2008. 12. 1

Overview of the Korean Nuclear Fuel Cycle Development and Recycled Uranium Fuel Program in Korea

Bo W. Rhee, J.Y. Jung, J.H. Park

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1

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3

4

5

Backgrounds of Korean Energy Situation

Status of Nuclear Power Generation and Spent Fuel Management in KoreaProposed Nuclear Fuel Cycle in Korea

Recycled Uranium Fuel Program for CANDU in Korea

Conclusion and Future Plans

Contents

1 Backgrounds of Korean Energy Situation

3

Year 2007

� Energy Consumption � World rank 9th

� Oil Consumption � World rank 7th

� Oil Import � World rank 4th

� 2.7 Mb/day

� 2007 Cost of Energy Import occupies 25% of the Total Export

� BP Statistics of World Energy 2007 � Energy balance of OECD countries 2004-2005 (IEA)

KoreaJapan Germany

FranceU.S.

U.K.Canada

20 19

3950

70

87

148

2 427

7

61

78

139

0

20

40

60

80

100

120

140

160

Sel

f-su

ffici

ency

[%]

Energy self-sufficiency (without nuclear power)

Energy self-sufficiency (including nuclear power)

Energy Demand and Supply Status in Korea

96.7% of the Primary Energy Resource is imported (2007)

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� Significant changes in energy sector along with the rapid economic growth during the past two decades

�Significant increase of energy consumption from 38 million TOE in 1980 to 235 million TOE in 2006 (more than 6 times).

�Structural changes in the energy consumption pattern

• Change from non-electric sector to electric sector (from 7.5% to 13.7%).

• Increase of LNG consumption.

• Increase of nuclear share in electricity generation from 9.5% in 1980 to

40.3% in 2006.

� The scarcity of indigenous energy resources

�Heavily depend on imported energy

�The overseas energy dependency continuously has risen from 47.5% in 1970 to 96.9% in 2006.

Energy Situation in Korea

2 Status of Nuclear Generation and Spent Fuel Management in Korea

6

� 20 Units Operation� 16 PWRs (6 OPR1000)

� 4 PHWRs (CANDU)

� 6 Units Under Construct ion� 4 OPR1000

• Shin-Kori : ’05.1 ~

• Shin-Wolsong : ’05.10 ~

� 2 APR1400

• Shin-Kori : ’07.9 ~

� 2 Units Under Licensing Review� 2 APR1400

• Shin-Ulchin고리고리고리고리

울진울진울진울진

월성월성월성월성

영광영광영광영광

(As of End of 2007)(As of End of 2007)(As of End of 2007)(As of End of 2007)

Facility Capacity Facility Capacity

Total :Total :Total :Total : 68.3 GWeNuclear :Nuclear :Nuclear :Nuclear : 17.7 GWe (26 %)

ElectriityElectriity GenerationGeneration

Total :Total :Total :Total : 403.1 TWhNuclear:Nuclear:Nuclear:Nuclear: 142.9 TWh (36%)

Operating

Under Licensing Review

OPR1000

Under Construction

APR1400

Current Status of Korean Nuclear Power Generation

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High Radiation and Heat Generation: ~12kW/t for 1yr cooled LWR FHigh Radiation and Heat Generation: ~12kW/t for 1yr cooled LWR FHigh Radiation and Heat Generation: ~12kW/t for 1yr cooled LWR FHigh Radiation and Heat Generation: ~12kW/t for 1yr cooled LWR FueluelueluelInclude High Include High Include High Include High RadiotoxicityRadiotoxicityRadiotoxicityRadiotoxicity ; takes ~ 3x10+5 yrs to reduce to the level of ; takes ~ 3x10+5 yrs to reduce to the level of ; takes ~ 3x10+5 yrs to reduce to the level of ; takes ~ 3x10+5 yrs to reduce to the level of Uranium OreUranium OreUranium OreUranium OreSemi Indigenous Energy Resource: Includes Semi Indigenous Energy Resource: Includes Semi Indigenous Energy Resource: Includes Semi Indigenous Energy Resource: Includes ----1% 1% 1% 1% PuPuPuPu and 96% and 96% and 96% and 96% UnburntUnburntUnburntUnburnt UUUU

� Annual Output of SF in Korea�700t/yr

CANDUCANDU PWRPWR

� Accum. Rate of SF

� 20 t/Rx20 t/Rx20 t/Rx20 t/Rx----yryryryr� 16 Units16 Units16 Units16 Units� 320 t/yr320 t/yr320 t/yr320 t/yr

� 95 t/Rx95 t/Rx95 t/Rx95 t/Rx----yryryryr� 4 Units4 Units4 Units4 Units� 380 t/yr380 t/yr380 t/yr380 t/yr

.0093Mt.0093Mt.0093Mt.0093Mt.05 Mt.05 Mt.05 Mt.05 Mt

R.O.K.R.O.K.R.O.K.R.O.K.

20502050205020502007200720072007

WorldWorldWorldWorld

.2 Mt.2 Mt.2 Mt.2 Mt

.7 Mt.7 Mt.7 Mt.7 Mt

20502050205020502005200520052005

11,500 t/yr11,500 t/yr11,500 t/yr11,500 t/yr700 t/yr700 t/yr700 t/yr700 t/yr

Characteristics and Generation Rate of Spent Fuel

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Transmutation

by FBR

Transmutation

by FBR

Fuel Materials

Short Half Life

(< 300 yrs)

Hi Radiative, Short Half Life

(< 30 yrs)

High Toxic,

Long Half Life(> few 10+4yrs)

3.5yr IrradU-235 ( 4%)U-238 (96%)

Pre-Irradiation

PuPu

(1.0%)MAMA

(0.1%)

I, I, TcTc

((0.1%)

Cs, Cs, SrSr

(0.5%)

UU--235235

(0.9%)

FP

TRU

FPFP

(4.1%)

UU--238238

(93.3%)

PostPostPostPost----IrradiationIrradiationIrradiationIrradiation

Disposal after

Long Term Storage

Disposal after

Long Term Storage

Direct DisposalDirect Disposal

Re-Use in FBR

Or CANDU

Re-Use in FBR

Or CANDU

MA : Minor ActinidesNp, Am, Cm

LWR Spent Fuel Characteristics and Management

0.0

2.0

4.0

6.0

8.0

10.0

12.0

14.0

16.0

18.0

Fissiles U-235 TRUs Pu

kg/tH

M

경수로경수로경수로경수로

중수로중수로중수로중수로

Comparison of the Fissile Materials

in the Spent Fuel

kg/tHM

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8mon IrradU-235 ( 0.7%)

U-238 (99.3%)

Pre-Irradiation

PuPu

(0.4%)MAMA

(0.0%)

Cs, Cs, SrSr

(0.1%)

UU--235235

(0.2%)

FPFP

(0.7%)

UU--238238

(98.6%)

Post-

Irradiation

I, I, TcTc

((0.1%)

FP

TRU

CANDU Spent Fuel Characteristics and Management

As of now, long term Storage

and Direct Disposal deemed

the best option

10

10000

2020 2040 2060 2080 21002000

20000

30000

40000

50000

60000

70000

80000

90000

Year

Acc

umul

ated

Spe

nt

Fue

l (t

HM

)

9,420t Accumulated as of the end

of ’07, Will exceed the storagefacility capacity from 2016

Dire

ct D

ispo

sal (

PWR

+ 4

CA

ND

U)

� Direct Disposal of SF

� Give Up ReUse of Useful Resource

� Large Size Respositry Needed

� Huge Construction Cost of Repository

� RadioToxicity las longer than 30,000 yrs

� Reuse SF Using SFR

� Safely Managing SF by

Significanlty Reducing Volume,

Heat, Radiotoxicity

“Environment Friendly”

Waste amount =1/20, Radiotoxicity = 1/1000, Size

of the Repository = 1/100

Accumulated Spent Fuel Management Plan

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Mid & Low Radioactive Waste Disposal Facility to be Completed by 2008

Spent Fuel Management Policy will be determined in due time

considering the direction of the National Strategic Policy and

Domestic Technology Development

To be Carried out with Public Consensus thru Enough Discussion

Needs timely Action Considering that the Current Storage will be

full by 2016

Spent Fuel Management Policy of Korea

POLICY: Decision of the 253 Nuclear Committee (2004.12.17)

3 Proposed Nuclear Fuel Cycle in Korea

CANDU Fuels in Korea: Past, Present, Future

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EfficientUse of U

ImproveOP&SA

2000s CANDU Fuel Cycle 2030s 2000s PWR Fuel Cycle 2030s

KALIMERSFRCANDU-6

Fuel

(U, TRU, Impurity FP)

Metal Fuel

CANFLEX-RUFuel

Pyroprocess

CANDU

PWR

Recycled U

SpentFuel

Natural U

CANFLEX-NUFuel

Recycled U in StorageDisposal of Radwaste

CANFLEX-SEUFuel

LVRF Fuel

Enrichment

OREOX

DUPICFuel

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Rise of Uranium Price

and Unstable Market

Uranium Price TrendUranium Price TrendUranium Price TrendUranium Price Trend

Efficient Use of the Uranium Using SFREfficient Use of the Uranium Using SFREfficient Use of the Uranium Using SFREfficient Use of the Uranium Using SFR

More than 100 times as efficient as PWR Only

※※※※ Source: Gen IV Roadmap, Fuel Cycle Assessment Repor t(2002)

※※※※ SourceSourceSourceSource: : : :

http://http://http://http://www.uxc.com/review/uxc_g_price.htmlwww.uxc.com/review/uxc_g_price.htmlwww.uxc.com/review/uxc_g_price.htmlwww.uxc.com/review/uxc_g_price.html) ) ) )

Effective Utilization of the Useful and Recyclable Resources

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Reduction of PWR SF Disposal Amount

70,000t →→→→ 4000t

Drastic Reduction of the Spent Fuel Output

4 Recycled Uranium Fuel Program for CANDU in Korea

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� 43 elements, 2 pin sizes (13.5 mm, 11.5 mm)

�20% reduction in linear element power (compared to 37-element)

� CHF enhancement pads

�3 to 9 % increase in critical channel power (compared to 37-element)

� Compatible with existing fuel handling system

� Benefits for NU and RU

Basics of CANFLEX

0o30o

60o

90o

120o

150o 180o

210o

240o

270

300o

330oWear PadCHF Enhancement ButtonSPACER

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3

4

5

6

7

8

910 11 12

13

14

15

16

17

18

1920

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2223

24

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26

2728 29

30

31

32

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3435

36

37

3839

40

41

42

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Cross-section of a CANFLEX Bundle

Linear Power Distribution Along the Radial Direction

CANFLEX FUEL DESIGNCANFLEX FUEL DESIGNCANFLEX FUEL DESIGNCANFLEX FUEL DESIGN<CANFLEX = <CANFLEX = <CANFLEX = <CANFLEX = CANCANCANCANDU DU DU DU FLEXFLEXFLEXFLEXIBLE IBLE IBLE IBLE

FUELLING>FUELLING>FUELLING>FUELLING>

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Development of CANFLEX-NU

Development : KAERI-AECL Joint Research (1991 ~ 1998)

Validation Test : In-reactor and Thermal-Hydraulic Test

Demonstration Irradiation (DI)

� CANFLEX-NU Bundle NRU Irradiation Test (1994 ~ 1997)

� CANFLEX-NU Bundle Water CHF Test (1999 ~ 2000)

� Canada

•24 Bundle Demonstration Irradiation in Pt. Lepreau (1998~2000)

� Korea

•Licensing for the CANFLEX-NU Design and Fabrication (1999, MOST)

•Licensing for DI of the 24 CANFLEX-NU Bundle in Wolsong Unit 1 (2002, MOST)

•DI of the 24 CANFLEX-NU Bundle in Wolsong Unit #1 (2002~2004)

•Visual Inspection and PIE Test for the DI Fuel (2003~2004)

CANFLEX-NU Program in Korea was suspended at 2004 but

now expect to come back to use the CANFLEX in Korea.

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�Aging of Wolsong Unit 1

� The first commercial CANDU reactor in Korea

• Has been operating for more than ~ 20 years at that time.

• Was expecting decrease of operating margin due to aging.

� Need to compensate the decreased operating margin

�Switching from 37-element fuel to CANFLEX-NU

� 43 and dual sized elements with buttons.

� Considered as the first solution to solve the aging problem.

� Benefits of a full core implementation of CANFLEX-NU.

• Enhancing the operational efficiency and safety margin due to a reduction of the

max. linear power by about 20 %.

• Enhancing CCP by appendages (buttons) of about 5 %.

Rationale of CANFLEX-NU DI in Wolsong Unit 1

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Development of CANFLEX-RU

Objectives

Preliminary Results

Expectation in Future

� Reactor Physics Analysis

� Fuel Element/Bundle Design

� Thermal-Hydraulic Analysis

� Safety analysis for some accident events

� Economic Benefits of CANFLEX-RU using in CANDU� Detail Analysis of Core Physics, Fuel Performance,

Thermal-hydraulics, Design V&V, In-pile & Out-pile Tests. etc.

� Safety Analysis� DI & Commercialization

� Feasibility Study of CANFLEX-RU (2000 ~ 2003)

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Characteristics of CANFLEX-RU

� Utilization of Advantages of CANFLEX-NU

• 43 elements

• Two types of elements

• Button � CHF Increase

� Utilization of Advantages of CANFLEX-NU

• 43 elements

• Two types of elements

• Button � CHF Increase

� Use Recycled Uranium

• Almost Doubled Burnup than NU

• Reduction of Uranium Use : ~50 %

• Reduction of Spent Fuels : ~50 %

� Use Recycled Uranium

• Almost Doubled Burnup than NU

• Reduction of Uranium Use : ~50 %

• Reduction of Spent Fuels : ~50 %

Reduction of Element Linear Power Reduction of Element Linear Power

Decrease Fission ProductDecrease Fission Product

CCP EnhancementCCP Enhancement

CANFLEX Fuel Bundle

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Preliminary Results of CANFLEX-RU

� CANFLEX-RU Fuel Element and Bundle Design

� CANFLEX-RU Reactor Physics

Analysis

� CANFLEX-RU Channel Thermal-Hydraulic

Analysis

� CANFLEX-RU Fuel Safety

Analysis

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� Thermal and Mechanical Analysis of Fuel Element� Element Linear Power-Burnup Envelop� Element Pressure, Pellet Temperature, Sheath Deformation� Sheath Oxidation, Sheath Collapse, etc.

� RU Powder Characteristics� Physical and Chemical Properties� Isotope Content, Density, Grain Size, Dose Rate, etc.

� Compatibility with the Existing CANDU-6 System� Primary Heat Transport System

– PT Wear & Corrosion, Spacer Wear, Endplate Fatigue, etc.� Fuel Channel

– Clearance between Bundle String & Shield Plug, Bearing Pad Wear,etc.

– Fuel Handling Machine– Endurance Test (Burnup Increase), Bundle Static & Impact Strength

Fuel Element and Bundle Design (1)

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� Physics Analysis Methodology

� Code Verification to RUFIC Fuel : WIMS-AECL, MULTICELL, Dragon,

RFSP

� Time-average Core Analysis

� Refueling Scheme : 2/4 Bundle Shift

� Uranium Content Effect on the Core Power & Burnup Distribution

� Liquid Zone Controller, Adjuster Rod, Absorber, Shut-off Rod, etc.

� Analysis for Equilibrium and Transient Core

� Refueling Simulation

� Equilibrium & Transient Core based on the 4 Bundle Shift

Reactor Physics Analysis (1)

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� Review Thermal-hydraulic Criteria

� Pressure Drop, Critical Power Ratio,

� Flow Stability, Channel Flow, Pellet Temperature, etc.

� RUFIC Fueled Channel� Channel Flow & Quality Distribution, CCP & CCP Ratio

Distribution� Effect of PT Creep, Height Effect of Bearing Pad

� Mixed of 37-element and RUFIC Fueled Channel

� Sub-channel Analysis

Thermal-hydraulic Analysis (1)

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� LB LOCA

� LB LOCA without ECC

� Feeder Break Accident

� Flow Blockage Accident

� End-fitting Failure Accident

� Pressure Rupture Accident

Safety Analysis

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Summary

Enhancement of Operating and Safety Margin for an Aged CANDU ReaEnhancement of Operating and Safety Margin for an Aged CANDU ReaEnhancement of Operating and Safety Margin for an Aged CANDU ReaEnhancement of Operating and Safety Margin for an Aged CANDU Reactorctorctorctor

Increase Operation Increase Operation Increase Operation Increase Operation MarginMarginMarginMargin���� Compensate Power ReductionCompensate Power ReductionCompensate Power ReductionCompensate Power Reduction

Enhancement of EconomyEnhancement of EconomyEnhancement of EconomyEnhancement of Economy

Reduce Fuel Cycle CostReduce Fuel Cycle CostReduce Fuel Cycle CostReduce Fuel Cycle Cost

Natural Synergism between PWR and CANDUNatural Synergism between PWR and CANDUNatural Synergism between PWR and CANDUNatural Synergism between PWR and CANDU

Partial Closed Fuel CyclePartial Closed Fuel CyclePartial Closed Fuel CyclePartial Closed Fuel Cycle

Establishment of Advanced CANDU TechnologyEstablishment of Advanced CANDU TechnologyEstablishment of Advanced CANDU TechnologyEstablishment of Advanced CANDU Technology

Expectation From “REUSE” Program

Utilization of Recycled Uranium with CANFLEX in

CANDU

5 Conclusion and Future Plans

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� Considering the scarcity of indigenous energy resources, and Heavy Dependency on the imported energy, it is inevitable to develop a clean, self-sustaining and environment friendly ENERGY Source

� Nuclear Energy is emerging as the most practically via ble option for the Demand for the Green Society.

� “Environment Friendly Spent Fuel Management Technolog y is deemed to be a MUST for Nuclear Power Prosperity.

� Sodium Fast Reactor plus Advanced Fuel Cycle Techno logy is deemed to be appropriate for Drastically reducing the S pent FuelProblems

� Recycled Uranium Fuel Cycle for CANDU and DUPIC fuel cycle, with Pyroprocessing is thought to be drastically reduce the Accumulated Spent Fuel

Conclusion and Future Plans