08.park smart korea

SMART

An Early Deployable Integral Reactor

for Multi-purpose Applications

INPRO Dialogue Forum on Nuclear Energy Innovations:CUC for Small & Medium-sized Nuclear Power Reactors, 10-14 October 2011, Vienna, Austria

Keun Bae ParkSMART Technology Development

SMARTSystem-integrated Modular Advanced ReacTor 2

Contents

SMR Perspectives

Design & Safety Features of SMART

Current (licensing) Status

Summary

SMART : System-integrated Modular Advanced ReacTor


Contents

SMR Perspectives



Summary


Small & Medium Reactors (SMR) offer Several Advantages Enable enhanced safety features (robustness)

- Easier implementation of passive safety features Suitable for isolated or small electrical grids Lower capital cost per unit

- Small initial investment and short construction period reduces financial risks- Makes nuclear energy feasible for more utilities and energy suppliers

Multi-purpose application (co-generation flexibilities) Just-in-time capacity addition, Short construction time

- Enable gradual capacity increase to meet electric demand growth

Many realizable SMR concepts proposed are based on the LWR technology and reflection of the past experiences By eliminating the cause of accidents (initiators), instead of controlling

accidents (ex. DBAs) Integral PWR fits into these logical requirements

SMR- Perspectives


SMR Prospects Replacement for retiring fossil plants

- reduces greenhouse gases Non-electrical uses

- desalination, process heat, etc Multiple units permit generation with less impact by planned outages

User Expectations (Requirements) Proven Technology - Licensing Requirements and Conformance Safety Plant Performance and Applications Economics and Financing Proliferation Resistance and Physical Protection Assurance of Supply

SMR- Perspectives


No single SMR can compete with large NPP Multi-modular units

Design/Equipment Simplification Modular construction approach Easier to adopt passive features (elimination of active components)

Shorter Construction Time

Multiple Units per Plant Enable facilities/equipments sharing Reduces site-related costs Permit generation with less impact by planned outages

Just-in-time Capacity Addition (Scalability) Enable gradual capacity increase to meet energy demand

Economical Aspects (Competitiveness)


Contents

SMR Perspectives

Design and Safety Features of SMART


Summary


Basic Concept of SMART

Plant Data

Power : 330 MWt Water : 40,000 t/day Electricity : 90 MWe

System-integrated Modular Advanced ReacTor

SeawaterFreshwater

Electricity

Desalination Plant

IntakeFacilities

Steam

SMART

SteamTransformer

330MWth Integral PWRElectricity Generation, Desalination and/or District Heating

Electricity and Fresh Water Supply for a City of 100,000 Population Suitable for Small Grid Size or Localized Power System


4 Units of MED-TVC to produce 40,000 ton/day + 90 Mwe Steam supplied through turbine extraction Steam Transformer - additional protection of possible radioactive

contamination

Application of SMART (1)

Schematic Diagram of MED-TVC

Return to Power Plant

From Power Plant

To Thermo Compressor

From Condensate Return

Return to Power Plant

From Power Plant

To Thermo Compressor

From Condensate Return

Steam Transformer

Desalination SystemDesalination System


147 Gcal/h of Heat Supply to Local Area Heating + 82 MWeSupply of Electricity and 85°C Hot Water for 100,000 Populations

- Based on Korean Peak Electric Power and Heat Usages

District Heating

0.0 0.5 1.0 1.5 2.0 2.5 3.060

80

100

120

140

160

180

60

80

100

120

140

160

180

Heat

Gen

erat

ion

(Gca

l/hr)

Elec

tric

Powe

r Gen

erat

ion

(MW

e)

LP TBN Exit Pressure (bar)

Expected design point for 85 °C hot water

Application of SMART (2)


Pressurizer

Helical Steam Generator

XX

XX X

X

Loop Type PWR Integrated Primary System

Inherent Safety : Passive

Residual Heat Removal

Advanced Digital Man-

Machine Interface System

Integral Design

Core

Canned Motor Pump

Enhanced Reactor Safety: No LBLOCA Flexible Applications: Electricity, Heat Early Deployment: Proven Technology

SMART(System-integrated Modular Advance

ReacTor)

SMART


Integral PWR - SMART

Control Rod Drive Mechanism

Pressurizer

Reactor Coolant Pump

Upper Guide Structure

Core Support Barrel

Flow Mixing Header Ass’y

Core

ICI Nozzles

Steam Nozzle

Feedwater Nozzle

SteamGenerator

330 MWt (100 MWe) nominal output• Small core (57 fuel assemblies) and source term• Unit output enough to support electricity, water and

heat demand for population of 100,000

Integral PWR with no large RPV penetrations• Less than 2’’ penetrations• In-vessel Pressurizer, Steam Generator and

RCP (Canned Motor Pump

Inherent Safety• Elimination of LB-LOCA by design• No core uncovery during SB-LOCA• Large Coolant Inventory per MW• Low Power Density (~2/3 of Large PWR)

Performance proved Fuel• Standard 17x17 UO2 (< 5 w/o U235) w/reduced height (2m)• Advanced Grid / IFM design• Peak Rod Burnup < 60 GWd/t• Performance proved @ operating PWRs

Improved Core Operability• Cycle length: 1,000 EFPD (~ 3 years)• Proven reactivity control measures

- CRDM, Soluble Boron, BP


Basic Information

Type of Reactor Integral PWRThermal Power 330 MWthElectric Power 100 MWe (in case of desalination : 90 MWe)Design Lifetime 60 yearsCore Thermal Margin > 15 %Fuel Type 17x17 Square Effective Core Height 2 mFuel Material UO2 Ceramic (< 5 w/o)Number of Fuel Assembly 57Refueling Period 36 monthsReactivity Control Control Rod Assembly, Soluble BoronSteam Generator Helically Coiled, Once-Through Type (8)Reactor Coolant Pump Glandless Canned Motor Pump (4)Control Rod Drive Mechanism Magnetic-Jack Type (25)


System Parameters

Parameter Value

Core Thermal Power (MWth)Design Pressure/Temperature (MPa/oC)Operating Pressure (MPa)SG Inlet Temperature (oC)SG Outlet Temperature (oC)Flow Rate (kg/sec)Steam Pressure (MPa)Steam Temperature (oC)Steam Superheating (oC)SG Tube MaterialSG Tube I.D/O.D (mm)Tube Plugging Margin (%)

33017/360

15323

295.720905.229830

Inconel 69012/17

10


Nuclear Steam Supply System General

• Thermal/Electric Power : 330 MWt/100 MWe• Design Life Time : 60 Years

Design Characteristics• Integrated Primary System• Passive Residual Heat Removal System• Simplified Safety Injection System• Long Refueling Cycle : 36 months• Full Digital MMIS Technology


Control & Protection (Digital MMIS)

Fully Digitalized I&C System : DSP Platform 4 Channel Safety/Protection System and Communication 2 Channel Non-Safety System

Advanced Human-Interface Control Room Ecological Interface Design Alarm Reduction Elastic Tile Alarm

Safety A channelSafety B channelSafety C channelSafety D channel

Non-Safety X channelNon-Safety Y channel

Safety Interface network

Non-Safety Interface networkNon-Safety Backbone network

Hard-wired connectionLogical data flow connection

RSR RCR TSC ERF

ISO

PIS D

PIS C

PIS B

PIS A

NIS D

NIS C

NIS B

NIS A

PPS D

PPS C

PPS B

PPS A

RTSG D

RTSG C

RTSG B

RTSG A

AIS(PAM B)

AIS(PAM A)

SGCS D

SGCS C

SGCS B

SGCS A

SMS B(ICCMS)

SMS A(ICCMS)

SafetyInterface Network

SMS(NIMS)

NIS Y

NIS X

PIS Y

PIS X POCS

PRCS Y

PRCS X

SDCS Y

SDCS X

AIS IPS

Non-safetyInterface Network

PAM-D

SGSC

NSGSC

NSGSC SGSCNSGSC NSGSC

Display such as Information (IPS), Indication (AIS) and Alarm (AIS)

LDP

Field Sensors Field Sensors Ex-Core Detectors MCC NIMS Sensors Ex-Core Detector Field SensorsCEDM

MCPMCC MCC

Non-SafetyBackbone Network

SafetyShutdownControlPanel

Main Control Panel

Auxiliary Control Panel

AISCEDM ERFICCMSIPSMCCMCPMCRNISNSGSCPAM -DPIS POCS PPSPRCSRCRRSRSCOPS SDCSSGCSSGSCSMSSSTSC

: Alarm and Indication System: Control Element Drive Mechanism: Emergency Response Facility: Inadequate Core Cooling Monitoring System: Information Processing System: Motor Control Center: Main Coolant Pump: Main Control Room: Nuclear Instrumentation System: Non -Safety Grade Soft Controller: PAM Display: Process Instrumentation System: POwer Control System: Plant Protection System: PRocess Control System: Rad waste Control Room: Remote Shutdown Room: SMART COre Protection System : SeconDary Control System: Safety Grade Control System: Safety Grade Soft Controller: Specific Monitoring System: Sub -network Switch: Technical Support Center






RSR RCR TSC ERF

ISO

PIS D

PIS C

PIS B

PIS A

NIS D

NIS C

NIS B

NIS A

PPS D

PPS C

PPS B

PPS A

RTSG D

RTSG C

RTSG B

RTSG A

AIS(PAM B)

AIS(PAM A)

SGCS D

SGCS C

SGCS B

SGCS A

SMS B(ICCMS)

SMS A(ICCMS)


SMS(NIMS)

NIS Y

NIS X

PIS Y

PIS X POCS

PRCS Y

PRCS X

SDCS Y

SDCS X

AIS IPS


PAM-D

SGSC

NSGSC



LDP


MCPMCC MCC



Main Control Panel





Electric System 100% x 2 Emergency DG & Alternate AC Power (Water-tight Bldg) Emergency Battery to Vital Systems for 10 hrs

Containment Building Passive Auto-catalytic Hydrogen Recombiners (12) Containment Spray System (2 Trains)

Water source from Sump integrated IRWST Containment Isolation System Aircraft Impact Proof

Auxiliary Building Quadrant Wrap-around Fuel Storage Inside Aircraft Impact Proof Single Base-mat with Containment

(Seismically Resistant)

EDG Bldg

Composite Bldg

Aux. BldgTBN Bldg

Containment

Balance of Plant


Core Damage Frequency less than 10-6 / RY

Containment Failure Frequency less than 10-7 /RY

Operator Action Time at least 30 min.

Capacity for Station Blackout EDG(2), AAC, Battery

Severe Accident Mitigation Capability In-Vessel Retention, ERVC, PARS, Containment Spray System

Seismic Design 0.3g SSE

Safety Consideration


CDF Contributor (Full Power Internal Events)

%SLOCA, 35.3

%RVR, 17.2 %ATWS, 11.4

%LSSB, 7.9

%LOFW, 7.7

%SGTR, 6.2

%GTRN, 4.4

%TLOCCW, 4.0

%RCPE, 2.2

%LOOP, 1.7

%ISLOCA, 1.0

%SGHR, 0.6

%SLBU, 0.2

%LOKV, 0.1

%LODC, 0.0

%LOCCW, 0.0


Inherent Safety No Large Break : vessel penetration < 2 inch Large Primary Coolant Inventory per MW Low Power Density (~2/3) Large PZR Volume for Transient Mitigation Low Vessel Fluence ( 1.1 x 1014 n/cm2) Large Internal Cooling Source (Sump-integrated IRWST)

Engineered Safety Features Passive Residual Heat Removal System (50 % x 4 train)

- Natural Circulation- Replenishable Heat Sink (Emergency Cooling Tank)

Safety Injection System (100 % x 4 train)- Direct Vessel Injection from IRWST

Shutdown Cooling System (100 % x 2 Train) Containment Spray System (2 Train)

Severe Accident Management In-Vessel Retention and ERVC Passive Hydrogen Control (PARs)

Safety Features


Safety Systems of SMART

Passive Residual Heat Removal System (4 trains) Safety Injection System (4 trains) Shutdown Cooling System (2 trains) Containment Spray System Emergency Diesel Generator (2) Alternate AC Hydrogen Control

Passive auto-catalytic recombiner(12)

Counter Measure : Severe AccidentLarge inventory of reactor coolantLarge containment volume


Passive Residual Heat Removal System

passively removes the residual heat from the secondary side of SG through natural circulation (10 m height difference btw SG and Hx)

cools down the temperature of RCS to 200℃ within 36 hours through removing the core decay heat and the sensible heat of reactor coolant after the reactor tripped from any power level


Station Blackout Management

SMART is secured against Station Blackout 2 Water-tight EDG and AAC insures Emergency Power Supply If EDG/AAC fails, Fully Passive (No Electricity) PRHRS insures

Safe Shutdown (PRHRS Heat Sink can be Replenished)

* Grace Time : the Time allowed for Operator’s Action before Core Damage** No Replenishment of PRHRS Heat Sink Assumed

Hydrogen Control PAR (12) passively removes Hydrogen in Containment, if any Large containment volume

- Max. hydrogen contents assuming 100% fuel clad oxidaion < 7 %: Hydrogen explosion does not occur

Scenario EDG/AAC PRHRS Grace Time*

1 Yes All 4 Trains -2 No All 4 Trains 20 Days**3 No 2 Trains 10 Days**4 No No 2.6 Days


Post Fukushima Action Items

No. Action Items Resolution

1 Automatic RX Shutdown @Earthquake >0.18g To be resolved @SSAR

2 Strengthen Aseismic Design for MCR Panel Done

3 Provide Water-tight Door & Drain Pump To be resolved @SSAR

4 Secure Mobile Generator and Battery To be resolved @SSAR

5 Improve Alternate EDG Design Criteria To be resolved @PSAR

6 Fix-up Extra Transformer Anchor Bolt To be resolved @PSAR

7 Prepare Measure to Cool-down SFP To be resolved @SSAR

8 Prepare Anti-Flood & Recovery for Final HeatRemoval

To be resolved @PSAR

9 Provide Passive Autocatalytic Recombiner Done

10 Provide Depress. or Purge on RX. Bldg N/A for SMART

11 Provide External Injection Path on SI To be resolved @SSAR


Contents

SMR Perspectives


Current (Licensing) Status

Summary


Technology Validation & Standard Design Approval

Standard Design, Licensing Q&A

2009 2010 2011 2012~17

LicensingSupport

Key Safety & Performance Validation

SSAR, CDM, EOG

SDA ApplicationPre-Application

TechnologyValidation

StandardDesign

Licensing

Standard Design Approval

FOAKE PlantConstruction Plan Preparation Underway

Separate Effect TestsDesign Tools & Methods

Regulatory Review

Pre-Application Review

Integral Effect Tests (VISTA)

SMART- ITLIntegral System Confirmation Tests

Construction


Current Status

Technology Validation Separate Effect Tests : 20 tests completed

Integral Effect Tests : small scale SBLOCA tests completed

Standard Design CDM, SSAR , EOG and related documents were submitted

for the application of Standard Design Approval : Dec. 2010

Licensing Pre-application Review (by KINS) : 2010

SDA Licensing Review (by KINS) : 2011

Standard Design Approval (Target) : End of 2011


Licensing Milestone toward SDA

Pre-Application Review : completed (2010) System Description, Preliminary Safety Analysis Reports, Tools &

Methods, Validation Test Plan, etc. (~ 800 Q&A’s)

Application of Standard Design Approval (Dec. 2010~ ) Certified Design Material, SSAR, EOG and related documents,

and 22 Technical Reports were submitted.

Document Conformance Evaluation (Feb. 2011)- 190 comments demanding supplementary / additional materials

1st Round Questionnaire (April, 2011)- 932 Q&A’s

2nd Round Questionnaire (July, 2011)- 470 Q&A’s

Nuclear Safety Committee Review : Nov. 2011

(target) Standard Design Approval : End of 2011


Project Organization - SMART SDA

Technology Validation : $60M Standard Design : $85M


Partnership for the SMART Project

KAERI KEPCO Consortium

KEPCO Consortium Project Management, Funding, Marketing Evaluation Leads the feasibility study on the construction of a FOAKE plant site survey, social acceptance, economics, etc


Contents

Introduction

History and Status of the SMART Project

Design Features

Safety of the SMART

Summary


Deployment Consideration

Domestic Construction Plan of Reference Plant Construction Planning (2012) Site Survey (2013~2015) Construction of Reference Plant (2015~2019 : FOAK)

Design Improvement for Construction (2012~2014) Application of Fukushima Daiichi Action Plans Prepare Automatic Reactor Shutdown @ Earthquake (> 0.18g) Enforce Seismic and Tsunami Criteria Prepare External Injection Path on the Safety Injection Line Improve Cooling Performance of Spent Fuel Pool Prepare Mobile Generation Facility & Connection Points

Optimization of BOP System Arrangement & Layout


Construction

Footprint 300 x 300 m for Electricity System 300 x 200 m for Desalination System

Boundaries EAB : Circle of R300 m EPZ : 1.5 km LPZ : 2 km

Construction Period 3 years (n-th plant)

Economics (as of 2007) Construction Cost

: $5,000 ~ $6,000/kWe Levelized Generation Cost

: ~ 6.1 ¢/kWh


Summary

SMR can provide Flexible Solutions to energy, water & environmental issues

Certified SMART Design will be available for commercial deployment

SMART is a viable option for early deployment of SMR Enhanced safety and operability by advanced design features Low licensing risks by using proven and validated technologies Flexible applications for both electricity and heat supply KEPCO consortium with wide NPP experiences strengthens the viability

of SMART

Thank you for attention !


Integral PWR - SMART

Control Rod Drive Mechanism

Pressurizer



Core Support Barrel

Flow Mixing Header Ass’y

Core

ICI Nozzles

Steam Nozzle

Feedwater Nozzle

SteamGenerator

330 MWt (100 MWe) nominal output• Small core (57 fuel assemblies) and source term• Unit output enough to support electricity, water and

heat demand for population of 100,000

Integral PWR with no large RPV penetrations• Less than 2’’ penetrations• In-vessel Pressurizer, Steam Generator and

RCP (Canned Motor Pump

Inherent Safety• Elimination of LB-LOCA by design• No core uncovery during SB-LOCA• Large Coolant Inventory per MW• Low Power Density (~2/3 of Large PWR)

Performance proved Fuel• Standard 17x17 UO2 (< 5 w/o U235) w/reduced height (2m)• Advanced Grid / IFM design• Peak Rod Burnup < 60 GWd/t• Performance proved @ operating PWRs

Improved Core Operability• Cycle length: 1,000 EFPD (~ 3 years)• Proven reactivity control measures

- CRDM, Soluble Boron, BP


Fuel & Core

Fuel Proven 17 x 17 UO2 Ceramic Fuel

with Reduced Height (2m) Peak Rod Burn-up < 60GWD/MTU

Core 57 Fuel Assemblies Fuel Cycle Length : 3 years Availability Factor : 95%

Reactivity Control Magnetic-Jack type CRDM Soluble Boron Burnable Poison

60 years of on-site Spent Fuel Storage

12 8 12 8 12

8 12 8 12 8

12 8 12 8 12

12 8 12

12 8 12

A B C D E F G H J

4

5

6

7

8

9

1

2

3

90°

270°

0°180°

2.82 w/o U-235 21 FA

4.88 w/o U-235 36 FA

N indicates No. of UO2+Gd2O3 fuel rods.

N

N

84 4

84 4

4

4

8

4

4

8

8

8 8

8

8

88

8

24

24

24

24

20

20

20

20

20

20 20

20

20

20

20

20

S2 S1 S1 S2

R1 R3 R1 R3 R1

S2 S1 S1 S2

R2 R3 R2

S2 S2

R1

R1

S2 S2

R2 R3 R2

A B C D E F G H J

4

5

6

7

8

9

1

2

3

90°

270°

0°180°

Regulating Bank

Shutdown Bank

R

S


Reactor Vessel Assembly

Primary Components in RPV 8 helical once-through SGs 4 canned motor pumps Internal steam pressurizer 25 magnetic jack type CRDMs

RPV Max 6.5m (D) x 18.5m (H) Material : SA508 Grade 3, Class 1


RPV and InternalsPSV Nozzle

CRDM Nozzle

ICI Nozzle

ICI Support Structure

PSV Nozzle

CRDM Nozzle

ICI Nozzle

PSV Nozzle

CRDM Nozzle

ICI Nozzle

ICI Support Structure

Flow Skirt

Core Support Barrel


Flow Mixing Header AssemblyHelically-coiled Steam Generator (8)

Impeller Flywheel

Diffuser

Component Cooling

Sealing Can

Shaft

Cooler Rotor

Stator

Impeller Flywheel

Diffuser

Component Cooling

Sealing Can

Shaft

Cooler Rotor

Stator

Canned Motor Pump(4)

In-vessel Steam Pressurizer

CRDM (25)


Nozzles

Nozzles on RPV

RCPItems Ea

RCP Nozzles 4

Feed Water Nozzles 8

Steam Nozzles 8

Safety Injection Nozzles 4*

Shutdown Cooling Nozzles 4*

Chemical Volume Control System Nozzles

2*

Ex-Core Detector Nozzles 2*

Reactor Coolant Ventilation Nozzles

1*

* Nozzle IDs are < 2.0 inch


Reactor Closure Head Assembly

ICI NozzleCRDM Nozzle

ICI Guide Tube Structure

RV Upper Flange

Name (Item) No Name (Item) No

CRDM Nozzle 25 PZR Level Gauge Nozzle 3

PZR Heater Nozzle 10 PZR Temp. Gauge Nozzle 2

PZR Safety Valve Nozzle 2 PZR Press. Gauge Nozzle 4

SDS Nozzle 2 Ex-Core Detector Nozzle 4

PZR Spray Nozzle 4 PZR Sampling Nozzle 1

ICI Nozzle 29 PZR Ventilation Nozzle 1

RV Level Gauge Nozzle 2


Pressurizer

In-Vessel Pressurizer Pressurizer Space

- Closure head and upper region of UGS- Not a separate equipment (hardware)

Pressure Control : by Electric heater- Steam & coolant mixture

Insulation - External Insulation on the Closure Head

- Wet Thermal Insulation

Operating Level

Surge Tubes

Steam

Heater


Major Component Design

Steam Generator

Helically coiled once-through HEX Produce Super-heated steam (30℃) Tube material : Alloy 690 Tube inspection (ISI)


Canned motor pumps Horizontally mounted on RV wall Monitoring

- Rotational Speed : Flow-rate- Acoustic & Vibration- Temperature (Coil, Coolant)- Motor Overload

Feed Water Header

Steam Header

Outer Shell

Impeller

Diffuser

Component Cooling Water Nozzle

Terminal Box

Shaft Cooling Tubes

Stator


Digital MMIS

Fully Digitalized I&C System : DSP Platform 4 Channel Safety/Protection System and Communication 2 Channel Non-Safety System

Advanced Human-Interface Control Room Ecological Interface Design Alarm Reduction Elastic Tile Alarm






RSR RCR TSC ERF

ISO

PIS D

PIS C

PIS B

PIS A

NIS D

NIS C

NIS B

NIS A

PPS D

PPS C

PPS B

PPS A

RTSG D

RTSG C

RTSG B

RTSG A

AIS(PAM B)

AIS(PAM A)

SGCS D

SGCS C

SGCS B

SGCS A

SMS B(ICCMS)

SMS A(ICCMS)


SMS(NIMS)

NIS Y

NIS X

PIS Y

PIS X POCS

PRCS Y

PRCS X

SDCS Y

SDCS X

AIS IPS


PAM-D

SGSC

NSGSC



LDP


MCPMCC MCC



Main Control Panel









RSR RCR TSC ERF

ISO

PIS D

PIS C

PIS B

PIS A

NIS D

NIS C

NIS B

NIS A

PPS D

PPS C

PPS B

PPS A

RTSG D

RTSG C

RTSG B

RTSG A

AIS(PAM B)

AIS(PAM A)

SGCS D

SGCS C

SGCS B

SGCS A

SMS B(ICCMS)

SMS A(ICCMS)


SMS(NIMS)

NIS Y

NIS X

PIS Y

PIS X POCS

PRCS Y

PRCS X

SDCS Y

SDCS X

AIS IPS


PAM-D

SGSC

NSGSC



LDP


MCPMCC MCC



Main Control Panel





Balance of Plant

Schematic Diagram of the Secondary System


Pre-Stressed Concrete Lined with Carbon Steel Plate

Maintains structural integrity of cavity in severe accident

Aircraft Crash Requirements are under legislative process in Korea SMART : designed to have reinforced CV and Aux. Bldg against Aircraft Crash

Reactor Containment Building

Containment Building- Design Pressure : 35 psig- Design Temperature : 240°F


Post Fukushima Action ItemsPost Fukushima Action Items Remark

Aseismic Structural Integrity

•Automatic Reactor Shutdown System @>0.18g Earthquake•Plant Safety System Seismic Design: 0.3g SSE

SSAR ReviseDone

Tsunami Protection •Designed Site Elevation > 10m•Water-tight Doors and Drain Pumps for Emergency Power Sources and Safety Related Equipments (EDG, AAC, Battery, SFSP Cooling System, Circulation Water Intake System….)

@ConstructionSSAR Revise

Additional EmergencyPower Source and Heat Sink

•Install Mobile Emergency Diesel Generator/Battery per each plant site•External Cooling Water Supply Lines to SFSP (+Mobile Water Supply)•Enhance AAC Design Requirements @ Multiple Units Failure (Capacity, Cooling Mechanism, Fuel Storage)

SSAR ReviseSSAR Revise@Construction

Severe Accident Mitigation

•Installation of Passive Auto-Catalytic Recombiners (PAR) and Real-time Hydrogen Monitors

•Containment Depressurization/Exhaust System @Severe Accident•Additional Installation of External Emergency Cooling Water Injection Lines for both Primary/Secondary Systems and Safety Parameter Monitoring System

•Enhance Operator Training Program @ Severe Accident Scenarios

Done

@ConstructionSSAR Revise

@Construction

Others •Enhancement of Emergency Preparedness (Additional Storage of Potassium Iodide, Gas Masks, Filters, RMonitors, RPSuit…)

•Revise Emergency Action Level of Radiation Emergency Plan reflecting earthquake and/or tsunami level

@Construction

@Construction


Technology Validation Program

SMART basically adopts Proven Technologies of Existing PWR

SMART-specific Technologies are being fully Validated Experimental Validation of SMART-specific Design Performance

and Safety Total of 22 Validation Experiments were Selected based on

− PIRT (Phenomena Identification and Ranking Table)− Experts Opinions from Regulation, Industries, Institutes

and Universities Experimental Validation envelop Fuel/Core, TH/Safety,

Mechanics/Components and Digital I&C Software Validation of Key Design Tools and Methods (11)

Core Physics, Core Thermal-Hydraulics, Safety Analysis, ….


SMART Design Code System

Nuclear DesignCASMO/MASTER

Fission ProductAnalysisORIGEN

Shielding DesignMCNP, ANISN,

DORT

Criticality AnalysisMCNP

Core T/H DesignMATRA-S

Core ProtectionSystem Design

SCOPS

Core Monitoring

System Design

SCOMS

Steam GeneratorSizing

ONCESG

PRHRS HX SizingTSCON

Structure DesignANSYS, ABAQUS

CAD/CAEINVENTOR

Safety AnalysisTASS/SMR-S


Technology Validation Program

Technology ValidationTechnology Validation StandardDesign

StandardDesign

Safety Tests Performance Tests Core SET• Freon CHF•Water CHF

Safety SET• Safety Injection•Helical SG Heat Transfer•Condensation HX Heat

Transfer Integral Effect Tests• VISTA SBLOCA• SMART-ITL

Core SET• Freon CHF•Water CHF

Safety SET• Safety Injection•Helical SG Heat Transfer•Condensation HX Heat

Transfer Integral Effect Tests• VISTA SBLOCA• SMART-ITL

Digital MMIS•Control Unit Platform•Communication Switch• Integral Safety System

Digital MMIS•Control Unit Platform•Communication Switch• Integral Safety System

Fuel Assembly•Out-of-Pile Mech./Hydr.

RPV TH•RPV Flow Distribution• Flow Mixing Header Ass.• Integral Steam PZR• PZR Level Measurement

Components•RCP Hydrodynamics•RPV Internals Dynamics• SG Tube Irradiation•Helical SG ISI• In-core Instrumentation

Fuel Assembly•Out-of-Pile Mech./Hydr.

RPV TH•RPV Flow Distribution• Flow Mixing Header Ass.• Integral Steam PZR• PZR Level Measurement

Components•RCP Hydrodynamics•RPV Internals Dynamics• SG Tube Irradiation•Helical SG ISI• In-core Instrumentation

Code Devel/V&V• Safety: TASS/SMR-S•Core TH: MATRA-S•Core Protec./Monitor.

Design Methodology•DNBR Analysis•Accident Analysis

(SBLOCA, LOFA, …) • Integral Rx Dynamics

Code Devel/V&V• Safety: TASS/SMR-S•Core TH: MATRA-S•Core Protec./Monitor.

Design Methodology•DNBR Analysis•Accident Analysis

(SBLOCA, LOFA, …) • Integral Rx Dynamics

Tools & Methods

V&VV&V

Technical ReportsTechnical Reports

Digital MMIS•MMI Human Interface•Control Room FSDM

Digital MMIS•MMI Human Interface•Control Room FSDM

StandardSAR

StandardSAR

Standard Design ApprovalStandard Design ApprovalStandard Design ApprovalStandard Design Approval

Des

ign

Dat

a

Digital MMIS Safety SystemDigital MMIS Control Room


High Temperature & High Pressure T/H Integral Tests

PRHR Tank

SteamLine

Reactor Vessel

RCP

SG

Feedwater Line

PRHRSMakeup Tank

VISTA- ITL

SMART- ITL

VISTA- ITL• Experimental Validation of SBLOCA Phenomena• Height Ratio = 1:2.8, Area Ratio = 1:470,

Operating Parameter Ratio : 1:1• Single Loop

SMART- ITL• Experimental Validation of Integral Performance and Safety • Height Ratio = 1:1, Area Ratio = 1:49,

Operating Parameter Ratio = 1:1• Four Loops


Technology Validation Program- Core & Fuel

Fast-run DNBR Code V&V• Code Characteristics- 4 channel model for SMART core- Non-iterative marching scheme- Lumped channel correction factor- Modular programing

• Code Applications- STDNBR module in SCOPS- POL module in SCOMS- Transient DNBR analysis module

4-Channel analysis model

2'2"

2" 2' 3 4

2" 2' 2"

2" 2' 3 2'

2"

3

3

2"

2"

0.0000.000

0.000

0.0000.000

0.000

11.029

21.013

31.035

41.016

51.017

71.040

61.039

81.037

131.033

91.017

101.019

111.046

121.033

171.046

161.044

151.016

141.013

181.025

191.027

201.029

211.015

220.977

300.938

290.952

280.969

270.985

261.006

250.990

240.990

231.008

310.973

320.969

330.969

340.971

350.961

360.952

370.940

380.932

390.928

Boundary of Fuel Assembly

Rod number &Peaking factor

Subchannelnumber

B) Channel 2 in details

2

1

Hot Assembly: 1/8 of single fuel assembly

Core Average Channel : One fuel assembly

A) 4-channel core representation

Subchannel Code V&V• MATRA-S code- Subchannel integral balance eq.- Homogeneous/Slip Equilibrium- Implicit, marching scheme- Inlet flow/Exit pressure B.C.

• MATRA-S structure

• MATRA-S code validation- Flow & enthalpy distribution tests- Flow blockage tests- Inlet jetting test- Subchannel void distribution tests

CHF Correlation System V&V

• TH Field Analysis: MATRA-S- Optimization of Mixing Coefficient

• Local Parameter CHF Correlation- Correlation Coefficients Optimization

• Limit DNBR- 95/95 tolerance limit- Statistical DNB Design

1st stage (SSAR) 2nd stage (License)

Correlation Conservative model for SSAR BE model for SMART fuel core

MethodEmploying Freon CHF data- Correction factors for SMART- Additional conservatism

Employing Water CHF data- Evaluation of SSAR correltion- Development of BE correlation

Core Protection/Monitoring System V&V

Protection System (SCOPS) Monitoring System (SCOMS)

CRAPOS· CRA Deviation PFs· CRA Positions

CORAPD· Axial Power Distribution· Avg. Node Power

CORVAR· Core Variables Update· LPD/DNBR Calculation

STDNBR· Static DNBR Calculation· Variables for DNBR

Input Signals - CRA Positions

Input Signals - Pump Speed - Tc/Th Temp. - Excore Flux - Pzr Press.

Group PositionsSubgroup Deviation

Pseudo PD(i)Avg. Node Power

Pseudo PD(i)Peaking FactorAvg. Node Power

LPD/DNBR PFsFail Flag

Static DNBRVariable for DNBR

Flow, Temp,Max. Power,

Enthalpy

From CORVAR - Flow - Excore Flux

TRPGEN · LPD/DNBR Trip · Aux. Trip, CWP

If, Necessary

Output toPPS

• CHF SAFDL• Thermal Margin• Transient DNBR• Setpoint analysis• MMIS Algorithm

DNBR Model

Model Validation

CHFData

Analysis

DIFFER-3

MIX HEAT-3

DIFFER-1

PROP-2

VOID

ENERGY

HEAT-2

AREAHEAT-1

FORCE

MIX

DIVGE, DIVSOR DIFFER-4

Enthalpy

Outer Iteration

Axial Sweep

GeometryFuel Temp. Property Crossflow& axial flow

Pressure

SETUP CIUNITSETRI SETPI SETIVRead-In Unit Conversion Print-Out Initialization

MATRA

RESULT

SCHEME

Channel & Rod resultsCHF summary

MAX. TIME?

END

YESNO

Subroutine nameMain functions

Data Selection(sample size, FA geometry, grid design, RH parameters, etc.)

Subchannel TH Analysis(turbulent mixing factor, pressure loss coefficients)

Correlation Form Selection

Coefficient Optimization(nonlinear regression, CHF locations, M/P)

Verification & Validation(visual verification, statistical tests, independent data)

Limit DNBR(95/95 tolerance limit, design margins)

Functional Design Requirements

DB Analysis(Non-RDB)

SCOPS/SCOMS Program

Validation

Uncertainty Analysis

Ind. Programing (MMIS)

Module & Unit Test

DB Analysis(RDB, Addressable)

COREPOW(1 sec) INPUT SIGNAL

Pump SpeedPump DPPZR PressureTBN 1st Stage PCore Inlet Temp.Core Outlet Temp.Feedwater Temp.Feedwater PFeedwater FlowrateSteam Temp.Steam PressureEx-Core Det. SisnalIn-Core Det. SignalCEA Position

SIGVAL(1 sec)

Signal Validation

Test

TBN Pow

Secondary QPrimary Q

RCS Flow

Temp. cal

Determine Reactor Q

Neutron Pow

Peaking factors(Fq,Fr,Fxy)

APS

3D Power distn

Flux tilt ratioAlarm

ASI

POWER3D(10 sec)

vs.

Determine POL

POL(? sec)

DNBR POL

LPD POL

Licensed POL

MARGIN(1 sec)

DNBR-POL

LPD-POL

AlarmAlarm

AlarmReactor Power

Fabrication

Water CHF/Mixing Test

• 5x5 Test Bundle

• Water CHF Test (Stern Lab)

Mixing CHF

Rod arrayRod dia. / pitchHeater type

5x5, full height9.5 / 12.6 mm

Indirect DC heater

ID of test bundleAxial power shapeRadial, hot/cold

M-1Uniform1.68/0.37

C-1/C-2/C-3U/Cos/U1.12/0.93

Freon CHF Test

• Freon-loop CHF Test- Fluid-to-fluid Scaling Law- CHF Data for SSAR CHF Correlation- CHF characteristics at low velocity- Influence of cold wall and grid spacing

• CHF Test Facility (KAERI)

FA Out-of-pile TestFuel Component Test

Tests for Component Selection

• Spacer Grid Impact Test• Top/Bottom Nozzle Structure Test• Debris Filtering Test• Fuel Rod Characteristics Tests• Control Rod Component Tests

2000 m

m

BNStructure

Test

Grid Impact Test Debris

Filtering Test

Grids for CHF Test

IFM grid

Mid grid

■ SpecificationsㆍStrain type sensorsㆍStatic scanner, 140 ch.ㆍ Dynamic scanner, 30 ch.ㆍ Displacement, Force, Strain, Acceleration

measurement

■ TasksㆍFull size PWR FA characterizationㆍVibrationㆍBending stiffnessㆍImpact performance

FAMeCT

■ SpecificationsㆍTwo full size PWR FAsㆍMax operating condition

- Flow rate: 1400 m3/hr- Temp.: 210oC- Pressure: 3.5 MPa

■ TasksㆍHydraulic compatibility

- Flow-induced vibration- Endurance of two different FA (wear)

PLUTO

Core Thermal-Hydraulic Tools and Methods Fuel Performance Tests


Thermal-Hydraulics and Safety

Reactor Pressure Vessel Assembly Flow Distribution Test

Internal Pressurizer/Level Meas. TestFMHA Performance Test

Design Certification forSMART Hydraulic System• 1/5 Scaling

• SG Outlet – Core Inlet Simulation

• Condition : ATM, 60°C

• Test Matrix- 1 or 2 Section SG Braekdown Test- FMHA Outlet Flow-Hole Optimization

• 1/6 Scaling• PZR Internal Structure

Simulation• Condition: 15MPa,

Saturation Temperature

• Test Matrix- Normal Condition- In-surge/Out-surge- Level Measurement Test

• Scale Ratio : 1/5• Simulation of reactor internal structure

• Operating Condition: 1 MPa, 100°C

• Test Matrix- Normal condition- 1 RCP Stop

Level Meter

PRHR Tank

SteamLine

Reactor Vessel

RCP

SteamGenerator

Feedwater Line

PRHRSMakeup Tank

SG and PRHRS Hx Heat Transfer Test Safety Injection Bypass Test

SeparateEffect Test

Integral Test Loop (ITL)

SMART-ITL

VISTA ITL

Safety Certification

• Scale Ratio : 1/49• Design Concept : 4 Loop, 4 Train Secondary side

• Operating Condition (Power/Pressure): < 30% Power, 15MPa

• Tube Modeling Test• Condition :- Normal and Transient

• Scale Ratio : 1/5 • Operationg Condition: < 4MPa, Saturated Temp.

• Scale Ratio Height/Volume) :1/2.8 , 1/473

• Single Loop Simulation

• Operating Condition (Power/Pressure): 100% / 15MPa

Thermal-Hydraulic Performance Tests Safety Validation Tests


Mechanics & Components

Reactor Coolant Pump Performance Test

Verification ofStructural Dynamic

Analysis Method

Verification of Hydraulic Load Analysis Method

Structural Dynamics Test and Analysis Method

HANARO and Capsule Including Alloy 690 Test Specimen for Neutron Irradiation

0.4T Compact Tension Test Specimen

Neutron Irradiation in HANARO

SMART Steam Generator WindedWith Helical Tubes

Alloy 690 Test Specimen

RPV Dynamics & Canned Motor Pump Tests SG Tube Material (A690) Irradiation Test

A B

0.4T CT Tensile

Small Tensile

Hv / M


Component Maintenance

ISI Test Mock-up for Steam Generator

Real Path of In-Core Instrument

ICI sensor Spec.Dia. : 10.7 mm Length: 18 m

Insert Force Analysis ofEddy Current Sensor

ISI (In-Service Inspection) TestUsing Eddy Current Sensor

Eddy Current Sensor Spec.Detector Dia. : 10.5 mmLength: 40 m

Insert ForceAnalysis of ICI

Insertion Test of ICI (In-Core Instrument)

Top-mounted In-core Instrumentation Helical SG In-service Inspection

08.park smart korea

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