Seismic Design : SSE 0.3g 2. APR1400 Overview2. APR1400

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


Nuclear Power in KoreaReactors Development in Korea

1. Introduction1. Introduction


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


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


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


2. APR1400 Overview2. APR1400 Overview


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)


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


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


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


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


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


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


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


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


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


4(A) THETA Program:T-H Separate Effect Tests (SET)

4(A) THETA Program:T-H Separate Effect Tests (SET)


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


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


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


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


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


4(B). ATLAS Program:T-H Integral Effect Test (IET)

4(B). ATLAS Program:T-H Integral Effect Test (IET)


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


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)


4(C). Severe Accident Research Program

4(C). Severe Accident Research Program


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%


5. Summary5. Summary


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


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


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


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.


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)


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.

Documents

Seismic Design : SSE 0.3g 2. APR1400 Overview2. APR1400