status of fast reactor and pyroprocess technology

1 FR09, Kyoto, 7-11 December 2009 Ministry of Education, Ministry of Education, Science and TechnologyScience and Technology

Status of Fast Reactor and Pyroprocess Technology Development in Korea

Ministry of Education, Science and TechnologyMinistry of Education, Science and Technology

International Conference on Fast Reactors and Related Fuel Cycles (FR09), Kyoto, Japan

7 December 2009

Jong-Bae CHOI


Outline

Korean Nuclear Power ProgramISFR & Pyroprocess Development ProgramIISFR Technology DevelopmentIIIPyroprocess Technology DevelopmentIVSummaryV


Korean Nuclear Power ProgramI

I.1 Current Status of NPPsI.2 Status of Spent Fuel StorageI.3 Radioactive Waste Management LawI.4 Reactor Transition Scenario


I.1 Current Status of NPPs

SeoulSeoul

Kori

Ulchin

Wolsong

Yonggwang

Installed CapacityTotal : 72.5 GWeNuclear : 17.7 GWe (24.4%)

Electricity GenerationTotal : 424.4 TWhNuclear : 151.0 TWh (35.6%)

As of December 2008As of December 2008 � In Operation–20 Units

• 16 PWRs (6 OPR1000)• 4 PHWRs at Wolsong

� Under Construction–4 OPR1000–2 APR1400

� Planned by 2022–6 APR1400

Under constructionIn operation

Preparation for ConstructionOPR1000APR1400


I.2 Status of Spent Fuel Storage

NPPSites

Kori

Yonggwang

Ulchin

Wolsong

Total

Storage Capacity(MTU)2,253

2,686

2,328

5,980

13,247

CumulativeAmount(MTU)1,685

1,623

1,294

5,481

10,083

Year of Saturation

2016

2016

2017

2009

As of December 2008Storage Capacity(MTU) 2,253

3,528

2,328

9,155

17,262

Year of Saturation

Expansion Plan

2016

2021

2017

2017

� On-site SF storage limit will be reached from 2016� Decision making process for interim SF storage


I.3 Radioactive Waste Management Law� National Assembly passed the Radioactive Waste

Management (RWM) Law on 26 February 2008– For safe management of radioactive wastes including spent fuels

�Main Contents of the Law– Establishment of a basic plan for RWM with the approval of

the Korea Atomic Energy Commission– Establishment of Korea Radioactive-waste Management

Corporation (KRMC) on 1 Jan 2009– Establishment of RWM fund

• Low and intermediate level radioactive waste• Spent fuel

� Proclamation of KPSE in September 2008 by MKE


I.4.1 Reactor Transition Scenario - KAERI Study

0000

10101010

20202020

30303030

40404040

50505050

60606060

70707070

80808080

2005200520052005 2015201520152015 2025202520252025 2035203520352035 2045204520452045 2055205520552055 2065206520652065 2075207520752075 2085208520852085 2095209520952095

Year

Insta

lled C

apacity (GW

e)

Lifetime

Extension

Advanced PWR

SFR

PHWR

PWR

73.9 GWe

28.8 GWe

�Total electricity generation growth rate- 2006~2030 : Planned - 2031~2050 : 1.0%/year- 2051~2100 : Reduced to 0%/year in 2100

�Nuclear share of 59.0% after 2030


I.4.2 Spent Fuel Inventories - KAERI Study

20062006200620062016201620162016

20262026202620262036203620362036

20462046204620462056205620562056

20662066206620662076207620762076

20862086208620862096209620962096

0000

10101010

20202020

30303030

40404040

50505050

60606060

70707070

80808080

90909090

100100100100

110110110110

SF A

ccum

ulated

(ktH

M)

Year

Cumulative PWR spent fuel

Once Through Cycle

97

Introduction of SFR

2

(Capacity Factor 85%)


SFR & Pyroprocess Development ProgramII

II.1 Long-term Development PlansII.2 Long-term Plan for SFR and PyroprocessII.3 Long-term Plan for Metal Fuel


II.1 Long-term Development Plans� The Korea Atomic Energy Commission approved Long-term

Development Plans for Future Reactor Systems on December 22, 2008– Include Plans for SFR, Pyroprocess and VHTR– Intend to provide a consistent direction to long-term R&D activities

� Detailed Implementation Plan is now being developed–Schedule, deliverables, responsibilities and resources

� Long-term Plans are implemented through Nuclear R&D Programs of the NRF with funds from the MEST


SFRSystem

Performance Test

Standard Design

Detailed Design

Demonstration Plant

Mock-up Facility

(Nat. U, 10t/Yr)Eng.-scaleFacility(10t/Yr)

PrototypeFacility(100t/Yr)

PrototypeFacilityOperation

Pyro-process

Advanced Design Concept

‘07 ’11 ’16 ’20 ’28’26

Licensing Technology Development Metal Fuel Irradiation Test

II.2 Long-term Plan for SFR and Pyroprocess

Viability &

Economics

Licensibility Construction


II.3 Long-term Plan for Metal Fuel

Operation

’07 ’10 ’15 ’20 ’25 ’30

Demo SFRConstruction

Metal Fuel Rod Fab. (U-X-Zr)

Metal Fuel AssemblyFab. (U-X-Zr)

Fuel Fab. in Hot Cell (U-TRU-Zr)

Fuel Fab. Facility Operation (U-TRU-Zr)

Fuel Fab. for Demo. SFR (U-TRU-Zr)

Fuel Slug (U-X-Zr)

Fuel Rod (U-X-Zr) Fuel Assembly

(U-X-Zr)Fuel Assembly with TRU (U-TRU-Zr)

Mass Production of Assembly(U-TRU-Zr)

FDR


SFR Technology DevelopmentIII

III.1 Advanced Concept Design StudiesIII.2 R&D Activities for Advanced SFR


III.1 Advanced Concept Design Studies

� 1200MWe, Pool-type Reactor� Fuel : U-TRU-Zr� Core I/O Temp : 390/545℃℃℃℃� DHR System : PDRC� 2-loop IHTS/SGS� Net Efficiency : 39.4%

Key Design FeaturesKey Design Features

Heat transport system of advanced pool type SFRConceptual NSSS Layout


III.1.1 Core Design

Total

Inner Core 318 Outer Core 306Primary CR 24Secondary CR 12Reflector 96B4C Shield 102IVS 222Radial Shield 120Empty CR 1

1201

Inner Core 54Middle Core 72Outer Core 198Primary CR 18Secondary CR 7Reflector 72B4C Shield 78IVS 84Radial Shield 90Total 673

Inner Core 54Middle Core 72Outer Core 198Primary CR 18Secondary CR 7Reflector 72B4C Shield 78IVS 84Radial Shield 90Total 673

Core Design Parameters Breakeven Core TRU Burner CorePower (MWe) 1,200 600Core height (cm) 80 89No. of fuel regions 2 3Cycle length (EFPM) 18 11Charged TRU enrichment (IC/MC/OC, wt%) 13.16/ - /16.79 30.0 Conversion ratio (fissile/TRU) 1.0/ - 0.74/0.57Sodium void reactivity (EOEC, $) 7.25 7.50

1,200 MWe Breakeven Core 600 MWe TRU Burner Core


III.1.2 Heat Transport System Design

Heat transport system of advanced pool type SFR

�Design studies for improved safety, economics and performance

�Reference design– Pool-type reactor– Superheated steam cycle– Straight double wall tube SG– 2 loop IHTS/SGS

�Design Options– S-CO2 Brayton cycle– Helical double wall tube SG


III.1.3 PDRC Design Features�System Design Features

– Elimination of active components– Operation by natural circulation– No operator action– Major components

• AHX, DHX, expansion vessel and piping

�System Operation– Normal operation

• Minimized heat loss enough to prevent sodium freezing

– Primary pump trip• Decay heat removal by natural circulation

PDRC design concept

Normal Normal operationoperation

PHTS pump PHTS pump shutdownshutdown


III.1.4 Mechanical Structure System�Studies for a cost competitive

large scale SFR– Size optimization – Large size components arrangement

�Design Issues– Feasibility of 2 loop layouts with large size equipments

– Simplified IHTS piping with large piping diameters and SG/pump arrangements

– Integrated components�Structural design evaluation to check design feasibility

Conceptual NSSS Design

Reactor VesselReactor VesselReactor VesselReactor Vessel

- SS316

- OD 14.5m

- Length 19.0m

- Thickness 0.05m

Rx Internals Rx Internals Rx Internals Rx Internals

36 CRDMs2 RP

UISIVTM


•PDRC experiment

Advanced Concept Design Studies

Advanced Concept Design Studies

Development of Basic Technologies

Development of Basic Technologies

Development of Advanced Technologies

Development of Advanced Technologies

•Sustainable and proliferation resistant core

•Na-CO2 interaction test

1971.57 [MW t] 16147.52 kg /s

394.27.60

Na 185.31 a tm 19.98545.0 189.2

19.98 202.77.53

RHRS

183.7364.4

9.2[MW t]

329.66 [MWt] 19.98

389.63044.5[MW t]

31.25 84.81 91.177.40 20.00 7.46

390.0

333.90 [MWt]

15445.9 kg/s71.0%29.0%

13.5 MWPump

TURBINEEff.=93.4% HTR

Ef.=91.7%

CORE

REAC TORVES SEL

COMP. #1E ff.=89.1%

COMP. #2Eff.=87.5%

COOLERCycle E ff. = 42.8 %Plan t Eff.(Gross) =41.2 %Plan t Eff.(Net) = 40.3 %

CO2

IHT S pump

Na-CO 2 HX

353.819.94

508.019.74

1528.7 [MW t] X 2

1751.31 [MWt]

4.3 X 2 MW

7400.2 kg /s X 2Na

1256.22 [MWe]

[C][MPa]

LT REf.=94.6%

0.1094526.0

0.1014364.0

0.16230.0

0.10145.0

26140.8 kg /s

1971.57 [MW t] 16147.52 kg /s

394.27.60

Na 185.31 a tm 19.98545.0 189.2

19.98 202.77.53

RHRS

183.7364.4

9.2[MW t]

329.66 [MWt] 19.98

389.63044.5[MW t]

31.25 84.81 91.177.40 20.00 7.46

390.0

333.90 [MWt]

15445.9 kg/s71.0%29.0%

13.5 MWPump

TURBINEEff.=93.4% HTR

Ef.=91.7%

CORE

REAC TORVES SEL

COMP. #1E ff.=89.1%

COMP. #2Eff.=87.5%

COOLERCycle E ff. = 42.8 %Plan t Eff.(Gross) =41.2 %Plan t Eff.(Net) = 40.3 %

CO2CO2

IHT S pump

Na-CO 2 HX

353.819.94

508.019.7419.74

1528.7 [MW t] X 2

1751.31 [MWt]

4.3 X 2 MW

7400.2 kg /s X 2Na

1256.22 [MWe]

[C][MPa][C][MPa]

LT REf.=94.6%

0.1094526.00.1094526.0

0.1014364.00.1014364.0

0.16230.00.16230.0

0.10145.00.10145.0

26140.8 kg /s

•S-CO2 Brayton cycle system

•Economic improvement of fluid and structural system

•System analysis code development •Sodium technology

development•Metal fuel technologies

Helium Gas VolumeHelium Gas VolumeHelium Gas VolumeHelium Gas Volume

245

225

CORECORECORECORE

190,195,2 00

205,210,2 15220

180

11 5

1 30

1 35

185

110

12 5

MP

120

1 40

Hot PoolHot PoolHot PoolHot Pool

23 0

235

Upper Hot PoolUpper Hot PoolUpper Hot PoolUpper Hot Pool

240

100

145

160

165

155

M P

150

170

110

IHX

280

260

285

IHX

270

250

275

735

835

73 0

83 0

740

840

1 00

0. 0

8. 2

9 .35

1 1.855

3.655

0. 128

0. 29

0.5134

0.5591

0.5075

0.55

0.5034

0.5266

0.4950

0.4950

1

35

34

33

.

.

.

5

4

3

2

36

37

38

1

35

34

33

.

.

.

5

4

3

2

36

Steam OutSteam OutSteam OutSteam Out

Water inWater inWater inWater in

IHTSIHTSIHTSIHTS

PumpPumpPumpPump

700

800

490

690

792

892

79 0

89 0 74 5

84 5

750

850

7 55

8 55

760

860

Surg e

Tank

765

865

772

872

TMDPVOL

9 10

9 50

77 587 5

920960

915

955

9 25

9 65

9 30

9 70

9 35

9 75

TMDPVOL

778

878

780

880

782

882785

885

795

895

0.6

1.19

1 10 100 1000 10000200

300

400

500

600

700

Over flow steady

Over flow start

Coastdown end

Reactor Trip(Outle t T: 555 oC)

LOHS initiation

Temp

eratur

e, o C

Time, s

Core inlet Core outlet

1 10 100 1000 100000.01

0.1

1

10

100

1000

10000

Hot Driver

B4C, IVS

ReflectorsControl Rods

Outer driversInner drivers

Middle drivers

Total

Flow

rate,

kg/s

Time, s

Helium Gas Volume245

225

CORE190,195,200205,210,215

220

180

115130

135185

110

125MP

120

140

Hot Pool230

235Upper Hot Pool

240

100

145160

165

155MP

150

170

110

IHX

280260

285

IHX

270250

275

735835

730830

740840

100

0.0

8.2

9.35

11.855

3.655

0.128

0.290.5134

0.5591

0.5075

0.55

0.50340.5266

0.4950

0.4950

1

353433...5432

363738

1

353433...5432

36

Steam Out

Water in

IHTSPump

700800

490690

792892

790890 745

845

750850

755855

760860

SurgeTank

765865

772872

TMDPVOL910950

775875

920960

915955

925965

930970

935975

TMDPVOL

778878780880782882785

885

795895

0.6

1.19

1 10 100 1000 10000200

300

400

500

600

700

Over flow steady

Over flow start

Coastdown end

Reactor Trip(Outle t T: 555 oC)

LOHS initiation

Temp

eratur

e, o C

Time, s

Core inlet Core outlet

1 10 100 1000 100000.01

0.1

1

10

100

1000

10000

Hot Driver

B4C, IVS

ReflectorsControl Rods

Outer driversInner drivers

Middle drivers

Total

Flow

rate,

kg/s

Time, s

AfterBefore

III.2 R&D Activities for Advanced SFR

•Under-sodium viewing technique

Liquid Liquid Liquid Liquid

WedgeWedgeWedgeWedge

UltrasonicUltrasonicUltrasonicUltrasonic

TransducerTransducerTransducerTransducer

AcousticAcousticAcousticAcoustic

ShieldingShieldingShieldingShielding

TubeTubeTubeTube

10 m10 m10 m10 m

WaveguideWaveguideWaveguideWaveguide

PlatePlatePlatePlate


Pyroprocess Technology DevelopmentIV

IV.1 Pyro-Processing TechnologyIV.2 Pyro-System Engineering Technology


IV.1 Pyroprocessing Research in Korea� Objective

– To develop pyroprocessing technology for reducing spent fuel volume and providing SFR fuel

� Key R&D Areas– An integrated pyroprocessing system with

• 50 kgHM/batch capacity by 2016• Waste minimization• Realization of high-throughput (HT)

– Including• Electrolytic reduction process• HT electrorefining and electrowinning process• Safeguards technology• Pyroprocess mock-up facility design and construction

ElectrolyticReduction Reactor

Electrorefining Reactor

Pyroprocess Mock-up (PRIDE)


IV.1.1 Flow Diagram of Pyroprocessing (KAERI)

TRU fuelfabrication

Decladding & Voloxidation Electrolyticreduction Electrorefining

Electrowinning

Molten saltwaste treatment Uraniumrecovery

Recycleor LLWRecycleor treatment

Cladding material

Low level waste

Off-gastreatment

Sodium-cooledfast reactor

Fission gas

Air

U3O8+(TRU+FP)oxide

(U+TRU+FP)metal

PWR spent fuel

TRU : Transuranic elementsNM : Noble metal elementsFP : Fission products

TRU fuelfabrication

Decladding & Voloxidation Electrolyticreduction Electrorefining

Electrowinning

Molten saltwaste treatment Uraniumrecovery

Recycleor LLWRecycleor treatment

Cladding material

Low level waste

Off-gastreatment

Sodium-cooledfast reactor

Fission gas

Air

U3O8+(TRU+FP)oxide

(U+TRU+FP)metal

PWR spent fuel

TRU : Transuranic elementsNM : Noble metal elementsFP : Fission products


IV.1.2 R&D Issues of Pyroprocessing� Purposes

� Increase throughput� Simple and easy operation mode� Reduce waste volume

� Improvement � Graphite cathode employment to recover U in electrorefining system� Crystallization method applied to recover pure salt from waste mixture

Spent Fuel Voloxidation Electroreduction Electrorefinning Electrowining Fuel Fabrication SFRHMHMHMHM


IV.2.1 System Engineering Technologies


� Integrated Engineering-scale Mock-up Facility by 2011� Argon Cell� Cell Inside Dimension : 40 mL x 4.75 mW x 6.3 mH� Facility Location : 2nd Floor of UCP* in KAERI

A birdA birdA birdA bird’s eye view of PRIDE Facilitys eye view of PRIDE Facilitys eye view of PRIDE Facilitys eye view of PRIDE Facility

* UCP : Uranium Conversion Plant which is now under decommissioning stage.

IV.2.2 PRIDE : PyRoprocess Integrated inactive DEmonstration Facility


IV.2.3 Safeguards Technology Development & International collaboration

Safeguards Technology for ACPF�Enhancement of PR of ACP�Development, Implementation, and Support of a Safeguards System for ACPF�Regional Collaboration for Transparency �Study for Neutron, Gamma, LIBS, SINRD

�Enhancement of PR of ACP�Development, Implementation, and Support of a Safeguards System for ACPF�Regional Collaboration for Transparency �Study for Neutron, Gamma, LIBS, SINRD

ROK-US PCG Collaboration for SG Tech.

NMA Technology for Pyro.

Safeguards Design and Safeguardability Assessment

IngotStorage

U-metal

ElectrolyticReduction

KMP-C

Salt Waste

KMP-FKMP-D

KMP-1NU

Argon Cell2nd Floor

Weig

ht

Voltage/Current

Imag

e

Image

Integrated S/Gs system

UCl3 Preparation

Electro-Refining

1st Floor

Waste Salt Treatment

U melting

VoloxidizerKMP-B

Weight/Radiation

KMP-G

Electro-Winning

U-metal/Waste

Waste

WasteStorage

Ingot/wastestorage

KMP-H

KMP-3

KMP-2

Waste

I ngotKMP-A

KMP-E

IngotStorage

U-metal

ElectrolyticReduction

KMP-C

Salt Waste

KMP-FKMP-D

KMP-1NU

Argon Cell2nd Floor

Weig

ht

Voltage/Current

Imag

e

Image

Integrated S/Gs system

UCl3 Preparation

Electro-Refining

1st Floor

Waste Salt Treatment

U melting

VoloxidizerKMP-B

Weight/Radiation

KMP-G

Electro-Winning

U-metal/Waste

Waste

WasteStorage

Ingot/wastestorage

KMP-H

KMP-3

KMP-2

Waste

I ngotKMP-A

KMP-E

PRIDE Establishment of the Safeguards

System in the PRIDE

ACPF (Lab-Scale Electrolytic Reduction)

Establishment of the SafeguardsSystem in the ACPF

�NDA System Test at INL�Safeguards Study for the KAPF � Safeguardability � Proliferation Resistance Analysis

�NDA System Test at INL�Safeguards Study for the KAPF � Safeguardability � Proliferation Resistance Analysis

ROK-US under the KAERI-10 Program

�Development of Safeguards Approach for Pyroprocessing Plant�Facility Design and Plant Operation Features that facilitate the implementation of IAEA Safeguards

�Development of Safeguards Approach for Pyroprocessing Plant�Facility Design and Plant Operation Features that facilitate the implementation of IAEA Safeguards

ROK-IAEA Collaboration with MSSP

ACPF : Advanced spent fuel Conditioning Process FacilityNMA : Nuclear Material Accounting, SG : SafeguardsPRIDE : PyRoprocess Integrated inactive Demonstration facilityESPF : Engineering Scale Pyroprocessing Facility

PR: Proliferation ResidenceLIBS : Laser Induced Breakdown SpectroscopySINRD : Self Indication Neutron Resonance Densitometer

Establishment of the Safeguards System

in the ESPF

Establishment of Establishment of the Safeguards System the Safeguards System

in the ESPFin the ESPF


V. Summary�Long-term Plan for SFR and Pyroprocess Development was

approved by the KAEC in December 2008– Construction of PRIDE facility by 2011– Standard design approval of demonstration SFR by 2020– Construction of KAPF facility by 2025– Construction of demonstration SFR by 2028

�Activities for the Development of Advanced SFR Concept– Advanced concept design studies– Development of advanced technologies– Development of basic technologies

�Activities for the Development of Pyroprocess Technology– PRIDE will be used for testing the integrity of unit process,

the adaptability of remote operation, and safegaurdability at an engineering scale

status of fast reactor and pyroprocess technology

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