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transcript
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
SMARTSystem-integrated Modular Advanced ReacTor 3
Contents
SMR Perspectives
Design & Safety Features of SMART
Current (licensing) Status
Summary
SMARTSystem-integrated Modular Advanced ReacTor 4
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
SMARTSystem-integrated Modular Advanced ReacTor 5
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
SMARTSystem-integrated Modular Advanced ReacTor 6
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)
SMARTSystem-integrated Modular Advanced ReacTor 7
Contents
SMR Perspectives
Design and Safety Features of SMART
Current (licensing) Status
Summary
SMARTSystem-integrated Modular Advanced ReacTor 8
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
SMARTSystem-integrated Modular Advanced ReacTor 9
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
SMARTSystem-integrated Modular Advanced ReacTor 10
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)
SMARTSystem-integrated Modular Advanced ReacTor 11
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
SMARTSystem-integrated Modular Advanced ReacTor 12
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
SMARTSystem-integrated Modular Advanced ReacTor 13
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)
SMARTSystem-integrated Modular Advanced ReacTor 14
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
SMARTSystem-integrated Modular Advanced ReacTor 15
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
SMARTSystem-integrated Modular Advanced ReacTor 16
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
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
SMARTSystem-integrated Modular Advanced ReacTor 17
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
SMARTSystem-integrated Modular Advanced ReacTor 18
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
SMARTSystem-integrated Modular Advanced ReacTor 19
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
SMARTSystem-integrated Modular Advanced ReacTor 20
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
SMARTSystem-integrated Modular Advanced ReacTor 21
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
SMARTSystem-integrated Modular Advanced ReacTor 22
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
SMARTSystem-integrated Modular Advanced ReacTor 23
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
SMARTSystem-integrated Modular Advanced ReacTor 24
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
SMARTSystem-integrated Modular Advanced ReacTor 25
Contents
SMR Perspectives
Design & Safety Features of SMART
Current (Licensing) Status
Summary
SMARTSystem-integrated Modular Advanced ReacTor 26
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
SMARTSystem-integrated Modular Advanced ReacTor 27
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
SMARTSystem-integrated Modular Advanced ReacTor 28
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
SMARTSystem-integrated Modular Advanced ReacTor 29
Project Organization - SMART SDA
Technology Validation : $60M Standard Design : $85M
SMARTSystem-integrated Modular Advanced ReacTor 30
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
SMARTSystem-integrated Modular Advanced ReacTor 31
Contents
Introduction
History and Status of the SMART Project
Design Features
Safety of the SMART
Summary
SMARTSystem-integrated Modular Advanced ReacTor 32
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
SMARTSystem-integrated Modular Advanced ReacTor 33
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
SMARTSystem-integrated Modular Advanced ReacTor 34
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 !
SMARTSystem-integrated Modular Advanced ReacTor 36
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
SMARTSystem-integrated Modular Advanced ReacTor 37
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
SMARTSystem-integrated Modular Advanced ReacTor 38
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
SMARTSystem-integrated Modular Advanced ReacTor 39
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
Upper Guide Structure
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)
SMARTSystem-integrated Modular Advanced ReacTor 40
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
SMARTSystem-integrated Modular Advanced ReacTor 41
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
SMARTSystem-integrated Modular Advanced ReacTor 42
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
SMARTSystem-integrated Modular Advanced ReacTor 43
Major Component Design
Steam Generator
Helically coiled once-through HEX Produce Super-heated steam (30℃) Tube material : Alloy 690 Tube inspection (ISI)
Reactor Coolant Pump
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
SMARTSystem-integrated Modular Advanced ReacTor 44
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
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
SMARTSystem-integrated Modular Advanced ReacTor 45
Balance of Plant
Schematic Diagram of the Secondary System
SMARTSystem-integrated Modular Advanced ReacTor 46
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
SMARTSystem-integrated Modular Advanced ReacTor 47
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
SMARTSystem-integrated Modular Advanced ReacTor 48
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, ….
SMARTSystem-integrated Modular Advanced ReacTor 49
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
SMARTSystem-integrated Modular Advanced ReacTor 50
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
SMARTSystem-integrated Modular Advanced ReacTor 51
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
SMARTSystem-integrated Modular Advanced ReacTor 52
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
SMARTSystem-integrated Modular Advanced ReacTor 53
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
SMARTSystem-integrated Modular Advanced ReacTor 54
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
SMARTSystem-integrated Modular Advanced ReacTor 55
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