National R&D for the Development of

Future Nuclear Energy Systems in KOREA

National R&D for the Development of

Future Nuclear Energy Systems in KOREA

Workshop on Advanced Nuclear Power SystmsApr. 16, ’08, Seoul, Korea

Moon Hee Chang

Workshop on Advanced Nuclear Power SystmsApr. 16, ’08, Seoul, Korea

Moon Hee Chang

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ContentsContents

Nuclear Energy PolicyI

Introduction to KAERIII

Future Nuclear Energy System DevelopmentIII

SummaryIV

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I. Nuclear Energy Policy I. Nuclear Energy Policy I. Nuclear Energy Policy

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Long Term Nuclear Energy PolicyLong Term Nuclear Energy Policy

Nuclear Energy Policy– Korean Atomic Energy Commission established the “Direction Direction

to Longto Long--term Nuclear Energy Policy towards the Year 2030term Nuclear Energy Policy towards the Year 2030” in 1994.

– Korean Government (MOST) formulated a long-term national nuclear energy policy, the “Comprehensive Nuclear Energy Comprehensive Nuclear Energy Promotion PlanPromotion Plan” (CNEPP) in 1997 on the basis of the previous Direction and Atomic Energy Act

Nuclear R&D Plan– Korean Government (MOST) devised the “MidMid-- and Longand Long--term term

National Nuclear R&D PlanNational Nuclear R&D Plan” in 1992– The Plan was expanded to the “National Nuclear R&D PlanNational Nuclear R&D Plan” in

1997 with the context of the CNEPP and Atomic Energy Act New Nuclear Policy in 2007– Considering the new trends of nuclear policies worldwide,

Korean Government established the 3rd CNEPP and the 3rd R&D plan in 2006

• They all have a 5 year timeframe from 2007 to 2011

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Vision & Policy Goals (3rd CNEPP)Vision & Policy Goals ((3rd CNEPP))

Contributing to Energy Security, Environmental Protection, Human Welfare and S&T Development

- Nuclear Energy as Prime Driving Force for Future Korea -

POLICY GOALSPOLICY GOALSPOLICY GOALS

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VISIONVISIONVISION

22

33

445566

To secure a nuclear energy supply for a sustainable developmentTo focus on nuclear energy as “energy together with the public” through a improvement of safetyTo promote the export of nuclear industry goods by attaining an international competitivenessTo improve the public health and quality of life through RT utilizationTo establish the infrastructure for an efficient promotion of nuclear energyTo strengthen nuclear diplomacy and international cooperation

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To secure a nuclear energy supply for a sustainable developmentTo secure a nuclear energy supply for a sustainable development111

(1) (1) Expanding nuclear power and strengthening its competitivenessOPR1000+, APR1400, etc.

(2) (2) Obtaining an indigenous proliferation-resistant nuclear energy system

Gen-IV SFR, Pyro-processing

(3) (3) Contributing to the establishment a technology-intensive energy supply system through various uses of nuclear energy

SMART for desalination, Gen-IV VHTR for hydrogen production, Thermonuclear fusion, etc.

(4) Establishing an obvious responsibility management system for(4) Establishing an obvious responsibility management system forradioactive waste disposalradioactive waste disposal

Low and intermediate level radioactive waste disposal facility, etc.

Related Programs (3rd CNEPP)Related Programs ((3rd CNEPP))

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II. Introduction to KAERI II. Introduction to KAERI II. Introduction to KAERI

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Role of KAERIRole of KAERI

Leads Nuclear R&D to support National Nuclear Energy Policy

Reactor System TechnologySMART, SFR, VHTR, FusionReactor System TechnologySMART, SFR, VHTR, Fusion

Radiation TechnologyRT, Bio, Rad. Environ Radiation TechnologyRT, Bio, Rad. Environ

Nuclear Industry Tech.I&C, Chem, Fuel, PIE

Nuclear Industry Tech.I&C, Chem, Fuel, PIE

HANARO Research ReactorRI, PIE, Neu. Beam

HANARO Research ReactorRI, PIE, Neu. Beam

Nuclear Safety ResearchTH, PSA, Environ., Mat.

Nuclear Safety ResearchTH, PSA, Environ., Mat.

Fuel Cycle TechnologyFuel Cycle, Waste, D&DFuel Cycle TechnologyFuel Cycle, Waste, D&D

KAERIR&D

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Major AchievementsMajor Achievements

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R&D VisionR&D Vision

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III. Future Nuclear Energy Systems Development

III. Future Nuclear Energy III. Future Nuclear Energy Systems Development Systems Development

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1970s 1980s 1990s 2000s 2010s 2020s 2030s

Korean Nuclear Reactor Systems– Past and Future

Korean Nuclear Reactor Systems– Past and Future

1st Phase : Gen II–Turn-key base–600 MWe

2nd Phase : Gen III• Standardization• 1,000 MWe

3rd Phase : Gen III+• Evolutionary

PWRs– APR1400– SMART

4th Phase : Gen IV• Revolutionary

– Electricity generation

– Hydrogen production

SMART

APR1400

KSNP

Kori NPP

Gen IV Systems Gen IV Systems

SMART

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Gen III+ (APR1400)Gen III+ (APR1400)

Advanced Power Reactor 1400– Evolutionary PWR

• 1,400 MWe– Features

• Lifetime : 60 years • Construction : 48 mon• CDF : < 10-5/RY• Availability : > 90%

– The 1st unit will be introduced into grid by 2013

APR1400APR1400

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Objective– Develop an Integrated Desalination Plant with SMART

(Thermal Power of 330MWt) both for Electricity Generation and for Seawater Desalination

SeawaterPotable water

Electricity

Desalination Plant

IntakeCondensate

Pump

Brine BlowdownPump

DistillatePump

To Outfall

Steam Supply

FeedSeawater

FinalCondenser

FlashCondenser

Main Ejector

Scale Inhivitor

Feed Water

1st Effect 2nd Effect 3rd Effect Last Effect

Vent Ejector

Steam

PlantSMART

SteamTransformer

System integrated Modular Advanced ReacTor

Plant Data

Power : 330 MWtWater : 40,000 t/dayElectricity: 90 MWe

Gen III+ (SMART)Gen III+ (SMART)

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• System-Integrated PWR

• Physically Inherent Safety Features

• Passive and Active (Hybrid) Engineered

Safety Systems

• Advanced Man-Machine Interface System

Design Characteristics

SMART Development ScheduleSMART Concept and Basic Design (’97 ~ ’02)

SMART-P Project (’02 ~ ’06)

SMART pre-project service (’06.7~’07.6)

• System design optimization

SMART Design Verification ( ~’11)

• Design Certification

RCP

SG

PZR

ReactorCore

SMART Reactor Vessel Assembly

SMART Design Characteristics SMART Design Characteristics

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Steam Generator

CRDM

Main Coolant Pump MCP Test Facility

CRDM Test Facility

Major Components Development Major Components Development

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Safety TestSafety Test– Feed-water Increase– Feed-water Decrease– Loss of Reactor

Coolant– Power Excursion Test

(CRDM Ejection)

Performance TestPerformance Test– Natural Circulation– Power Ascension

Test – T-H Behaviour Under

Heat-up Operation– PRHRS Performance

Analysis

Test Results are Used for Computer Code Verification and System Design

High Temperature and Pressure Test High Temperature and Pressure Test

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Gen IV (SFR) Gen IV (SFR)

Korea Advanced LIquidMEtal Reactor

– Effective uranium utilization and waste minimization

• 600 MWe

– Features• Reactor Type : Pool-Type• Coolant : Sodium• Fuel : Metal (U-TRU-Zr) • Core I/O Temp: 390/545oC• DHR System: PDRC• 2-Loop IHTS/SGS• Net Efficiency: 39.4%• CDF : < 10-6/RY

KALIMER-600 KALIMER-600

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SFR Technology Development Status SFR Technology Development Status

’92

’02

’97

Basic Research

‘91 ‘95 ‘05‘00 ‘10

KALIMER-150Conceptual Design

KALIMER-600Conceptual Design

Gen IV SFRDevelopment

’07

Gen IV SFR Concept

Sodium Experimental FacilitySodium Experimental Facility

’92

’02

’97

Basic Research

‘91 ‘95 ‘05‘00 ‘10

KALIMER-150Conceptual Design

KALIMER-600Conceptual Design

Gen IV SFRDevelopment

’07

Gen IV SFR Concept

Sodium Experimental FacilitySodium Experimental Facility

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Gen IVSFR

System Performance

TestStandard Design

Detailed Design

Proto/Demo Plant

Mock-up Facility

(Nat. U, 10t/Yr)

Eng.-scaleFacility(10t/Yr)

PrototypeFacility

(100t/Yr)

PrototypeFacility

Operation

Pyro-process

Advanced Design

Concept

‘07 ’11 ’16 ’20 ’28’26

Licensing Technology Development

Metal Fuel Irradiation Test

Completion

SFR Development Action Plan SFR Development Action Plan

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Gen IV (VHTR) Gen IV (VHTR)

Nuclear Hydrogen Devel. and Demonstration (NHDD) – Develop and Demonstrate

Nuclear Hydrogen Production Technology using VHTR

– Features • VHTR dedicated to Hydrogen

Production • VHTR: 200MWth Block or

Pebble Core at 950oC• Intermediate Loop • Hydrogen Production: SI

– Nuclear Hydrogen Key Technologies Development since 2004

NHDDNHDD

VHTRVHTR

Intermediate LoopIntermediate Loop

SI Hydrogen Sys.SI Hydrogen Sys.

VHTRVHTR

Intermediate LoopIntermediate Loop

SI Hydrogen Sys.SI Hydrogen Sys.

Reactor

IHX

Reactor

IHX

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NH Key Technologies DevelopmentNH Key Technologies Development

Resolve Technical Challenges for NHDD Project

Fuel(Core)

Natural CoolingFilter

SO3 Decomposor

Cold Air

Warm Air

Graphite(Reflector)

He Purifier

Circulator

IHXHelium950, ~490, ~200oC

Protection Wall

Hot Gas Duct

Isolation Valve

VHTR IS Thermochemical Plant

Fuel(Core)

Natural CoolingFilter

SO3 Decomposor

Cold Air

Warm Air

Graphite(Reflector)

He Purifier

Circulator

IHXHelium950, ~490, ~200oC

Protection Wall

Hot Gas Duct

Isolation Valve

VHTR IS Thermochemical Plant

Iodine-Sulfur Process• Process Integration

• Catalysts, EED, MBR, ..• Process at High P.

Materials & Components• Codification

• Screening of Materials (Metals, Graphite, Ceramics)• Components: IHX, PHE, …

Fuel Manufacturing• Tech. Localization

• QC of TRISO

Design & Safety• Design Tools/Method

• Core at 950oC• Cooled Vessel

• Intermediate Loop• Safety Issues

Fuel(Core)

Natural CoolingFilter

SO3 Decomposor

Cold Air

Warm Air

Graphite(Reflector)

He Purifier

Circulator

IHXHelium950, ~490, ~200oC

Protection Wall

Hot Gas Duct

Isolation Valve

VHTR IS Thermochemical Plant

Fuel(Core)

Natural CoolingFilter

SO3 Decomposor

Cold Air

Warm Air

Graphite(Reflector)

He Purifier

Circulator

IHXHelium950, ~490, ~200oC

Protection Wall

Hot Gas Duct

Isolation Valve

VHTR IS Thermochemical Plant

Iodine-Sulfur Process• Process Integration

• Catalysts, EED, MBR, ..• Process at High P.

Materials & Components• Codification

• Screening of Materials (Metals, Graphite, Ceramics)• Components: IHX, PHE, …

Fuel Manufacturing• Tech. Localization

• QC of TRISO

Design & Safety• Design Tools/Method

• Core at 950oC• Cooled Vessel

• Intermediate Loop• Safety Issues

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Nuclear Hydrogen Devel. Action PlanNuclear Hydrogen Devel. Action Plan

VHTRVHTR

Intermediate LoopIntermediate Loop

SI Hydrogen Sys.SI Hydrogen Sys.

VHTRVHTR

Intermediate LoopIntermediate Loop

SI Hydrogen Sys.SI Hydrogen Sys.

VHTRVHTR

Intermediate LoopIntermediate Loop

SI Hydrogen Sys.SI Hydrogen Sys.

VHTRVHTR

Intermediate LoopIntermediate Loop

SI Hydrogen Sys.SI Hydrogen Sys.

’08 ’15 ’20 ’30 ‘40

Fuel Cell Commer. 12Mt/yr H2 Production

Tech. Development Tech. Demonstration Introduction Commercialization

Fossil Resources and Climate Change• Energy Security• Environment Protection• Economic Growth

Conceptual, Basic Design and Licensing

NHDD Design

Detailed Design, Const., Operation

NHDD Const. & Demon.

Design, Construction and Hydrogen Production

Commercial NH System Construction & Operation

Nuc

lear

Hyd

roge

n Sy

stem

Regulation Research Licensing/Regulation Guideline

Design/Licensing Basis

CP

Reg. Guide.

Risk (Economy, Tech)

Licensability

Market Demand, PA, Business Plan

H2 Demand Increase

OL

VHTR, Mat. & Comp., Fuel, SI H2 ProductionNHDD Key Technologies DevelopmentNHDD Key Technologies Development

Gen-IV ViabilityGen-IV Viability Gen-IV PerformanceGen-IV Performance Major Milestones2020: NHDD Const.2024: NHDD Demon.2020’s: Commercial.

Major MilestonesMajor Milestones2020: NHDD Const.2020: NHDD Const.2024: NHDD Demon.2024: NHDD Demon.20202020’’s: Commercial.s: Commercial.

Hyd

roge

n Ec

onom

y

VHTRVHTR

Intermediate LoopIntermediate Loop

SI Hydrogen Sys.SI Hydrogen Sys.

VHTRVHTR

Intermediate LoopIntermediate Loop

SI Hydrogen Sys.SI Hydrogen Sys.

VHTRVHTR

Intermediate LoopIntermediate Loop

SI Hydrogen Sys.SI Hydrogen Sys.

VHTRVHTR

Intermediate LoopIntermediate Loop

SI Hydrogen Sys.SI Hydrogen Sys.

’08 ’15 ’20 ’30 ‘40

Fuel Cell Commer. 12Mt/yr H2 Production

Tech. Development Tech. Demonstration Introduction Commercialization

Fossil Resources and Climate Change• Energy Security• Environment Protection• Economic Growth

Conceptual, Basic Design and Licensing

NHDD Design

Detailed Design, Const., Operation

NHDD Const. & Demon.

Design, Construction and Hydrogen Production

Commercial NH System Construction & OperationDesign, Construction and Hydrogen Production

Commercial NH System Construction & Operation

Nuc

lear

Hyd

roge

n Sy

stem

Regulation Research Licensing/Regulation Guideline

Design/Licensing Basis

CP

Reg. Guide.

Risk (Economy, Tech)

Licensability

Market Demand, PA, Business Plan

H2 Demand Increase

OL

VHTR, Mat. & Comp., Fuel, SI H2 ProductionNHDD Key Technologies DevelopmentNHDD Key Technologies Development

Gen-IV ViabilityGen-IV Viability Gen-IV PerformanceGen-IV Performance Major Milestones2020: NHDD Const.2024: NHDD Demon.2020’s: Commercial.

Major MilestonesMajor Milestones2020: NHDD Const.2020: NHDD Const.2024: NHDD Demon.2024: NHDD Demon.20202020’’s: Commercial.s: Commercial.

Hyd

roge

n Ec

onom

y

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Gen-IV International Forum (GIF)Gen-IV International Forum (GIF)

* Korea is participating in Projects level.

Gen IVGen IV

Canada, EU, France, Japan, Korea, S. Africa, Switzerland, USA, Russia, China

EU, France, Japan, Korea, USA,

EU, France, Japan, S. Africa, Switzerland

Canada, EU, France, Japan, Korea*

Under discussion of R&D plan(Participating Countries : USA, EU, Japan)

LFR

SFR(5)

SFR(5)

VHTR(8)

VHTR(8)

SCWR(5)

SCWR(5)

Under discussion of forming SSC(Proposing countries to participate : France, USA)

GFR(5)

GFR(5)

MSR

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GIF Projects ParticipationGIF Projects Participation

SFR– System Integration and Assessment – Safety and Operation– Advanced Fuel (Mar, ’07)– Component Design & BOP (Oct, ’07)– GACID (Sept, ’07)

VHTR– Computational Method– Fuel and Fuel Cycle (Jan, ’08)– Material– Hydrogen Production (Mar, ’08)

SCWR– Thermal Hydraulics and Safety– Materials and Chemistry

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IV SummaryIV SummaryIV Summary

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National R&D for the Development of Future Nuclear Energy Systems in KOREA is introduced

– Gen-III+ systems, APR1400 and SMART, for implementation in 2010’s

– Gen-IV Systems, SFR and VHTR, for demonstration in 2020’s

KAERI is taking the lead in the development of SMART, SFR and VHTR