march 20, 2010 jae kyu lee - international atomic energy ...jkl).pdf · • design progress: ......

March 20, 2010

Jae kyu Lee

ContentsContentsContentsContentsThe Evolution of Nuclear Power PlantI

Reactor TypeslI

llI Design FeaturesllI

1

ll The Evolution of Nuclear Power PlantThe Evolution of Nuclear Power PlantThe Evolution of Nuclear Power PlantThe Evolution of Nuclear Power Plantl.l. The Evolution of Nuclear Power PlantThe Evolution of Nuclear Power PlantThe Evolution of Nuclear Power PlantThe Evolution of Nuclear Power Plant

Challenge and ResponseChallenge and Response

2

Why Nuclear Energy?Why Nuclear Energy?

● In Nov. 5th 1916, Presented the Einstein’s theory of relativity

y gyy gy

● Amazing and Awesome High Calorific Power

= =

Uranium 1g Oil 9 drums Coal 3 tons*Uranium 1g Oil 9 drums Coal 3 tons

(* 6,000kal/kg Calorific Power Coal Basis)

1’st Anti-Nuclear Movement1’st Anti-Nuclear Movement

● In 1941, Started Manhattan Project by Mr. Oppenheimer in USA

● In Aug, 9 1945, Dropped the atomic bomb at Hiroshima/Nagasaki

- 150,000~246,000 People died, 90% of Buildings destroyed

- The worst incident that the largest people died in the shortest periodThe worst incident that the largest people died in the shortest period

GEN I : Prototype ReactorsFrom soldiers to efficient workers

GEN I : Prototype ReactorsFrom soldiers to efficient workersFrom soldiers to efficient workersFrom soldiers to efficient workers

Mid of 1950 ~ Mid of 1960

1’st Commercial NPP : CALDER HALL-1● Reactor Type: GCR

● Model: MAGNOX

● Gross Capacity: 60MWe

● Construction Start Date: 01 Aug, 1953

Shippingport

Magnox

F i 1● Commercial Operation Date: 01 Oct, 1956

● Permanent Shutdown Date: 31 Mar, 2003

Fermi 1

Dresden

GEN II : Commercial Power ReactorsCommercialized design derived from US naval reactors

GEN II : Commercial Power ReactorsCommercialized design derived from US naval reactorsCommercialized design derived from US naval reactorsCommercialized design derived from US naval reactors

Mid of 1960 ~ Mid of 1990

LWR - PWR, BWR

CANDUCANDU

VVER

AGR

2’nd Anti-Nuclear Movement2’nd Anti-Nuclear Movement

● In March 1979, The Three Mile Island Nuclear Accident in USA

● In April 1986, The Chernobyl Nuclear Accident in Soviet Union

GEN III : Advanced LWRsEnhanced safety and economy

GEN III : Advanced LWRsEnhanced safety and economyEnhanced safety and economyEnhanced safety and economy

Mid of 1990 ~ Present

1) STANDARDIZED DESIGN

2) SIMPLER and MORE RUGGED DESIGN

3) LONGER OPERATING LIFE – 60 Years

4) RESISTANCE TO SERIOUS DAMAGE AP1000

APR1400

SUCH AS CORE MELT ACCIDENTS

APR1400

EPR

VVER1200

ABWR

3’rd Anti-Nuclear Movement3’rd Anti-Nuclear Movement

● In March 2011, Happened the massive earthquake/tsunami in east Japan

● Arose the Fukushima Nuclear Disaster

9

Man-made Disaster? Nature-made Disaster?Man-made Disaster? Nature-made Disaster?

FukushimaDescription

OnaqawaNPP

FukushimaNPPFukushima

Onagawa

Epicenter

Commercial Operation

Started in 1984

Started in 1982

Site Elevation

14.8m10m(1~4 units)

13m(5&6 units)

Tsunami Remakably1~4: Complete

Fl diTsunamiDamage Undamaged

Flooding

5~6: Undamaged

Challenge and ResponseChallenge and Response

C ti E l ti f NPP D i

NPP Safety

Continuous Evolution of NPP Design

Ad d ES & MU3) D i C

Fukushima

Adopted ES & MU3) Design Concept

Chernobyl

Threemile Adopted SAMS2) Design Concept

Adopted MMIS1) Design Concept

1) Man-Machine Interface System 2) Severe Accident Mitigation System 3) Extreme Situation & Multi-Units NPP

The Evolution of Nuclear PowerThe Evolution of Nuclear Power

GEN I : Prototype Reactors

GEN II : Commercialized design derived from US naval reactors

GEN III : Enhanced safety and economy

GEN IV : Sustainable growth and Resistance to weapons proliferation

Source: Generation IV Nuclear Energy Initiative, US DOE Jan. 2006

12

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Reactor TypesReactor TypeslIlI Reactor TypesReactor TypeslI.lI.

PWR / BWR / PHWR / AGRPWR / BWR / PHWR / AGR

13

Reactor TechnologiesReactor Technologies

Common Nuclear Power Reactor Technologies

Fuel Natural U Enriched U Fuel – Natural U, Enriched U Moderator – Water, Heavy water, Graphite Coolant – Water, Heavy water, Gas (CO2, He), Liquid Metal Steam Generator

P iPressurizer MSSV

SimulatorPressurizer MSSV Simulator

Pressureizer Containment Steam Generator (2)

MSLBBreak Simulator

Steam Generator (2)

MSLBBreak Simulator

Safety Injection Tank (4)

Jet Condenser

SGDowncomer

Feedwater

Safety Injection Tank (4)

Jet Condenser

SGDowncomer

Feedwater

Jet CondenserHeat Exchanger

FeedwaterHeat Exchanger

LBLOCABreak Simulator

Reactor CoolantPump (4)

LineJet Condenser

Heat Exchanger

FeedwaterHeat Exchanger

LBLOCABreak Simulator

Reactor CoolantPump (4)

Line

Reactor Vessel

F d tJet Condenser

Containment SimulatorDischarge Line

ContainmentSimulators

Reactor Vessel

F d tJet Condenser

Containment SimulatorDischarge Line

ContainmentSimulators

14

FeedwaterPump

Jet CondenserSpray Pump

SimulatorsFeedwaterPump

Jet CondenserSpray Pump

Simulators

Pressurized Water Reactor (PWR)Pressurized Water Reactor (PWR)

2

1

3

TG side basically not radioactive!

① What kind of Coolant and Moderator is adapted? Water((H2O)

② Where is Steam produced? In the Steam Generator

③ What kind of Fuel is used? Low Enriched Uranium (Approx. 3%)

④ NSSS Supplier: WEC/Toshiba, AREVA/MHI, ROSATOM/ASE, KEPCO/DOOSAN

Boiling Water Reactor (BWR)Boiling Water Reactor (BWR)

3

2

1

TG side radioactive!

① What kind of Coolant and Moderator is adapted? Water((H2O)

② Where is Steam produced? In the Reactor

③ What kind of Fuel is used? Low Enriched Uranium (Approx. 2.5%)

④ NSSS Supplier: GE/Hitachi/Toshiba

Pressurized Heavy Water Reactor (PHWR)Pressurized Heavy Water Reactor (PHWR)

1

2


3

① Where is Steam produced? In the Steam Generator

②② What kind of Fuel is used? Natural Uranium (Approx. 0.7%)

③ What kind of Coolant and Moderator is adapted? Heavy Water((D2O)

④ NSSS Supplier: AECL(Canada)

Advanced Gas-cooled Reactor (AGR)Advanced Gas-cooled Reactor (AGR)

650oC


① Where is Steam produced? In the Steam Generator (inside steel-lined concrete vessel)

② What kind of Fuel is used? Low enriched Uranium (2.5~3.5%)( )

③ What kind of Coolant and Moderator is adapted? CO2 Gas Coolant, Graphite Moderator

④ NSSS Supplier: Developed from Magnox (UK)

18

④ NSSS Supplier: Developed from Magnox (UK)

Reactor Types in OperationReactor Types in Operation

Reactor type Main CountriesNo Gwe

Coolant ModeratorReactor type Main Countries(%) (%)

Coolant Moderator

PWR(Pressurized Water Reactor)

US, France, Korea, Japan,Russia, China,

265(60)

251.6(65)

water water

BWRUS J S d

94 86.4t t

(Boiling Water Reactor)US, Japan, Sweden

(21) (22)water water

PHWR(Pressurized Heavy Water Reactor)

Canada, India, Korea44(10)

24.3(6)

heavy water

heavy water

AGR and MagnoxUK

18 10.8CO graphite

(Gas-cooled Reactor)UK

(4) (3)CO2 graphite

RBMK(Light Water Graphite Reactor)

Russia12(3)

12.3(4)

water graphite

FBRJapan, France, Russia

4 1.0 liquid di

none(Fast Neutron Reactor)

p , ,(1) (0.2) sodium

Other Russia4(1)

0.05(0.01)

water graphite

TOTAL441(100)

386.5(100)(100) (100)

1) GWe = capacity in thousands of megawatts (gross)2) Source: Nuclear Engineering International Handbook 2008

19

Small-Medium Reactors with DevelopmentSmall-Medium Reactors with Development

ModelElectrical Output (MWe)/

Reactor TypeDeveloper

VK 300 300 MWe PWR1) Atomenergoproekt RussiaVK-300 300 MWe PWR1) Atomenergoproekt, Russia

CAREM 27 MWe PWR CNEA & INVAP, Argentina

KLT-40 35 MWe PWR OKBM, Russia

MRX 30 100 MWe PWR JAERI JapanMRX 30-100 MWe PWR JAERI, Japan

IRIS-100 100 MWe PWR Westinghouse-led, international

B&W mPower 125 MWe PWR B&W, USA

SMART 100 MWe PWR KAERI KoreaSMART 100 MWe PWR KAERI, Korea

NP-300 100-300 MWe PWR Technicatome (Areva), France

HTR-PM 105 MWe HTR2) INET & Huaneung, China

PBMR5) 165 MWe HTR ESKOM South AfricaPBMR5) 165 MWe HTR ESKOM, South Africa

GT-MHR 280 MWe HTR General Atomics (USA), Minatom (Russia) et al

BREST 300 MWe LMR3) RDIPE (Russia)

FUJI 100 MWe MSR4) ITHMSO Japan-Russia-USAFUJI 100 MWe MSR ) ITHMSO, Japan-Russia-USA

1) PWR : Pressurized Water Reactor 2) HTR: High-temperature Reactor3) LMR : Liquid Metal Reactor 4) MSR: Molten Salt Reactor5) PBMR: Pebble Bed Modular Reactor

20

5) PBMR: Pebble Bed Modular Reactor

GEN IV ReactorsGEN IV Reactors

Generation IV International Forum (GIF) Generation IV International Forum (GIF)

Chartered in mid 2001, 13 participating countries

Selection of 6 reactor technologies in 2002

U.S.AUnited KingdomArgentina

Goals of GEN IV Reactor Development

Switzerland

South KoreaCanada

Brazil

A CLEAN, SAFE AND COST-EFFECTIVE means

A RESISTANT means to diversion of materials for

WEAPONS PROLIFERATION

South Korea

South AfricaJapanFrance

+ WEAPONS PROLIFERATION

A SECURE means from TERRORIST ATTACKS

A CLOSED FUEL CYCLE SYSTEMSEUROTOM

A means for thermo-chemical HYDROGEN PRODUCTION(GIF: Gen IV International Forum)

21

The History of Reactor Types (PWR)The History of Reactor Types (PWR)

APWR(일) MHI

(미) WEC

AP1000AP600(미) WEC

APR1400

Sys 80 Sys 80+

OPR1000

(미) CE

(한) KEPC0 APR1400

EPR1600N4CP-0CP-1

OPR1000(한) KEPC0

(프) AREVA

(러) AEP/ASE* VVER1200

CP-2

VVER440 VVER1000

Gen Ⅱ Gen Ⅲ

* AEP: Atom Energo Prom ASE : Atom Story Export

1970 1980 1990 2000 2010

The History of Reactor Types (BWR/PHWR)The History of Reactor Types (BWR/PHWR)

(미) GE

(미) GE ESBWR(미) GE

ABWRBWR

(일) Hitachi/Toshiba

ACR700ACR1000

CANDU 6CANDU 9

PHWR(캐) AECL CANDU 9

Gen Ⅱ Gen Ⅲ

1970 1980 1990 2000 2010

Design FeaturesDesign FeaturesIIIIII Design FeaturesDesign FeaturesIII.III.

AP1000/EPR/VVER1200/APR1400/APWRAP1000/EPR/VVER1200/APR1400/APWR

ABWRABWR ABWRABWR

ACR1000ACR1000

24

WEC/Toshiba – AP1000 (PWR)WEC/Toshiba – AP1000 (PWR)

• Size: 1,100 MWeProjects under construction & planned

Design Features

• Design Progress: NRC Certification 2005

• Reactor Design Features

- Standardized design

Simplified construction and operation

• China : Sanmen (2), Haiyang (2)

• USA : Vogtle (2), VC Summer (2)

- Simplified construction and operation

- Longer operation life – 60 years

- Passive safety feature design

45% less seismic building volume- 45% less seismic building volume

Passive RHR System Passive Containment Cooling System

Passive ECCS

Areva – EPR (PWR)Areva – EPR (PWR)

Projects under construction & plannedDesign Features

• Size: 1,600 MWe

• Design Progress: French Design Approval


- Evolutionary design

• Finland: Olkiluoto (1)

• France: Flamanville (1)


- High fuel efficiency

- Flexible operation

- Double containment

• China: Taishan (2)

- 45% less seismic building volume

Olkiluoto 3, Finland Flamanville 3, France

Rosatom/AEP/ASE – VVER1200 (PWR)Rosatom/AEP/ASE – VVER1200 (PWR)

R i L i d (1) N h (1)Size: 1 200 MWe

Projects under construction & plannedDesign Features

• Russia: Leningrad (1), Novovoronezh (1)

• China : Tianwan (VVER1000x2)

• India: Kudankulam (VVER1000x2)

• Size: 1,200 MWe

• Design Progress: The 1’st 2-units under construction



• Turkey: Akkuyu (VVER1200x4)

• Ukraine: Khmelnitskiy(VVER1000x2)

• Finland: Hanhikivi (VVER1200x1)

- High fuel efficiency

- 60 years plant life

• Finland: Hanhikivi (VVER1200x1)

• Hungary: Paks(VVER1200x2)

• Czech: Temelin (VVER1000x2)

KEPCO/DOOSAN – APR1400 (PWR)KEPCO/DOOSAN – APR1400 (PWR)

Projects under construction & planned

Design Features

• Size: 1,450 MWe

• Design Progress: Design Certification 2002

• First unit expected to be operating in 2014


• Korea: Shin Kori (4), Shin Hanul(2)

• UAE: Braka (4)

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- Standardized plant



- Based on System 80+ design features (DC in 1997 by US NRC)

Mitsubishi(MHI) – APWR (PWR)Mitsubishi(MHI) – APWR (PWR)


Design Features

• APWR1700: 1,700 MWe designed by MHI

• Atmea1: 1,100 Mwe designed by MHI/Areva

• Design Progress: Basic design in progress, US DC

application 2008

• Turkey: Sinop (Atmea1 x 2)

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application 2008


- Hybrid safety features


GE/Hitachi/Toshiba – ABWR (BWR)GE/Hitachi/Toshiba – ABWR (BWR)

Projects under operation & construction

Design Features

• Size: 1,300 MWe

• Design Progress: Commercial operation since 1996



• Japan: Kashiwazaki-Kariwa(2), Hamaoka(1)

• Taiwan: Longmen (2)

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- More efficient, Less waste

- Simplified construction (48 months) and operation

1st, 2nd ABWRs Kashiwazaki-Kariwa

Operation start : 1996

3rd ABWR Hamaoka unit 5

Operation start : 2005

AECL/SNC-Lavalin – ACR1000 (PHWR)AECL/SNC-Lavalin – ACR1000 (PHWR)


Design Features

• Size: 1,080 MWe

• Design Progress: Undergoing certification in Canada



• Be ready for discussion with interested utilities

j p


- Light water cooling

- Low enriched fuel

GEN III Reactor Design FeaturesGEN III Reactor Design Features

Country (Developer) Reactor Size

(Mwe) Design Progress Design Features(Improved Safety in All)

• AP-600: NRC certified 1999 FOAKE • Simplified construction and operationUSA(Westinghouse)

AP-1000(PWR)

1100 AP 600: NRC certified 1999, FOAKE. • AP-1000 NRC certification 2005, first units

being built in China, many more planned

Simplified construction and operation• 3 years to build.• 60-year plant life.

France(Areva)

EPR(PWR) 1600

• French design approval.Being built in Finland and France, planned f Chi US i d l d

• Evolutionary design.• High fuel efficiency.

Fl ibl ti(Areva) (PWR) • for China. US version developed. • Flexible operation

Japan(Mitsubishi)

APWR(PWR) 1530

• Basic design in progress, • planned for Tsuruga, • US DC application 2008.

• Hybrid safety features.• Simplified Construction and operation

Korea(KEPCO/DOOSAN)

APR-1400(PWR) 1450

• Design certification 2002, • First units expected to be operating in 2013.• US DC Application is underway

• Evolutionary design.• Increased reliability.• Simplified construction and operation.

Russia VVER-1200 1200 • Replacement under construction for • Evolutionary design.• High fuel efficiency(AEP/ASE) (PWR) 1200 • Leningrad and Novovoronezh plants • High fuel efficiency.• 60-year plant life

US-Japan(GE/Hitachi/Toshiba)

ABWR(BWR) 1300 • Commercial operation in since 1996~7

• In US: NRC certified 1997, FOAKE.

• Evolutionary design.• More efficient, less waste.• Simplified construction (48 months)

Canada(AECL/SNC-Lavalin) ACR 1080 • Undergoing certification in Canada

• Evolutionary design.• Light water cooling.• Low-enriched fuel.

32

Unique Design Features in GEN III ReactorsUnique Design Features in GEN III Reactors

1) Standardization for expediting licensing and reducing construction time and cost

SIMPLER DESIGN for easier operation and maintenance

HIGHER AVAILABILITY for longer operation life - typically 60 yearsg p yp y y

2) Safety adapted not only “active” safety techniques but more “passive” safety measures

REDUCED POSSIBILITY of core melt accidents

RESISTANCE TO SERIOUS DAMAGE such like from an aircraft impact

3) Greater Power production from 1200MWe to 1600MWe

4) Higher Burn-up to reduce fuel use and the amount of waste

33

Lee Jae Kyu PELee, Jae Kyu, PE +82-31-260-1718

[email protected]

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