Inspection BC:Start of Basemat Construction FL : Fuel Loading CO: Commercial Operation
ABWR#1CO:1996/11
Kashiwazaki-Kariwa-6
ABWR#2CO:1997/7
Kashiwazaki-Kariwa-7
ABWR#3CO:2005/1Hamaoka-5)
ABWR#4CO:2006/3
Shika-2)
BC FL
39.5M 8.8M3.5M 48.3M
43.5M1M 10.5M 54.0M
44.5M 10.5M2.5M 55.0M
RI
38M2M 49.2M11.2M
COD
BC CO
Predictability of Schedule
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
North Anna 3 ESBWR
Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved 22
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
Economic Simplified Boiling Water Reactor
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
Parameter
Core Thermal Power Output Plant Net Electrical Output(1)
Reactor Operating Pressure Feedwater Temperature(2)
RPV Diameter Height
Reactor Recirculation Fuel
Control blades
4500 MWt1520 MWe7.17 MPa (1040 psia)216C (420F)
7.1 meters (23.3 feet)27.6 meters (90.5 feet)Natural Circulation1132 fuel bundlesShortened length of 3m269 Fine Motion ControlRod Drives (FMCRDs)
(1) Typical (site dependent)
(2) Nominal Rated Operation
ESBWR: Economy of Scaleand Simpler Design
Key plant / reactor characteristics
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
ABWR to ESBWR evolution: Nuclear Island
1
1
1
Fuel and Aux Pool Cooling equivalent designs2
Reactor Water Cleanup System equivalent designs
2 2
3
3
3 Suppression Pool Cooling & Cleanup System equivalent capability
7 High Pressure Core Flooder replaced by HP CRD makeup
4 Residual Heat Removal System equivalent for shutdown cooling
64
4
7
5
Standby Liquid Control System simplified design
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8 Reactor Core Isolation Cooling replaced by Isolation Condenser
8
8
6 Hydraulic Control Unit equivalent design
7
6
9 Residual Heat Removal Containment Spray replaced by PCCS
9
9
Safety Relief Valves Diversified by Depressurization Valves
Systems are Equivalent or Simplified
10
ABWR ESBWR
10
25
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
ESBWR modularization based on ABWRRoof Truss Steels
RCCV Top Slab
RCCV liner
Central Mat
Base Mat HCU Room Offgas Equipment Lower Condenser Block
T-G Pedestal Piping Unit
Upper Condenser
Condensate Demin. Piping
Condensate DemineralizerUpper Drywell Module
RPV Pedestal
MSIV RWCU Reheat Exchanger
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
Passive safety/natural circulation Increased volume of water in the vessel
Increased driving head
Chimney, taller vessel
Reduced flow restrictions Open downcomer
Shorter core
Significant reduction in components Pumps, motors, controls, Heat Exchangers
Power Changes with FeedwaterTemperature and Control Rod DrivesMinimal impact on maintenance
Natural Circulation
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
ESBWR Passive Safety Systems
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
ESBWR LOCA response
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
Isolation Condenser System
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passivedecay heat
removal
Fully passive only requires gravity to
function and starts automatically(fails in-service if DC power is lost)
4 separate systems in reinforced concretevaults
Limits reactor pressure (no SRV lifts) andtemperature and conserves waterinventory following containment isolation
Steam (heat) rises from reactor to thecondenser pool, condenses, then gravitypulls the cool water down into the reactor(closed-loop)
Removes heat fromcontainment
Core cooling
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
Simple refill actions even in the worst conditions
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
Simple refill actions even in the worst conditions
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
Simple refill actions even in the worst conditions
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
PCCS heat
exchanger test
IC/PCCPOOLS
DW2
GDCSPO
WW2
WETWELLWW1
RPV
DRYWELLDW1
GIST facility
IsolationCondenser Testing
BDLBREAK
LOWERDRYWELL
HORIZONTALVENT (1 OF 2)
GDCSINJECTION LINE(1OF 4)
UPPERDRYWELL
VACUUMBREAKER(GDLBTESTSONLY)
MSLBREAK
REACTORPRESSURE
VESSEL
DEPRESSURIZATION LINE(1OF 2)
WETWELL
Panda Full HeightContainment Test facility
WW to DWVacuum Breaker
ESBWR Proven innovationdrywell to wetwell
vacuum breaker test
Depressurization Valve
test
BiMACtesting
fuel modified
GNF2
natural circulationproven at Dodewaard
FMCRDsfrom ABWR
Copyright 2013 GE Hitachi
Nuclear Energy International, LLC- All rights reserved 35
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved 36
Operations
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
ABWR and ESBWR state-of-the-art operations
Fully Digital ControlSystem
Fewer components, No drift,
less power and heat Fault tolerance control Four division safety
redundancy Automated operation
Surveillance testing greatlyreduced
Improved Man-MachineInterface
Large mimic displays
Prioritized alarms Flat panel controls
minimize hard switches Human factored displays
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ABWR and ESBWR offer substantial
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved
ABWR and ESBWR offer substantial
improvements in O&M
Key component redundancy Maintenance flexibilityOperational transients
Simplifications in design Safety, operations, and reliability
O&M costs
Improvements in plant maintenance Easier operations, greater reliability
Maintenance cost and dose
Simpler to operate Safety and reliability
Operator actions and transients
Lower radiation exposure Outage efficiency and FME reduction
Occupational dose and rad waste costs
Passive safety (ESBWR) Safety and plant simplificationMaintenance costs and dose
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reservedSource: An ESBWR staffing study performed by a leading independent firm
Best in-class O&M
ESBWR requiressignificantly fewerplant personnel thanany other GenerationIII/III+ design.
A direct reflection of theESBWRs simpler design
Allows for a higherpercentage of localworkforce
Fewer ex-pats results indirect cost savings
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Copyright 2013 GE Hitachi Nuclear Energy - Americas, LLC - All rights reserved 40
ABWR
ESBWR
Safe.
Simple.
Smart.
1 Based on the industry standard measure of reactor safety - core damage frequency2 Claims based on the U.S. DOE commissioned Study of Construction Technologies and Schedules, O&MStaffing and Cost, and Decommissioning Costs and Funding Requirements for Advanced ReactorDesigns and an ESBWR staffing study performed by a leading independent firm