8ES-EAP-20110011-08ES-EAP-20110011

IAEA Interregional Workshop on Advanced Nuclear Reactor Technology for Near Term Deployment

Mitsubishi US-APWR and EU-APWR

Hiroshi Nojiri4th July, 2011

Mitsubishi Heavy Industries, Ltd.

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1. Evolution of the MHI’s PWR Design and

Technology

2. Main Design Features of US-APWR and

EU-APWR

3. Design Features of EU-APWR

relevant to Fukushima Accident

4. MHI Nuclear Capabilities

5. Summary

CONTENTS

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1. Evolution of the MHI’s PWR Design and Technology

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Contribution to All of the 26 Japanese PWR Plants From First PWR Power Plant Mihama Unit1 in 1970 to the 21st Century’s Latest APWRsNew Build (or Replacement) Projects Continued Constantly even in the 80-90’s “Nuclear Stagnation”in the US and EuropeDeveloped Our Own Technologies throughout Long History to Our Core Competence

24 PWRs in operationTsuruga -3/4 APWRs under

Licensing

Current Operating Fleet of MHI’ PWR’s

TOMARI P/S

TSURUGA P/S

MIHAMA P/S

IKATA P/S

OHI P/S

GENKAI P/S

Rokkasho Reprocessing

Plant

JoyoMonju

Fast (Breeder) Reactors

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PWR Development and APWR

70’s 80’s 90’s 2000’s 2010’s 2020’s

Development & Improvement of PWR Technology

APWR Upgrading

APWR Tsuruga-3/4licensing process

US-APWRUS NRC Licensing

EU-APWR

US Utilities

European Utilities

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2. Main Design Features of US-APWR and EU-APWR

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The APWR is a large capacity Generation III four-loop PWR.The US version is the US-APWR, which is under licensing by US NRC for DC.The EU-APWR is the European version of the APWR.The basic design concept of the EU-APWR and the US-APWR is the same as that of the APWR (Tsuruga #3,4) whose design is complete and is under safety review and licensing process in Japan.The US-APWR and EU-APWR are based on the established APWR technology.

What is APWR

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Improvements leading to EU-APWR

Current 4-loop PWRAPWR

(Tsuruga 3 and 4)EU-APWR/US-APWR

Electric Output 1,180 MWe

3,411 MWt

12 ft Fuel 193 Assem.

4,900m2

20,100 m3/h

44 inches blades

PCCV

Electrical 2 trainsMechanical 2 trains

HHSI×2Accumulator x 4

LHSI×2

Safety System : AnalogControl System : Digital

1,538 MWe 1,700Mwe Class

Core Thermal Output 4,451 MWt 4,451 MWt

Core 12 ft Fuel 257Assem. 14ft Fuel 257 Assem.

SG Heat Transfer Area per SG 6,500m2 8500m2

Thermal Design Flow rate per loop 25,600 m3/h 25,400 m3/h

Turbine 54 inches blades 74 inch blades

Containment Vessel PCCV PCCV

Electrical 2 trainsMechanical 4 trains

Electrical 4 trainsMechanical 4 trains

HHSI× 4Advanced Accumulator x 4

Elimination of LHSI

HHSI ×4Advanced Accumulator x 4

Elimination of LHSI

I&CFull Digital Full Digital

Safety Systems

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Improved Operation & Maintenance

Attractive Economics

High Reliability

Enhanced Safety

Steam generator

Reactor

Engineeringsafety features

High Pressure Turbine

Low Pressure Turbine

Reheat Stop Valve

ExciterGenerator

Intercept ValveMoisture Separator & Reheater

Steam Chest (Main Stop Valve・Governing Valve)I & C System （54-inch rotating blades）Turbine Generator

4 Mechanical Systems of Engineered Safeｔy Features

Refueling Water Storage Pit Installed in Containment Vessel

• Advanced Accumulator (Passive Device)

• Advanced Control Room with Compact Console

• Easier Maintenance by Full Digital I&C

• Construction Cost Reduction (Compact Layout, Simplified Systems and Component)

• Improved Reactor Internals (Neutron Reflector)

• Improved Steam Generator

Features of APWR

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Reactor Flow Test

SG Separator Test

LP Turbine Test

1992 2000 2004

Performance, Flow, Seismic Tests

Performance and Flow Tests

Performance Tests

• Reactor Internalsand Neutron Reflector Flow Tests

Operability Tests with Simulator

Performance and Vibration Tests

• Compact SG andImproved Separator

• Advanced Accumulator

• High-performance RCP

• Advanced I&C System

• Turbine

1994 1996 1998 2002 2006 2008 2010

: APWR : US-APWR

Flow Tests (Lower Plenum)

• Fuel14ft Fuel Assembly

74 inch Turbine On Load Test

Verifications for Advanced Designs

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3,565 MWt17.9 kW/m

4,451 MWt17.6 kW/m

4,451 MWt15.2 kW/m

Current4 Loop Plant APWR

Large Output

Low Power Density

12ft 12ft 14ft

193F/As 257F/As 257F/As

EU-APWR/US-APWR

Reactor Design

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Large volumetric core structure Neutron Reflector

for fuel cost reduction

Higher reliability

Neutron Reflectorfor simplified structure（ Number of bolts ：

2,000→ 50)

Core barrel

Large reactor internals for large output

10 ringblocks

Cooling holes

Reactor Internals Design

Lowercore plate

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Enhanced Safety of APWR- ECCS Configuration -

ACCSIPLHSIPCSPSHRVRWSP

：Advanced Accumulator：Safety Injection Pump：Low Head SIP：Containment Spray Pump：Spray Header：Reactor Vessel：Refueling Water Storage Pit

SH SH

SHSH

RWSP

RV

4 train ；DVI*1 design for SIP→ Independent and

Redundant→ Simplified configuration

50%-capacity pumps

In-containment RWSP→ Low CDF*2

1/10 of current 4-loop plant

Advanced Accumulator →Passive flow switch

Combination of conventional accumulator and LHSIP

System Configuration

＊1：Direct Vessel Injection

＊2：Core Damage Frequency

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Current 4 Loop Plant

APWR

Accumulator 4(conventional type)

4(advanced type)

100%×2 50%×4(used also as RHR)

SI Pumps:High HeadLow Head

100%×2100%×2

(used also as RHR)

50%×4－

CS Pump

Safety Systems Comparison of number of ECCS component

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Safety Systems Advanced Accumulator (1/3)

Nitrogen

InjectionWater

Flow Damper

Large Flow Rate

Injection Water

Nitrogen

Flow Damper

Reduced Flow Rate

Main stand Main stand pipepipe

Side inletSide inlet

Side inletSide inlet

The flow damper passively switches the injection flow rate.

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Current Four-Loop plant APWR

Inje

cted

flow

Inje

cted

flow

Time Time

Blow Down& RV Refill

Blow Down& RV RefillLong-time cooling Long-time cooling

AccumulatorLow head injection pump

High head injection pump

Requirement for injection Requirement

for injection

Advanced accumulator

Safety injection pump

Core Re-flooding Core Re-flooding

Automatic Switching of Injection Flow Rate by Flow DamperElimination of Low Head Injection Pumps

Improvements of reliabilityReduction of total capacity of safety injection pumpsSubstitution for RHR function by CS* Pumps/Coolers

＊：Containment Spray

Safety Systems Advanced Accumulator (2/3)

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Large Flow Flow Switching Small Flow

○ 1/5 scale flow damper model○ Verification Points

- During large flow, no vortex flow occurred.- At lower water levels, a stable vortex is created, causing a

decrease in flow rate.

Flow Pattern in Vortex Chamber

Verification Test of Advanced Accumulator

Safety Systems Advanced Accumulator (3/3)

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Soft OperationSoft Operation

Large Display PanelLarge Display Panel

Improved monitoring and operational performance by integrating controls and information display

Improved monitoring and operational performance by integrating controls and information display

Compact Operator ConsoleCompact Operator Console

Advanced Control RoomImproved human-system interface and reliability of operation

Full Digital I&C Became “On-The-Job”

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Current4 Loop APWR EU-APWR/US-APWR

Electric Output 1,180 MWe 1,538 MWe 1,700 MWe ClassCore Thermal Output 3,411MWt 4,451 MWt 4,451 MWt

Model 54FTube size 7/8” 3/4” 3/4”

Model

LP last-stage blade

93A-1

44 inch

70F-1 91TT-1

Reactor Coolant Pump MA25(60 Hz) MA25(50Hz)/MA25(60Hz)

Turbine 54 inch 74 inch

Steam Generator

Plant Parameters and Major components

APWR1,538MWe output is achieved by large capacity core and large capacity main components such as SG, RCP, turbine, etc.

EU-APWR/US-APWR1, 700MWe output is achieved from a higher efficiency than APWR.

• Same core thermal output with APWR• High-performance, large capacity steam generator• High-performance turbine

Main features of US and EU-APWR (1/3)

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Current 4 Loop APWR EU-APWR/US-APWR

Core Thermal Output 3,411MWtNO. of Fuel Assem. 193

Fuel LaticeActive Fuel Length 12ft 12ft 14 ft

Reactor internals Baffle/former structure Neutron Reflector Neutron Reflector

In-core Instrumentation Bottom mounted Bottom mounted Top mounted

17×17 17×17 17×17

4,451 MWt 4,451 MWt257 257Core

and Fuel

Reactor Core and Internals

APWRIncreased number of fuel assemblies increase core capacityNeutron reflector enhances reliability and fuel economics

EU-APWR/US-APWR14ft assemblies in the same reactor vessel achieves low power density, which enhances fuel economics for 24 month operationImprove reliability and maintainability of reactor vessel with top mounted ICIS

Main features of US and EU-APWR (2/3)

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Current 4 Loop APWR EU-APWRUS-APWR

Electrical 2 trainsTrains

Mechanical 2 trains 4 trains 4 trains

LHSI pump 100% × 2 - -

RWSP Outside CV Inside CV Inside CV

Control Room ConventionalSafety I&C Conventional

ACC 4 4 (Advanced) 4 (Advanced)Systems

HHSI pump

Non-Safety I&C

100% × 2

PCCV

Digital

2 trains 4 trains

50% × 4(DVI) 50% × 4(DVI)

Containment Vessel PCCV PCCVI & C

Full Digital Full Digital

Safety Systems

Safety system and I & C

APWREnhanced safety with simplified and reliable safety systems

• Mechanical four-train systems with direct vessel injection• Elimination of LHSI pump by utilizing advanced accumulators • Elimination of recirculation switching by In-containment RWSP

EU-APWR/US-APWREnhanced safety by four-train safety electrical systemsEnhanced on line maintenance capability

Main features of US and EU-APWR (3/3)

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Safety Objectives & Safety Principle

Probabilistic Approach in EU-APWR DesignProbabilistic Safety Approach (PSA) is used at the design stage in order to :

identify where diversity is needed in the design of safety systems, in complement to redundancy ;

demonstrate that probabilistic safety targets are metdefined in the EUR ;

cumulative core damage frequency < 10-5 per year

cumulative frequency of exceeding the criteria for limited impact (CLI)* < 10-6 per year

CLI : Acceptance criteria given by a comparison of a linear combination of families of isotope releases versus a maximum value. Each criteria is associated with a specific kind of limited consequence to the public.

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Safety Design Items

Item US-APWR EU-APWRDesign Extension Conditions

Not required in the USAlternate AC (non-

safety)

ATWS, multiple SGTR, MSLB+SGTR and SBO) and complex sequences

Additional Diverse systemsEBS, ACCWS, AAC( two trains)

Grace Period 10minutes 30 minutes Fire protectionSystem and layout design

assuming fire coincident with OLM

assuming fire coincident with a single failure and OLM

Air plane crash Base Assuming Larger Plane

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Seismic Design Response Spectra (SDRS)for US-APWR and EU-APWR standard design

0.3 g Peak Ground AccelerationFor the two horizontal directions and the vertical directionEU-APWR SDRS envelops EUR Design Basis Earthquake (DBE)

Earthquake

0.0

0.5

1.0

0.1 1.0 10.0 100.0Frequency ( Hz )

Acceleration (G)

EU-APWR RG 1.60 EUR-Hard soilEUR-Medium soilEUR-Soft soil

0.3G

0.25G

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Buildings

Reactor Building

TurbineBuilding

Auxiliary Building

Access BuildingPower Source Building

(Containment Vessel)Plant

North

R/BA/B

AC/B

T/B

PS/B PS/B

P.N.

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Typical Project ScheduleYears -7 -6 -5 -4 -3 -2 -1 0 +1 +2 +3 +4 +5

Milestones

Construction

Engineering & Design

Licensing

Permitted

First ConcreteCommercialOperationFuel Loading

48 months

CommissioningApply

*1: The open-top installation method is assumed.

Major Components Basic Design & Material Spec. (Site-Specific)

FSAR

TI

CI

NI

T-G Installation

Heavy ComponentsInstallation*1

Super Heavy Duty Crane Procurement

Cold Hydraulic Test

Civil Basic DesignCivil Engineering

Excavation etc.

Site-Specific Basic Design

Detailed Design (Detailed 3D-CAD, Piping Drawings etc.)

8 months

Hot Functional Test

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3. Design Features of EU-APWR relevant to Fukushima Accident

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Design Features of EU-APWR relevant to Fukushima Accident

Mitigation systems to address multiple failures of safety systems have been incorporated into the design

Redundant diverse AC power supplies (air-cooled gas turbine generators)Redundant alternate heat removal systems

by air-coolers, independent from seawater coolingRedundant extra boration systems

Even in the case of a loss of Ultimate Heat Sink (Essential Service Water) coincident with SBO, Plant could be brought to a cold shutdown.

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Design Features of EU-APWR relevant to Fukushima Accident

Mitigation systems to cope with severe accident have been incorporated into design

MHI core catcherRedundant reactor cavity injection systemsPassive Autocatalytic Recombiner in the CV Large volume of Containment (PCCV)

Investigating lessons-learned from Fukushima Accident, MHI would further reinforce the robustness of EU-APWR for severe situations.

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G

Gas Turbine Generator

(3)Extra Boration System

(4) MHI core catcher

(2)Alternate Component Cooling Water System

(4) Reactor Cavity Injection System

RCP thermal barrierSFP HxRHR Hx

Design Features of EU-APWR

(1)Alternate AC Power Source

(4) PAR

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4. MHI Nuclear Capabilities

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DesignDesign ManufactureManufacture ConstructionConstruction

Research and DevelopmentResearch and Development MaintenanceMaintenance

Mitsubishi performs broad and integrated business activities from research & development, design, manufacture, and construction through maintenance related to PWR plants.

MHI Engineering Activities

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Mitsubishi streamlines all of its processes from initial basic design to manufacture/construction using a seamless design information management system (CAD/CAM systems).

Material Management

Manufacturing by CAM

Construction Management

Stress Analysis of Piping

Integrated Database

Design - Plant Engineering -

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Mitsubishi encourages technical innovation and maintains its efforts to update its technologies at all times with high accuracy, efficiency, and reliability.

Electron beam gun

Turn table

Reactor Vessel

6000 ton Hot press forming

150kWElectron beam welding machine

Super large Multi- functional NC- machine “Super Miller”

Manufacturing

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Modularization in construction

1. Piping modules4. CV upper head

3. SC modules2. Packaging

modules

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Tomari Unit 3(Commercial Operation from December 2009)

40m Diameter Containment Vessel Upper Head

Heavy Duty Crane(Reducing Field Work)

Mitsubishi has introduced and demonstrated advanced construction methods resulting in both reduced construction schedules and reduced cost.

Construction

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5. Summary

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Summary of US-APWR and EU-APWR

Enhanced SafetyFour train safety system, advanced accumulator, full digital I&C system and advanced main control board

Higher ReliabilityEmploying well designed, verified, and proven technologies

Improved EconomicsLarge capacity and high plant performanceHigh fuel performance for 12 to 24 months operation

Compliance with US or European Requirements