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Overview of APROverview of APROverview of APROverview of APR1400 1400 1400 1400 DesignDesignDesignDesign

IAEA INPRO DF-7

Vienna, November 19-22, 2013

Jong Tae Seo

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1. Design Development

2. Design Characteristics

3. Design Verification

4. Construction Projects

5. INPRO Criteria for Evaluation

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Development Strategy

APR1400 Design Development

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� Uprate power to 4,000 MWth (1,450 MWe) based on

OPR1000’s 2,825 MWth (1,050 MWe) technology

� Incorporate Advanced Design Features to enhance safety

and operational flexibility

� Meet the Utility Requirements (domestic & world-wide)

− Proven Technology

− Constructability

− Maintainability

− Regulatory Stabilization

Development Strategy

APR1400 Design Development

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* OPR1000 :

Optimized Power

Reactor 1000

*APR1400 :

Advanced Power

Reactor 1400

1,400 MWeUnder Construction

- SKN # 3,4, SUN # 1,2

NSSS Design

Palo Verde #2 (CE,1300MWe)

Core Design

ANO #2 (CE,1000MWe)

OPR1000

1,000 MWe

- In Operation - YGN #3,4 (’95/’96) - UCN #3,4 (’98/’99)

Improved OPR10001,000 MWe

- In Operation - YGN #5,6 (’02/’02) - UCN #5,6 (’04/’05)

- Under Construction - SKN #1,2 - SWN #1,2

ADF/PDF

Latest Codes

& Standards

EPRI URD

System 80+

APR1400 Design Development

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Standard Design Approval by KINS in 2002

Standard Design Approval

of APR1400Standard Safety Analysis Report

APR1400 Design Development

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Parameters APR1400

Thermal/ Elec. Power 4,000 MWt / 1,450 MWeDesign Life 60 YearsSeismic Acceleration 0.3 g

Operating Parameters- Thot / Tcold 615 / 555 OF- Operating Pressure 2250 psia- RCS Flow Rate 1.66 x 106 lb/hr- Main Steam Pressure (@Full Power) 1000 psia- Main Steam Flow Rate 8.975 x 106 lb/hr

Safety Parameters - CDF 2.25 x 10-6 < 10-5/RY

- Containment Failure Frequency 7.19 x 10-7 < 10-6/RY- Thermal Margin >10%- Emergency Core Cooling System 4-train, DVI,

Fluidic Device in SITPerformance Requirements- Plant availability More than 90 %- Unplanned trip Less than 0.8/year- Refueling cycle 18 ~ 24 months

Design Parameters

APR1400 Design Characteristics

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RCS Configuration

APR1400 Design Characteristics

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Reactor Core

Number of assemblies : 241

Thermal margin : above 10 %

Refueling cycle : over 18 months

Batch average burn-up : 55,000 MWD/MTU

Enhanced operational flexibility

- Daily load follow operation capability

- MOX loading capability up to 1/3 core

APR1400 Design Characteristics

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Plus-7 FuelTM

APR1400 Design Characteristics

GT (4)

IT (1)

Spacer Grid

Debris Filtering

Bottom Nozzle

Removable

Top Nozzle

Fuel Rod with

High Burnup

Capability

Reduced Rod Bow

Top Inconel Grid

Mid-Grid(9) with

Mixing Vanes

Debris Filtering

Protective Grid

Bottom Inconel Grid

with High Burnup

Capability

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Reactor Vessel & Internal

Reduced radiation exposureReduced radiation exposure

• Reduced Cobalt contents in base material

Integrated Lower Internal AssemblyIntegrated Lower Internal Assembly

• Welded IBA to UGS upper flange

- Eliminate tie rods, round nuts, snubber flange & Block

Integrated Inner Barrel AssemblyIntegrated Inner Barrel Assembly

• Integrated core support barrel, core shroud,and lower support structure in one assembly

Enhanced RV integrityEnhanced RV integrity

• No weld seam in fuel region shell

• Using low Copper contents material

APR1400 Design Characteristics

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Integrated Head Assembly (IHA)

Integrated ComponentsIntegrated Components

• Head area cable tray

system, CEDM air

handling unit, cooling

duct, cooling manifold

and head lift rig, etc.

IHA ReducesIHA Reduces

• Refueling Time

• Occupational Radiation

Exposure

• Component Storage Area

• Seismic Load

APR1400 Design Characteristics

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Reactor Coolant Pump

Vertical pump

Motor-driven centrifugal pump

Bottom suction & horizontal discharge

Single stage impeller

APR1400 Design Characteristics

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Pressurizer with POSRV

Increased VolumeIncreased Volume

• Total volume : 2,400 ft3

• Enhancing coping capability against

plant transients

• Performing over-pressure protection and

safety depressurization

• Main valve open by pilot valve actuation

• Steam/Water/Two-Phase discharge

• No drift of the opening set-point

• Reliable valve operation without

chattering and leakage

• Low susceptibility for valve stuck-open

Pilot Operated Safety Relief ValvePilot Operated Safety Relief Valve

APR1400 Design Characteristics

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Steam Generator

• Increasing space to install SG nozzle dam

- Improving stability in mid-loop operation

Modified SG Inlet Nozzle AngleModified SG Inlet Nozzle Angle

• Increased anti-vibration bars

- Reducing flow-induced tube vibration

Improved Tube Support Bars and PlateImproved Tube Support Bars and Plate

Design ParametersDesign Parameters

• Integral Economizer

• Number of tubes : 13,102 / SG

• Plugging margin : 10 %

• Tube material : Inconel 690

APR1400 Design Characteristics

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Safety Injection System

CONTAINMENTCONTAINMENTCONTAINMENTCONTAINMENT

SITSITSITSIT SITSITSITSIT

SITSITSITSIT SITSITSITSIT

S/GS/GS/GS/G RVRVRVRV S/GS/GS/GS/G

SIPSIPSIPSIP

SIPSIPSIPSIP

SIPSIPSIPSIP

SIPSIPSIPSIP

IRWSTIRWSTIRWSTIRWSTRCPRCPRCPRCP

RCPRCPRCPRCP

RCPRCPRCPRCP RCPRCPRCPRCP • No safety injection water spillage

in cold-leg break LOCA

• Increase the reliability of the

injection during LOCA

Simplified DesignSimplified Design

Direct Vessel InjectionDirect Vessel Injection

• Mechanically independent 4 train

• 1 SIP/train

• 1 SIT/train

• No low pressure pumps

• One injection mode

APR1400 Design Characteristics

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MMIS Overview

APR1400 Design Characteristics

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APR1400 Design Characteristics

Advanced Control Room

• Major components

- Redundant compact workstation

with soft control

- Large display panel

- Advanced alarm system

- Safety console

· Backup for common mode failure

- Computerized procedure system

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Layout : Slide-along Arrangement (2 units)

• Auxiliary Building (AB)- Quadrant arrangement to enhance safety

- Accommodating MCR, Emergency D/G,

Fuel handling facilities

• Reactor Containment Building (RCB)- Pre-stressed cylindrical wall and hemi-

spherical dome concrete structure

- Wrapped around by auxiliary building

• Compound Building (CB)- Accessible from both units

- Housing common facilities of Access control,

Radwaste treatment, Hot machine shop, etc

• Turbine Building (TB)- Steel structure with reinforced concrete

turbine pedestal

- Common tunnel for all underground facilities

APR1400 Design Characteristics

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Quadrant Arrangement of Safety Components

Quadrant CQuadrant CQuadrant CQuadrant C Quadrant AQuadrant AQuadrant AQuadrant A

Quadrant DQuadrant DQuadrant DQuadrant D Quadrant BQuadrant BQuadrant BQuadrant B

CCWP 3

CCWP 4 CCWP 2

CCWP1

SCP 1

SCP 2

SIP 3

SIP 2

SIP 1

SIP 4CSP 2

CSP 1

SIP ( Safety Injection Pump) SCP (Shutdown Cooling Pump) CSP (Containment Spray Pump) CCWP (Component Cooling Water PuSIP ( Safety Injection Pump) SCP (Shutdown Cooling Pump) CSP (Containment Spray Pump) CCWP (Component Cooling Water PuSIP ( Safety Injection Pump) SCP (Shutdown Cooling Pump) CSP (Containment Spray Pump) CCWP (Component Cooling Water PuSIP ( Safety Injection Pump) SCP (Shutdown Cooling Pump) CSP (Containment Spray Pump) CCWP (Component Cooling Water Pump)mp)mp)mp)

APR1400 Design Characteristics

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Fluidic Device (FD)

APR1400 Design Verification

Closure PlateClosure PlateClosure PlateClosure Plate

Vortex ChamberVortex ChamberVortex ChamberVortex Chamber

Insert PlateInsert PlateInsert PlateInsert Plate

Middle & Middle & Middle & Middle & Lower Lower Lower Lower PlatePlatePlatePlate

Partition PlatePartition PlatePartition PlatePartition Plate

VAPER (Valve Performance Evaluation Rig)

• Evaluate safety injection flow performance of Safety Injection Tank

with fluidic device

• Test facility : Same size and pressure condition as APR1400

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Direct Vessel Injection (DVI)

APR1400 Design Verification

Examine/measure ECC bypass in reflood phase of cold-leg large break LOCA

� 1/5 linear scale (UPTF:1/4.08 linear scale)

� Steam-water (superheated and saturated steam) tests

Multi-dimensional Investigation in Downcomer Annulus Simulation

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IRWST and Sparger

APR1400 Design Verification

� Measure air, steam, and water blowdown load on SDVS & IRWST structures

� Investigate thermal mixing between discharged fluid and water in IRWST

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Integral Test Loop of APR1400 - ATLAS

APR1400 Design Verification

� State-of-the-art integral loop test facility

� Scale:1/2-height & 1/144-area of APR1400

� Test data useful for code benchmarking

Steam Generator (2)

Safety Injection Tank (4)

Reactor Vessel

Jet Condenser

Jet CondenserHeat Exchanger

FeedwaterHeat Exchanger

FeedwaterPump

Jet CondenserSpray Pump

LBLOCABreak Simulator

Containment SimulatorDischarge Line

ContainmentSimulators

Reactor CoolantPump (4)

PressurizerMSSV Simulator

MSLBBreak Simulator

SGDowncomer

FeedwaterLine

Steam Generator (2)

Safety Injection Tank (4)

Reactor Vessel

Jet Condenser

Jet CondenserHeat Exchanger

FeedwaterHeat Exchanger

FeedwaterPump

Jet CondenserSpray Pump

LBLOCABreak Simulator

Containment SimulatorDischarge Line

ContainmentSimulators

Reactor CoolantPump (4)

PressurizerMSSV Simulator

MSLBBreak Simulator

SGDowncomer

FeedwaterLine

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FOAK Project – Shin Kori 3&4

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Milestone Schedule (Unit 3)

FOAK Project – Shin Kori 3&4

� Site Grading : Sep. 13, 2007

� Excavation(CP) : Apr. 15, 2008

� First Concrete Pouring : Oct. 16, 2008

� Set Reactor Vessel : Jul. 15, 2010

� Cold Hydro Test : May 1, 2012

� Hot Functional Test : Nov. 20, 2012

� Fuel Loading(OL) : Jan. 2014 (Tentative)

� Commercial Operation : Sep. 2014 (Tentative)

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Project Structure

FOAK Project – Shin Kori 3&4

Equipment Start-upConstruction

T/G

DOOSAN

BOP

KHNP

A/E

KEPCO E&C KHNP

KEPCO

E&CWEC

Local

Constructors

Project Management

KHNP

FUEL

KEPCO NF

NSSS

DOOSAN

GE Vendors

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Site Views

FOAK Project – Shin Kori 3&4

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Site Views

FOAK Project – Shin Kori 3&4

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Manufacturing

FOAK Project – Shin Kori 3&4

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Construction Pictures

FOAK Project – Shin Kori 3&4

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Construction Pictures

FOAK Project – Shin Kori 3&4

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Construction Pictures

FOAK Project – Shin Kori 3&4

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Other APR1400 Construction Projects

Shin-Hanul 1&2

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• Construction Permit : 2011.12.3

• Unit #1 First Concrete : 2012.7

• Commercial Operation :

Unit #1 : 2017.4

Unit #2 : 2018.4

• PSAR Submit : 2010.12.31

• Construction Permit : 2012.7

• Unit #2 First Concrete : 2013.5

• Unit #1 RV Setting : 2014.7

• Commercial Operation : 2017.5

~ 2020.5

Barakah NPP 1~4 in UAEBarakah NPP 1~4 in UAE

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Other APR1400 Construction Projects

Shin-Hanul 3&4

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• PSAR Submitted for

Construction License : May 2012

• Commercial Operation : Unit #5 : 2019

Unit #6 : 2020

• Contract Negotiation• Commercial Operation : Unit #3 : 2020

Unit #4 : 2021

Shin-Kori 5&6

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Nuclear Status in Korea

Units (MWe)Units (MWe)

# 1,2,3,4,5,6

� In Operation

6 (5,900)

Younggwang 6 (5,900)

KoriKoriKoriKori 8 8 8 8 ((((7777,,,,937937937937))))

#1 ~ 4, SKN #1,2

Shin Kori #3,4

� Under Construction

� In Operation6 (5,137)

2 (2,800)

Shin Kori #5,6

� Under Planning

2 (2,800)

# 1,2,3,4,5,6

Shin Ulchin #1,2

6 (5,900)

2 (2,800)

� Under Construction

� In Operation

UlchinUlchinUlchinUlchin 8 8 8 8 ((((8888,,,,700700700700))))

Shin Ulchin #3,4

� Under Planning

2 (2,800)

Wolsong 6 (4,779)

# 1,2,3,4 (HWR)

ShinWolsong #2

� Under Construction

� In Operation4 (2,779)

1 (1,000)

SWS# 1(PWR) 1 (1,000)

HANBIT

HANUL

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Nuclear Status in Korea

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5

28

20,716

6,600

27,316

In Operation

Under Construction

Total

Units (MWe)

60

70

80

90

100

`00 `01 `02 `03 `04 `05 `06 `07 `08 `09 `10 `11 `12

Korea World AverageCapacity Factor

84.3%

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Nuclear Status in Korea

Installed CapacityInstalled Capacity Power Generation

Total: Total: Total: Total: 81818181,,,,806 806 806 806 MWMWMWMW Total: Total: Total: Total: 504504504504,,,,869 869 869 869 GWhGWhGWhGWhGeneration in 2012

Generation Mix Generation Mix

22%22%

Nuclear

Coal

Gas

Oil

Hydro

Others

25%25%

30%30%25%25%

9%9%8%8% 30%30%

39%39%

6%6%3%3%

1%1%

(20,716 MW)(20,716 MW) (150,327 GWh)(150,327 GWh)

as of January 1, 2013

2%2%

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Selected INPRO Criteria for

APR1400 Evaluation

� BP-1 Defense in Depth

� UR1.2 (Detection and Interception)

� CR1.2.1 : I&C and Inherent Characteristics

� UR1.3 (Design Basis Accident)

� CR1.3.3 : Safety Features

� UR1.4 (Release into Containment)

� CR1.4.3 : Accident Management

� BP-4 Research, Development and Demonstration

� UR4.2 (RD&D for Understanding)

� CR4.2.1 : RD&D

� CR4.2.2 : Computer Codes

� CR4.2.3 : Scaling

39

Initial Pre-application Meeting