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IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 0 -
Proven Technology for the APR1400’s Development, Licensing and Deployment:Focusing on Thermal-Hydraulic Safety Aspect
Chul-Hwa SONG *
General Project Manager (Director)Thermal-Hydraulics Safety Research Division
Korea Atomic Energy Research Institute
Feb. 1~4, 2010IAEA, Vienna
IAEA INPRODialogue ForumWorkshop
* [email protected] IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 1 -
Contents
APR1400 Overview2
3
5
Process for Development & Licensing
Performance Verification & Evaluation
Summary
1 Introduction
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 2 -
Nuclear Power in KoreaReactors Development in Korea
1. Introduction1. Introduction
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 3 -
Current Status of NPPs in Korea
Yong-gwang6 units
Kori8 units
Ulchin8 units
Wolseong6 units
In OperationUnder Construction
Radioactive Waste Disposal Facility (Under construction)
Radioactive Waste Disposal Facility (Under construction)
Daejeon
From J.J. Ha (2009)
`In Operation
20 units(17,716 MW)
`UnderConstruction
8 units(9,600 MW)
`Planned
10 units(15,400 MW)
(4 OPR1000 & 4 APR1400)
(OPR1000+, APR1400+, APR+)
(8 OPR1000)
35~40 % of Electricityfrom Nuclear
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 4 -
Safe and Economic Operation of NPP
※ Source: Nucleonics Week, Feb. 2009
Capacity FactorCapacity FactorCapacity Factor
Year 2008
World Avg.World Avg.Korea Korea
79.4%
93.3%
Outstanding Performance in NPP OperationShown in Korea !!
Year 2008
93.3
73.1
89.9
66.7
76.1
KoreaKorea Japan Canada Russia France USA
59.2
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 5 -
Reactors Development in Korea
1970s 1980s 1990s 2000s 2010s 2020s 2030s
1st Phase: Gen-II2nd Phase: Gen-II+/III
3rd Phase: Gen-III+
4th Phase: Gen-IV
Turn-key Base- 600 MWe
Standardization - OPR1000 (1,000 MWe)- APR1400 (1,400 MWe)
Evolution. PWRs- APR+ (1,500 MWe)- SMART (330 MWt)
Revolutionary- SFR : KALIMER- VHTR : NHDD- (SCWR)
- ITER
Self-supporting Technologies
Self-supporting Technologies Advanced
TechnologiesAdvanced
Technologies Innovative TechnologiesInnovative
Technologies
1978 2002 2013
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 6 -
2. APR1400 Overview2. APR1400 Overview
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 7 -
APR1400: Design OverviewSafety Goals
Seismic Design : SSE 0.3gCore Damage Frequency : < 10-5/RYContainment Failure Frequency: < 10-6/RYCoping Time for Station Blackout: > 8 Hrs
Performance Requirements and Economic GoalsPlant Lifetime : 60 yearsPlant Availability : > 90%Occupational Radiation Exposure: < 1 man-Sv/RYConstruction Period : 48 Month (for Nth Plant)
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 8 -
Design Improvements in APR1400
APR1400: Design Characteristics
Increased Safety Margin- Reduced hot-leg temp.
M
Stable Operation- POSRVs
ImprovedMaintainability- Integrated head assembly
Improved SG Integrity- Inconel 690 tubes- Reduced hot leg temp.- Increased plugging margin
Severe AccidentMitigation- IVR-ERVC
Enhanced TransientResponse- Increased
Pzr volume
High Reliability & Better Performance :• Safety Injection System: DVI• Safety Depressurization/Vent System:
- IRWST/SpargerMajor Specification of the APR1400
THETA: Separate Effect Test Program• Tests for New Safety Systems Verification• Tests for New Safety Components Develop.
ATLAS: Integral Effect Test Program
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 9 -
APR1400: New Safety Features
Sparger (6x2) In IRWST
FluidicDevice (1x4)
DVI-SIS(1x4)
New Design FeaturesFour trains of the safety injection system with a DVI(direct vessel injection) modeA passive fluidic device (FD)in SIT’s (accumulators)In-containment refueling water storage tank (IRWST)Safety depressurization & vent system (SDVS)In-Vessel Retention (IVR) by ERVC
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 10 -
APR1400: Milestone
Phase-I (’92.12 ~ ’94.12): Conceptual Design- Reactor Type Selection- Development of Top-Tier Design Requirements
Phase-I (’92.12 ~ ’94.12): Conceptual Design- Reactor Type Selection- Development of Top-Tier Design Requirements
Phase-II (’95.3 ~ ’99.2): Basic Design- Development of Design Specifications for NSSS Components- Preparation of Standard SAR (Safety Analysis Report)
Phase-II (’95.3 ~ ’99.2): Basic Design- Development of Design Specifications for NSSS Components- Preparation of Standard SAR (Safety Analysis Report)
Phase-III (’99.3 ~ ’01.12): Optimization and Licensing- Design Optimization; Performance Verification- Detailed Design of Long-Lead Items- Licensing Application of Std. Design (Standard Design Approval: May ‘02)
Phase-III (’99.3 ~ ’01.12): Optimization and Licensing- Design Optimization; Performance Verification- Detailed Design of Long-Lead Items- Licensing Application of Std. Design (Standard Design Approval: May ‘02)
Phase-IV (’07.12 ~ ’13.9): Construction & Comm. Operation- Construction Permit & F/C : ’08. 4, ’08. 10 - Commercial Operation of the 1st Unit: ’13. 9
Phase-IV (’07.12 ~ ’13.9): Construction & Comm. Operation- Construction Permit & F/C : ’08. 4, ’08. 10 - Commercial Operation of the 1st Unit: ’13. 9
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 11 -
DB
Model
DB
APR1400: Comprehensive T-H R&DsComprehensive Thermal-Hydraulic R&D for the APR1400 Development and Licensing Support (’99~’06)THETA : SET ProgramATLAS : IET ProgramMARS : Safety AnalysisSevere Accident Mitigation Measures
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 12 -
3. Process for Development, Verification and Licensing
3. Process for Development, Verification and Licensing
Nuclear Organizations In KoreaProcess for Design Development & VerificationProcess for Licensing & Deployment
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 13 -
Nuclear Organizations in Korea (1/2)
President
Prime Minister
Min. of Edu., Sci. & Tech. (MEST)
Min. of Knowl. & Economy (MKE)
Min. Foreign Affairs & Trade
Nat. Energy Commission
Atomic Energy Comm. (AEC)
Nucl. SafetyComm. (NSC)
KEPCO
KHNPKNFKOPECKPS
KEPCO: Mother company of KHNP, KOPEC, KNF & KPS; electricity transmission & distributionKHNP: Operating NPPsKOPEC: NSSS & AE designKNF: Fuel supplyKPS: Plant maintenanceDOOSAN: Heavy components design & manufacturing
KAERIKINS
KAERI: Comprehensive R&D organization for new reactors & fuels, nuclear safety, radiation applications, etc.KINS: Licensing review, inspection, regulatory research
Science & Technol. Comm.
Governmental Organization
Min. of Environ.
Min. of Strategy & Finance
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 14 -
Nuclear Organizations in Korea (2/2)
Ministry of Education, Sci. & Technol. (MEST)
Manufacturing
Operation &Management Nuclear Fuel
Design & Engineering
Maintenance & Services
Construction
KHNPKHNP
Doosan & BOP Vendor
Hyundai, Daewoo, Doosan, Samsung, etc
Ministry of Knowledge& Economy (MKE)
Key Nuclear Organizations
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 15 -
Process for Standard Design Develop.
Major R&D ActivitiesTesting and Analysis for Performance Verification and Safety Evaluation of New Design Features,Development of Key Technologies and Long-Lead Items, andLicensing Support
Appli
catio
n of S
tanda
rd
Design
App
roval
MEST(PJT Planning,
NPP Licensing)
MEST(PJT Planning,
NPP Licensing)
Licen
sing R
eview
& Appro
val (K
INS)
Exp. Data Base andEvaluation Results
Request ofDevelop. & Testing
Reporting of
R&D Results
Approval of R&D
Plan and Budget
Industries(APR1400 Standard Design
Development)
Industries(APR1400 Standard Design
Development)
KAERI(R&D)
Mid-/Long-Term PJT
KAERI(R&D)
Mid-/Long-Term PJT
MKE(PJT Co-Funding,NPP Operation)
MKE(PJT Co-Funding,NPP Operation)
Phase
I
II
III
‘92. 12-
‘94. 12Selection of Reactor TypeConceptual Design
‘95. 3-
‘99. 2Basic DesignSSAR Development
‘99. 3-
‘01. 12
Design OptimizationLicensing the Standard DesignDevelopment of Long-Lead Items
Period Activities
IV ‘02. 5 Standard Design Approval
MKE : Formerly MOCIEMEST : Formerly MOST
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 16 -
Process for Licensing & Deployments
Developm
ent
Con
struction
Design Developments (’92.12~’01.12)
Phase-I (‘92~’94)Design Require.Design Concepts
Phase-II (‘95~’98)Design Develop.Design Spec. & SSAR
Phase-III (‘99~’01)Design OptimizationLong-lead items Devel.
R&D for ‘Proven Technology’
Std.Design
Approval(’02.5)
Std.Design
Approval(’02.5)
CP:Construct.
Permit(’08.4)
CP:Construct.
Permit(’08.4)
F/C: First Concrete
(’08.10)
Set RV: Rx VesselSet (’10.8)
Commissioning(’13.1~’13.8)
OL:OperationLicensing(~’12.12)
OL:OperationLicensing(~’12.12)
F/L:Fuel Loading
(’13.1)In-PlantTesting
(’12)
Operation
HFT:Hot Func.
Test
CommercialOperation(‘13.9~)
Std. SAR(SSAR)
~ 50 months
As of Jan. 2010
Final SAR (FSAR)
CHT: Cold HydroTest (’12.5)
Construction (’07.9~’12.12)
Pre-Operation
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 17 -
4(A) THETA Program:T-H Separate Effect Tests (SET)
4(A) THETA Program:T-H Separate Effect Tests (SET)
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 18 -
SET: (1) OverviewDVI Test
Focused on Unique T-H Phenomena in a RPV Downcomer Due to the DVI Type T-H Evaluation Relevant to the Safety:
LBLOCA: ECC Bypass, Downcomer BoilingSBLOCA: DVI Line BreakMSLB: Boron Mixing
Fluidic Device (FD) TestSmall-scale Test for the Design Develop.Full-scale Tests for:
Design Confirmation, and Performance Evaluation/Verification
IRWST/Sparger TestIRWST along with the SDVS Actuation for a RCS DepressurizationTo Provide Exp. Data for Evaluating their TH & Mechanical Behaviors
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 19 -
SET: (2) DVI Type of Safety InjectionComplete Set of Experiments for the LBLOCA Reflood
D/C-Core Interaction:(ATLAS)
Degree of SubcoolingReflood RateReflood H/TManometric Oscillation
Phenomena in the Middle D/C:(MIDAS, DIVA)
Breakup of Steam Jet & FilmMulti-D Steam-Water InteractionDirect ECC BypassSweep-outECC Penetration
Phenomena in the Upper D/C:(MIDAS, DIVA, LFS)
Water Jet ImpingementLiquid Film Spreading Entrained Liquid DropletH/T: Steam Condensation
M
Phenomena in the Lower D/C:(DOBO)
Stored Energy ReleaseBoiling H/T at WallBubble RiseCondensation of BubblesDegree of SubcoolingHydrostatic Head
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 20 -
2.1m
ColdLeg
DVINozzle
Downcomer
SI Inflow
Steam Inflow
LBLOCA Reflood Phase
Comprehensive Research for DVISystematic Approach for LBLOCA ECC Bypass (’99~’02)
(2)
Liquid Film Spreading Test
T-H Model/Correlations
Improvements
Air-Water Tests: ECC Bypass
(DIVA)
Steam-WaterTest
(MIDAS]
Steam-WaterTest
(MIDAS]
UPTF-21D(KAERI-GRS)UPTF-21D
(KAERI-GRS)
B.E. CodesEvaluation &
Assess.
B.E. CodesEvaluation &
Assess.
Application&
LicensingReview ofAPR1400,
and
StandardDesign
Approvalof
APR1400
Application&
LicensingReview ofAPR1400,
and
StandardDesign
Approvalof
APR1400
(4)
(5)
(3)
(1)
E.M. MethodAnalysis
E.M. MethodAnalysis
(3)
(1)
Develop. ofthe Scaling
Method
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 21 -
SET: (3) Passive S.I. (FD: Fluidic Device)FD Design Development and its Performance Verification
Development and Performance Verification of the Full-scale Fluidic Device (FD), as a Passive Flow Controller, for APR1400 (’97~’01)
Determination of the characteristic curve of S.I. flow for safety analysisManufacturing Sensitivity Tests: Uncertainties in Manufacturing (‘03~’06)
SI Flow bySIT w/ FD
SI FlowOnly by
SIT
VAPER
SIT
A
B
FD:FluidicDevice
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 22 -
SET: (4) Safety Depressurization Sys.Hydrodynamic Loads on the Internal Structures inside IRWST
Air Clearing LoadCondensation-induced Load
Thermal Mixing in a PoolDirect Contact Condensation of Steam JetsThermal Mixing
Local Hot Spot
SDVS
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 23 -
4(B). ATLAS Program:T-H Integral Effect Test (IET)
4(B). ATLAS Program:T-H Integral Effect Test (IET)
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 24 -
ATLAS: Advanced Thermal-Hydraulic
Test Loop for Accident Simulation
IET: (1) ATLAS ProgramIntegral Effect Test Program: ATLAS
Tests for safety issues and/or interests of APR1400
Reference NPP: APR1400Geometric Scale:
1/2 H, 1/144 A, 1/288 VLoop Configuration:
2 Hot Legs & 4 Cold LegsIntegrated Annular DC
Operating Conditions:Full Press./Temp.Max. 8% of Scaled Power
Simulation of APR1400transients & accidents for assessment & validation of system analysis codes
One of the Three World-class IET
Facilities
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 25 -
IET: (2) ATLAS TestsATLAS: Application & On-going Projects
Verification of safety concerns for APR1400Validation of regulatory & industrial safety analysis codes:
MARS, SPACE Codes
Domestic cooperative programs
DSPDOOSAN: FLB
Int’l cooperative programsOECD/NEA ISP-50:
– DVI-Line BreakCounterpart tests:
– LSTF, PKL, etc. Support of future safety research needs
ISP-50
(SPACE)
(RETAS)
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 26 -
4(C). Severe Accident Research Program
4(C). Severe Accident Research Program
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 27 -
Measures for Severe Acc. MitigationHydrogen Management System (HMS)
Passive Auto-catalytic Recombiners (PAR) limits the average H2concentration
IVR-ERVCIn-Vessel corium Retention through External Reactor Vessel Cooling
Cavity Flooding System (CFS): Cooling and scrubbing the core debris
H2 15 Vol%
H210 Vol%
H2O30 Vol%
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 28 -
5. Summary5. Summary
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 29 -
Current Status of APR1400Two Commercial Projects :
Domestic Pjt. : KNU # 25~26 (SKN #3&4)International Pjt. : UAE # 1~4
Key Milestones: SKN #3&4Design Certification (DC) : May 2002Construction Permit (CP) : Dec. 2007First Concrete (F/C) : Nov. 2008Set Reactor Vessel : Aug. 2010Fuel Loading (F/L) : Jan. 2013#1 COD (SKN #3) : Sep. 2013#2 COD (SKN #4) : Sep. 2014
Another DC Application: US-NRC Pre-Application Review Process : Started from Early 2010
First Conc...
Building/Structural Work
Set RV
Equipment Installation
CHT HFT F/L C/O
’08.11 ’10.08 ’12.5 ’13.01 ’13.09
Doosan Heavy Industry Co., Korea
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 30 -
Construction Site of SKN # 3&4, Korea
Aug. 2009
Oct. 2009
Eng’g Progress (SKN #3): ~45 % of Construction (As of Jan ‘10)
#1 CB
#2 CB
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 31 -
Application of APR1400 R&D Results
• Understanding New T-HPhenomena
• Physical Models/CorrelationsDevelop.
• Resolving Safety Issues• Technology Transfer
Evaluation, Validation and Improvements of the
Best-Estimate Codes forSafety Analysis(MARS, TRACE, etc.)
Support of Advanced
Technologies Developments on
NPP’s
Securing the Base Technologies Searching for International Cooperation Support of
Evaluation/Validation of
Design Codes (E.M.) and
their Localization
Optimized Design
Concepts
Development and
Securing the Key
Technologies for
Advanced LWR’s
Support of APR1400
Standard Design Approval and Construction Permission
APR+SMART
APR1000
• KINS• US-NRC
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 32 -
Concluding RemarksAPR1400 Has Been successfully Developed Based on New Technologies and the Abundant Experiences of the ALWR Design, Construction and Operation in Korea
OPR1000 APR1000 (APR1000+)APR1400 APR+
ARP1400 Has Been fully Verified in Terms of Performance and Safety.
Enhanced Nuclear Safety and Improved Economic CompetitivenessAPR1400 Is now Being Deployed in Commercial Markets:
Two (2) Units are Under Construction, and Another Four (4) Unitsare Planned in Korea.
Capable of Providing Competitive Cost and High ReliabilityFour (4) Units are Planned to Construct in UAE.Design Certification Process in US-NRC Started in Early 2010.
Advancements In Technologies Are Now In Progress for Gen-III+ such as APR1000 (’09~) and APR+ (‘07~) in Korea.
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 33 -
ReferencesC.-H. Song et al., “Thermal-Hydraulic R&Ds for Gen-III+ and Gen-IV Reactors at KAERI: Issues and Future Directions”, NURETH-13, Kanazawa, Sept. 27~Oct. 2 (2009)I.C. Chu et al., ”Development of Passive Flow Controlling Safety Injection Tank for APR1400”, Nuclear Eng. & Design., 238, pp. 200-206 (2008).C.-H. Song, “Thermal-Hydraulic Tests and Analyses for the APR1400's Development and Licensing”, Presented at US-NRC, USA (2007)C.-H. Song, W.P. Baek, J.K. Park, “Thermal-Hydraulic Tests and Analyses for the APR1400's Development and Licensing”, Nuclear Eng. & Technol., Vol. 39 (2007) W.P. Baek, C.-H. Song, et al., ”KAERI Integral Effect Test Program and the ATLAS Design,” Nuclear Technology, Vol. 152 (2005) K.Y. Choi, et al., “Experimental Simulation of a Direct Vessel Injection Line Break of the APR1400 with the ATLAS,” Nuclear Engineering and Technology, Vol. 41 (2009)W.P. Baek, et al., “LBLOCA and DVI Line Break Tests with the ATLAS Integral Facility, “ Nuclear Engineering and Technology, Vol. 41 (2009)J.J. Jeong et al., “Development of a Multi-Dimensional Thermal-Hydraulic System Code, MARS 1.3.1”, Annals of Nuclear Energy, 26, pp.1611-1642 (1999).IAEA, Status of Advanced Light Water Reactor Designs, IAEA-TECDOC-1391 (Chap. 4.9), May 2004H.G. Kim et al., “The Design Characteristics of the Advanced Power Reactor 1400”, ICONE-13, Beijing, China (2005)
IAEA INPRO Dialogue Forum Workshop(IAEA, Feb. 1~4, 2010) - 34 -
AcknowledgementsThis Work Has Been Done by KAERI and Financially Supported Over 10 Years :
Mostly by MOST (Ministry of Science & Technology) and MOCIE (Ministry of Commerce, Industry & Energy) of the Republic of Korea, and Partly by KINS (Korea Institute of Nuclear Safety) and Industries (KHNP, KOPEC, etc.).
The Author deeply Appreciates It for their Technical Contributions from the Colleagues in the THSR Division at KAERI.