korea atomic energy research institute
TRANSCRIPT
Korea Atomic Energy Research Institute
17th INPRO Dialogue Forum on Opportunities and Challenges in Small Modular Reactors, 2-5 July 2019, Ulsan, Republic of Korea
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365MWth (~100MWe) Integral PWR Electricity & Steam Generation, District Heating or Desalination
Seawater Potable
Water
Electricity
Desalination Plant
Intake Facilities Steam
Electricity and Water for a City of 100,000 ~ 500,000 Population
Steam Transformer Hot Water
Heat pipe
District Heating
Seawater Desalination
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Integral reactor coolant system – elimination of large bore pipe connections resulting in the removal of LBLOCA
Passive safety features – No requirement of active controls and operator intervention to cope with malfunctions and safety events
Competitive electricity generation cost - Lower generation cost than other energy sources (coal, gas…)
Construction and maintenance cost saving - Multiple construction at small grid system (shorter transmission line)
Power supply for small grid system Seawater desalination District heating
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Joint Design of FOAK SMART by PPE (Pre-Project Engineering)
Joint Export of advanced SMRs based on IP Ownership Sharing
Joint Implementation High-Level Commitments
A Robust Project Supported by KSA-ROK Governmental Agencies
H.E. President Moon & H.E. Minister
Al-Falih(‘18.5)
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7/12
KAERI President
V. President
ALARA QA SMART Development
HCB NSSS Design SMART Design
Construction Preparation
BOP Design
Fuel Design
Component Design & Test
Design Integration
Core Design
Fluid Sys. Design
Mechanical Design
MMIS Design
Safety Analysis
PSA
Severe Accident
Validation Test
CRT Support
Core Design
F. S. Design
Mech. Design
MMIS Design
Safety Analysis
PSA & S.A. TH Test
KAERI
External Organization
KSA Trainee
Steering Committee
Project Control Committee
HF
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<SMART HCB Program Structure>
<SMART OJT Program >
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Engineers who completed CRTs and OJT are eligible for design work(OJP) with duly processed job qualification as per the SMART QAP requirements
10/12
Satisfies state-of-the-art Korean regulatory norm
Preliminary Accident Management Program was also developed
VTT has reviewed and confirmed the quality and depth of PSAR
The total number of design documents and drawings is ~ 9,000
The number of whole packages (MOM, memo, etc.) is more than 12,000
Includes essential design methodology of NSSS (core, fluid, mechanical, etc.)
KAERI delivered SMART PPE package to K.A.CARE at the end of February, 2019
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‘15 ‘16 ‘17 ‘18 ‘19 ‘20 ‘21 ‘22 ‘26 ‘23 ‘24 ‘25
SDCA Launch
EPC Contract
COD of SMART PPE
SMART Design Technology SMART Construction (Including CP Licensing) ◦ KSA- ROK Joint SMART EPC ◦ Detail design (DL1) and FSAR ◦ Operator training
◦ To confirm safety of SMART design
SDCA Licensing Review
◦ Basic design (DL2) and PSAR for KSA construction ◦ Technology validation program
◦ Innovative technologies (incl. compact steam generator and internal CRDM)
Joint R&D for Advanced SMART
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Standard Design Approval of SMART100
KHNP 3 July 2019
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Schedule
Design Characteristics
Industrial Standards
R&D Activities and Expected Effects
Contents
Nuclear Power Plants in Korea
Project Overview
Pre-Project Engineering & Construction Plan
Organization
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In Operation 24 Units 22,529 MW
Under Construction 5 Units 7,000 MW
Wolsong 1,2,3,4 (PHWR)
Kori 2,3,4 Shin-Kori 1,2,3
Shin-Hanul 1,2 Hanul 1,2,3,4,5,6
Hanbit 1, 2, 3, 4, 5, 6
Shin -Wolsong 1,2
Shin-Kori 4,5,6
Nuclear Power Plants in Korea
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Project Overview
Performing the SDA of SMART100 to replace with complete passive safety systems
Reducing the burden of the construction permit
Complementary design to satisfy regulatory requirements Creating Documentation for SDA application in accordance
with the Nuclear Safety Enforcement Law
January 2019 to December 2021(36months) Application of SDA : October 2019
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Pre-Project Engineering & Construction Plan
Technology Development
SMART Development Pre-Project Engineering
1997 ~ 2015 3 Yr 5~6 Yr
Commercialization
SMART Standard Design Technology Validation Licensing Safety Enhancement for Post Fukushima Action Plan
Korea & KSA
FOAK Plant Construction
2 FOAK Plants Construction Licensing (SDA, CP, OL)
KHNP-KAERI-KSA Korea
FOAK Engineering Design K.A.CARE HCB PSAR
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Organization
PROJECT MANAGEMENT
KHNP
Technical Coordination
KHNP/KAERI
KAERI K.A. CARE
CONTRACTORS
FnC : CPRSS BHI : CPRSS Lid POSCO : BOP HGS : RCP SOOSAN : MMIS
KEPCO NF
NSSS DESIGN
KEPCO E&C
(SD)
BOP DESIGN
KEPCO E&C (AE)
COMPONENT DESIGN
DOOSAN
FUEL DESIGN
HGS: Hyosung Good Springs
KHNP KAERI
Management Cooperation
K.A.CARE/KHNP
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Schedule
2019 2020 2021
Complementary Design
SDA Evaluation/Response to RAI Review
Rev.0 Rev.1
Completion of SDA Review
Oct. 2019 Aug. 2021 Oct. 2021
Apr. 2019 Sep. 2019
Additional Works
Documentation
Acquisition (June 2022)
SDA Application
Feb. 2019
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Characteristics
1st SDA SMART100
Site Generic Site(Korea) Generic Site(KSA)
Safety Systems Active & Passive Passive
Plant Power 330 MWt 365 MWt
Regulation & Standard Korean Norm Korean Norm
Design Level DL2 DL2
• Passive Safety System • DC Batteries(No EDGs) • Simple Emergency Operation • Small Exclusion Area Boundary
Better Safety Less Cost
• Power Increment • Smaller Building Volume • Less and Smaller Components
Engineering Features
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Item 1st SDA SMART100
Electric Power >100 MWe >110 MWe
Cycle Length 36 Month 30 Month
Steam Generator Flow rate 250.8 kg/s Flow rate 294.7 kg/s
Heat Transfer Height 478 cm Heat Transfer Height 439 cm
Reactor Coolant Pump Design Flow 3,240 m3/h Design Flow 3,840 m3/h
Passive Residual Heat Removal System (PRHRS)
4 trains (36 hrs) 4 trains (72 hrs) 2 valve trains for each
Safety Injection System 4 100% Active 4 Passive Core Makeup Tank (CMT) & Safety Injection Tank (SIT) sets
Depressurization System 2 Active SDS (Safety Depressurization System)
1 Stage 2 Trains (2 Lines for each) Automatic Depressurization System (ADS) actuated by CMT & SIT Levels
Containment Spray System 2 100% Active Containment Pressure and Radioactive Suppression System (CPRSS)
Changes from 1st SDA
Characteristics
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Items 1st SDA SMART100
Shutdown Cooling System 2 Active (Safety) 2 Active Function (Non-Safety) using SG and CCWS
Emergency Power Source 2 100% Safety System DC Batteries (4 Trains), Non-Safety DGs
Primary Coolant Pre-heating Auxiliary Heater Preheating system
Startup Temperature 200 °C Startup Temperature > 300 °C
Automatic Seismic Trip System (ASTS)
N/A ASTS
MMIS Safety I&C System DSP (Digital Signal Processor) based Platform
Programmable Logic Controller (POSAFE-Q PLC)
Chemical & Volume Control System
Use Boron Recovery System Remove Boron Recovery System
Radiation Source Term TID-14844 Alternative Source Term (NUREG 1.183)
Reactor Pressure Vessel Head Shape: half hemisphere Head Shape: Cut-hemisphere
Total Height : 18.50 m Total Height: 16.83 m
Re v is io n s f r o m 1s t SDA
Characteristics
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Technology Standards
LAW AND GUIDELINE
Application of the Korean Law and Guideline in accordance with the Code Cutoff Date(April 30, 2019)
Application of the USA license requirements in a supplementary manner
INDUSTRIAL STANDARDS
Korea Electricity Power Industry Code(KEPIC), published in 2005 plus the code addenda published in 2006, 2007, 2008, 2009 The Nuclear Safety and Security Commission referrers the KEPIC (until
April 30, 2019)
CHARATERISTICS OF INTEGRATED REACTOR
In case of inappropriate circumstances to apply the law, guideline and industrial standards Discussion with the regulatory body to deal with reflecting unique
characteristics of integral reactor
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Evaluation of thermal hydraulic behaviors of CVCS etc.
Development of CVAP methodology Modeling of RHSA integrity Evaluation of Post LOCA dose and TID of PSIS components
Analysis of Jet impingement zone of influence
Assessment of Blast Wave load and resonance Analysis of piping and
environmental fatigue RCAB structural analysis and
calculation sheet according to construction phases
Documentation of the fuel performance Seismic performance verification of the
end of the fuel life Performance test of anti-corrosion of
HANA Cladding and fuel rod Conceptual design of transportation
vessel
Design and manufacturing of CVAP miniature model
Secure safety of the CRDM design Integrity evaluation of S/G tube Design and integrity evaluation of the
Main equipment(RV, CRDM, etc.)
Fuel
NSSS
BOP
Equip
R&D Activities and Expected Effects
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Acronyms
SMART SDA EUR FOAK PSAR KINS MMIS PPE SSAR CVCS CVAP RHSA LOCA TID PSIS CRDM RCAB RV
: System-integrated Modular Advanced ReacTor : Standard Design Approval : European Utility Requirements : First Of A Kind : Preliminary Safety Analysis Report : Korea Institute of Nuclear Safety : Man Machine Interface System : Pre-Project Engineering : Standard Safety Analysis Report : Chemical and Volume Control System : Comprehensive Vibration Assessment Program : Reactor Head Structure Assemble : Loss-Of-Coolant Accident : Total Integrated Dose : Passive Safety Injection System : Control Rod Drive Mechanism : Reactor Containment Auxiliary Building : Reactor Vessel
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