Nuclear Fuel Cycle and sustainable development ...

Nuclear Energy Division FJOH Summer School, Aug. 27, 2004 1

Frederic JOLIOT & Otto HAHN Summer School on Nuclear Reactors “Physics, Fuels and Systems”

Nuclear Fuel Cycle and sustainable development : strategies for the future

Dr. Jacques BouchardHead of the Nuclear Energy Division

French Atomic Energy Commission (CEA)[email protected]


Why should Nuclear Energy play a major role ?

•• PromisingPromising assetsassetsto to produceproduce HydrogenHydrogen

•• No CO2 No CO2 emissionsemissions andand nonocontribution to Global contribution to Global WarmingWarming

•• EnhancesEnhances thethe energyenergy supplysupply securitysecurity

•• SafetySafety improvementsimprovements in 3rd in 3rd GenGenreactorsreactors are are alreadyalready significantsignificant

•• An An alreadyalready competitivecompetitive energyenergysourcesource

CO2 emissions in 2001 / GDP


tC/1000 US$

0,00

0,05

0,10

0,15

0,20

0,25

Czech

Rep

ublic

Poland

Austra

lia

Slovak

Rep

ublic

South

Korea

United

Stat

esCan

ada

Greece

Finland

Hunga

ryTurke

yBelg

iumGerm

any

Mexico

Netherl

ands

New Zea

land

Luxe

mbourg

United

King

dom

Irelan

dSpa

inDen

markJa

pan

Portug

alAus

tria Italy

Norway

Franc

eIce

land

Sweden

Switzerl

and

Total O

CDE

France : 27th /30

Source : AIE/OCDE, 2000


Sustainable Development Vision Scenario (IEA 2003)

0

5

10

15

20

25

30

1990 2000 2010 2020 2030 2040 2050

Wor

ld P

rimar

yE

nerg

yS

ourc

es (G

toe)

6

6,5

7

7,5

8

8,5

9

Wor

ld P

opul

atio

n (B

illio

ns)

Other RenewablesBiomassNuclearGasOilCoalPopulation

Source IEA : Energy to 2050 -Scenarios for a Sustainable Future


Towards a revival of nuclear ?

USA : “The NEPD Group recommends that the President support the expansion of nuclear energy in the United States as a major component of our national energy policy.”Report of the National Energy Policy Development Group, May 2001

Europe « … the need to keep nuclear power at the heartof Europe’s energy mix »European Parliament resolution, Novembre 2001

The Evolution of Nuclear Power


Advanced Advanced ReactorsReactorsCurrent Current

ReactorsReactors

Generation I

Generation II

1950 1970 1990 2010 2030 2050 2070 2090

Generation III

FirstFirstReactorsReactors

UNGGCHOOZ

REP 900 REP 1300

N4 EPR

Future Future SystemsSystems

Generation IV

?


Nuclear Share of World Electricity Generation

At the end of 2002 :• 441 Nuclear power

reactors operating in 31 countries – 359 installed GWe

• 32 New Reactors – 27 GWe capacity - under construction

• Nuclear plants provide 16 percent of global electricity generation -~ 2,600 Billion KWh


Nuclear Energy assets for a worlwide development

Nuclear Energy :• A « zero-carbon »

emitting source

• Economically viablePossible high future ?

Nuclear Energy should play a major role in the next 50 years

But what challenges do we envision for a large expansion of Nuclear Power ?

Source : EIA, 2002


Significant prospects for nuclear energy deployment in the world

USA + 1500 Power Plants

by 2020 includingnuclear (+ 50 GWe ?)

FINLAND 5th reactor

Source : TotalFinaElf0%

20%

40%

60%

1900 1950 2000 2050

Coal R en

Oil

Gas

HydroNuclear

KOREAnuclear capacity

increase + 9 GWeby ~ 2015

INDIA nuclear capacity

increase from 2.5 to 20 GWe by 2020

JAPAN nuclear capacity

increase + 12 GWeby 2012

CHINA + 400 GWe

including + 30 GWeof nuclear capacity

by 2020BRAZIL

Nuclear ProgramRevival

Existing Gen II Reactors : an irreplaceable experience


An irreplaceable experience :17% of worlwide electricity generation

from nuclear power

more than 10 000 year.reactors of experience

~ 355 LWRs corresponding to 80% of theworld nuclear fleet (90% of the power produced)

To reinforce current results :Demonstrate, « prove » the safety of

NPPs and Fuel Cycle facilities

Still improve Nuclear Energy competitiveness

LIGHT WATER REACTORS WILL REMAIN

PREDOMINANT DURING THE FIRST HALF

OF THIS CENTURY

Civaux

Gen II : A nuclear power fleet that will need to be replaced


Operational NPPs Mean age

Country Nb Reactors Mean Age

United States 104 28 years

France 58 18 years

Japan 53 18 years

UnitedKingdom

31 29 years

Sweden 11 24 years

Germany 19 22 years

Belgium 7 23 years

China 7 5 years

Finland 4 23 years

Gen III : a mature technology for near term deployment


Generation III reactors identified as‘Near Term Deployment’ by the Generation IV Forum

Advanced Pressurized Water Reactors

AP 600, AP 1000, APR1400, APWR+, EPR

Advanced Boiling Water ReactorsABWR II, ESBWR, HC-BWR, SWR-1000

Advanced Heavy Water Reactors

ACR-700 (Advanced CANDU Reactor 700)

Small and middle range power integrated Reactors

CAREM, IMR, IRIS, SMART

High Temperature, Gas Cooled, Modular ReactorsGT-MHR, PBMR


Gen III : significant improvements in safety

Le Le projetprojet EPREPR

Core meltspreading area

Double-wall containmentwith ventilation and filtration system

Containmentheat removalsystem

Four-trainredundancyfor main safeguardsystems

Inner refuelingwater storage tank

EPR

Le Le projetprojet EPREPR

Core meltspreading area

Double-wall containmentwith ventilation and filtration system

Containmentheat removalsystem

Four-trainredundancyfor main safeguardsystems



EPR•• lessless wastewaste / kWh/ kWh•• higherhigher Pu Pu consumptionconsumption•• higherhigher resourcesresources savingssavings•• more more competitivecompetitive

AndAnd alsoalso otherother improvementsimprovements ::

Significant R&D efforts performed at CEA


ExampleExample : : severesevere accidents for EPRaccidents for EPR

10001000 tests

CATHARE : logiciel de thermohydraulique accidentelle pour la gestion des accidents de dimensionnement

VULCANO : dispositif d’essais et coulée de Corium

Gen III : An improved back-end of the Fuel Cycle


EPR, an EPR, an increasedincreased flexibilityflexibility for MOX use in for MOX use in reactorsreactors,,plutonium plutonium recyclingrecycling scenariosscenarios studiedstudied atat CEACEA

Plutonium annual balanceKg Pu/year

REP 900 UO2 : + 200

REP 900 MOX : 0

EPR 100% MOX : - 670

100% MOX Core

MOXUOXGrappe de contrôle et d’arrêt d’urgence EPRREP 900

An enhanced capacity to burnPlutonium

Enhanced ability for plutonium multi-recycling

GEN IV : paves the way for a sustainable nuclear energy


• Concepts with breakthroughsMinimization of wastesPreservation of resources

New requirements for sustainable nuclear energy• Gradual improvements in :

CompetitivenessSafety and reliability

Resistance to Proliferation

New applications :hydrogen productionwater desalinationdirect use of heat

Penetration of new markets :emerging countriessmall countries

Génération IVInternational

Forum Members

Génération IVInternational

Forum Members

U.S.A.U.S.A.

ArgentinaArgentina

BrazilBrazil

CanadaCanadaFranceFrance

JapanJapan

South AfricaSouth Africa

UnitedUnitedKingdomKingdom

E.U.E.U.

SwitzerlSwitzerlandand

South KoreaSouth Korea


Closed Fuel Cycles and Fast Reactors : minimize radiotoxicity

Plutonium recycling

Spent FuelNo reprocesisng

Uranium Ore (mine)

Time (years)

Rel

ativ

e ra

dio

toxi

city

P&T of MA

Pu +MA +FP

MA +FP

FP

Unat

Actinides

Spentfuel

Vitrified Waste

FP

GEN IV FR

Treatment and

Re- fabricationI.T.R.*

* : Integrated Treatment and Refabrication

Benefits of Advanced fuel Cycles :•• A A drasticdrastic minimizationminimization ofof ultimateultimate

wastewaste ::- volume, radiotoxicity, heat reduction

•• ResourcesResources preservationpreservation•• EnhancedEnhanced resistanceresistance to to proliferationproliferation


GEN IV : Gas Cooled Reactors

VHTR

GFR

HTR

Fast neutronsFull Actinide recycling

Hydrogen production


Capability to target new applications

NuclearNuclear energyenergy willwill bebe essential for :essential for :• Electrical power generation

… but … but alsoalso for new applications :for new applications :• Hydrogen production• Direct use of Heat• Sea water desalination

Nuclear HeatNuclear HeatHydrogenHydrogen OxygenOxygen

H2O22

1

900 C400 C

Rejected Heat 100 C

Rejected Heat 100 C

S (Sulfur)Circulation

SO2+H2O+O22

1H2SO4

SO2+

H2OH2O

H2

I2

+ 2HI

H2SO4

SO2+H2OH2O

+

+ +

I (Iodine)Circulation

2H I

I2

I2

WaterWater

Nuclear HeatNuclear HeatHydrogenHydrogen OxygenOxygen

H2O22

1 O22121

900 C400 C

Rejected Heat 100 C

Rejected Heat 100 C

S (Sulfur)Circulation

SO2+H2O+O22

1H2SO4

SO2+

H2OH2O

H2

I2

+ 2HI

H2SO4

SO2+H2OH2O

+

+ +

I (Iodine)Circulation

2H I

I2

I2

WaterWater

Very High Temperature Reactor

Fuel Cell Prototypevehicle

(hydrogen)


French Fleet of Nuclear Power Plants (2003)

Installed capacity in 200363 GWe

Nuclear Electricity GenerationProduction : 420 TWh

(77,6% of the total power produced)

58 PWRs + 1 FBR in operation

• 34 CP (900 MWe) (20 loadedwith 30% MOX)

• 24 P4 (1300 MWe)

• 4 N4 (1450 MWe)

• PHENIX (250 MWe)

(source : RTE - 2004)Shutdown NPP

Phenix

Transition scenarios between generations


Generation 3+

Generation 4Existing fleet40-year plant life

Plant life extension beyond 40 years

0

10000

20000

30000

40000

50000

60000

70000

1975

1980

1985

1990

1995

2000

2005

2010

2015

2020

2025

2030

2035

2040

2045

2050

2055

2060

Average plant life : 48 years Source : EDF, ENC 2002

Generation IV nuclear energy systems for sustainable long termImportant role of LWRs in the 21st century, that will be in operation until the end of the 21st century


Waste

PWR2°/3°Gen PUREX

U, Pu

FP SpentFuel

Uenr

PartitioningP.F.M.A.

Waste

PWR2°/3°Gen

PWR2°/3°Gen PUREX

U, Pu

FP SpentFuel

Uenr

PartitioningP.F.M.A.

M.A.

Transition from Pu mono-recycling in PWRs to Actinide global recycling in fast neutron Gen IV systems

Unat

I.T. R.*

Actinides

*I.T.R. : Integrated Treatment & Refabrication

FR4° Gen FP

Waste

SpentFuel

Unat

I.T. R.*

Actinides

*I.T.R. : Integrated Treatment & Refabrication

FR4° Gen

FR4° Gen FP

Waste

SpentFuel

• Mono-recycling of Pu (20 PWRs900 loaded with 30% MOX)

• Partitioning and interim storage of MA in order to minimize the amount of Actinides in the ultimate waste

• Maximum utilization of existing fuel cycle plants (La Hague, Melox)

• Management of Pu stockpile to deploy 4th generation fast neutron systems (> 2035)

• Recycling of MA from interim storage

• Integral recycling of Actinides in fast neutron 4th systems

• Non Proliferation

Grouped Actinide Extraction «GANEX»


FPs.

DISSOLUTION

SPENT FUEL

U preliminary RECOVERY

U

U +Pu+M.A.

EXTRACTIONAn + Ln

BACK-EXTRACTION An

BACK-EXTRACTION Ln

Ln

WASTE

ACTINIDESto recycle

Perspective for actinides management


2020 2030 2040 205020102000 2060 2070 2080

Gen4FR

U

GAM (U,Pu,MA)

Pu(U)

Gen 2LWR

UPu

Gen 3LWR

U,Pu,MA

GANEXon Spent LWR Fuels

(MOX and UOX)

Pu recyclingin LWRs

( MOX fuel)

Global Actinide Management(extraction and recycling)

in Gen 4 FRRecycling of LWR Puand MA in Gen 4 FR

Analyzed scenarios


Base scenario2015 - Mono-recycling of Plutonium as MOX fuel in PWR-900 and in EPR (>2020)

Concentration of Pu in Mox fuel

2020 - 2025 Introduction of Global Actinide Extraction and Treatment of spent MOX fuel to constitute a Plutonium stockpile

Light glass : reduced radio-toxicity and heat releaseInterim storage of grouped [Pu + Np/Am/Cm]

2035 - Introduction of fast neutron 4th generation systemsRecycling in Gen 4 FR of grouped [Pu + Np/Am/Cm] from spent LWR Mox and Uranium fuelsIntegral recycling in Gen 4 FR of Actinides from Gen 4FR spent fuel

Alternative scenarios in case of postponed deployment of Gen IV systems1 – Extension of Pu mono-recycling in PWRs2 – Multi-recycling of Pu in PWRs in order to stabilize the Pu stockpile3 – Multi-recycling of (Pu+Am) in PWRs to slow down the build-up of (Pu + Am)

Analyzed scenarios


Scenario based on the SFR reactors is slighly breeder, increasing the Pu inventory. The Minor actinides inventory is decreasing at 2100. Some optimisation are needed in order to reduce more efficiently MA inventory.

Inventories (t)

One Pu recycling Pu Multiple recycling (MOX-

UE)

Pu + Am multiple recycling (MOX-UE + Am)

MOX in PWR, then (Pu, Np, Am, Cm, ...) in FNR Gen IV ( SFR)

2035 2050 2070 2100 2035 2050 2070 2100 2035 2050 2070 2100 2035 2050 2070 2100

Pu (Total) 396 485 600 773 373 402 413 424 384 431 465 486 448 567 682 809

Np 20 31 48 75 18 30 45 69 17 29 45 64 24 31 33 25

Am 51 81 121 179 52 88 135 205 44 52 59 64 53 71 75 63

Cm 4.7 5.3 5.6 6.4 6.3 8.5 9.9 17.4 9.5 16 30 45 4 7 10 18

AM (Total) 76 118 174 260 76 127 190 291 71 97 134 173 82 109 118 106

Am+Cm (Total) 56 86 127 186 58 97 145 222 54 68 89 110 57 78 85 81

TRU total 472 603 774 1033 449 528 603 715 455 528 599 659 530 676 800 915

Pu (outpile) 313 407 527 698 266 266 276 287 283 276 312 328 397 347 461 401

TRU (outpile) 383 519 696 952 336 384 458 570 338 351 420 480 76 86 96 66

%(Am+Cm) for 20% Pu 3.6 4.2 4.8 5.3 4.3 7.3 10.5 15.5 3.8 5.0 - 2.5% 2.5% 2.5%

% MOX in N.P. 12% 12% 10% 10% 20% 24% 26% 28% 22% 38% 48% 48% 0% 50% 50% 100%

Analyzed scenarios - Main technical features (1)


Mono-recycling of Pu as Mox fuel in EPRFabrication of MOX fuel compatible with MELOX plantIncreasing Pu and (Am + Cm) stockpilesPossibility to recycle all Actinides in fast neutron systems after ~2080 to be confirmed

Multi-recycling of Pu as Mox-UE fuel in EPRFabrication of MOX-UE fuel in MELOX with a capacity increased to ~230 t/yStabilization of the Pu stockpile (~420 t) and accumulation of (Am + Cm)Possibility to recycle all Actinides in fast neutron systems after ~2040 to be confirmed

Multi-recycling (Pu + Am) as Mox-UE fuel (or Am targets) in EPRSpecific plants needed for the fabrication of fuel or targets with AmericiumModerate growth of Pu & Am stockpiles and accumulation of Cm Recycling of (Mox-UE + Am) in 45 % of the park or 50-60 % of the park with Am targetsPossibility to recycle all Actinides in fast neutron systems after ~2050 to be confirmed

Analyzed scenarios - Main technical features (2)


Multiple recycling in PWRs (Pu or Pu+ Am) has a priori little impact on the radio-toxicity of the residual nuclear matters in 2100 if fast neutron systems could finally not be deployed.

Inventories (t) Open cycle

Mono-Pu Multi-Pu Multi-Pu + Am

Pu 1020 773 424 486

MA 217 260 291 173

TRU 1237 1033 715 659

Radio-toxicity 1 ~ 0.8 – 0.9 ~ 0.5- 0.8 ~ 0.5- 0.6

In case of postponed deployment of fast neutron systems, 2 or 3 recyclings of Pu in PWRscould be envisaged around 2040 and 2060 to stabilize the Pu stockpile. However, there appear few motivations for multi-recycling strategies of (Pu + Am) in PWRs which would require specific fuel cycle plants, which would involve more than 50 % of the park and would produce large amounts of Cm, without stabilizing Pu and Am stockpiles.

Furthermore, such strategies would lead to accumulate stockpiles of nuclear matters difficult to recycle, without appreciable gain on the radio-toxicity in comparison with an open fuel cycle.

Base scenario (Gen 4 FR in ~ 2035) is the most attractive and sounded

Transition Gen II/III Gen IV : Items to be assessed


Nuclear materials optimization :

• Feasibility of plutonium multi-recycling in LWR

• Feasibility of M.A. temporary storage

• Fuel technologies (design and fabrication) for the M.A.transmutation with fast neutron reactors

• Feasibility of actinides integral recycling in Generation IVfast neutron systems


Global Actinides Management : 1st conclusions

1. Fast neutron 4th generation systems afford:to transmute all Actinides they generate, andto recycle also, to some extent, the Minor Actinides generatedby the PWRs, after partitioning and interim storage.

2. The physics of transmutation incites to recycle plutonium and Minor Actinides in 4th generation systems as soon as possible (~2035).

3. In case of postponed 4th generation systems deployment:future nuclear systems have enough flexibility to recycle the Minor Actinides generated by the LWRs,however with increasing constraints depending on the time and previous recyclings.

From this point of view, 2 to 3 recycles of Plutonium in EPR, to temporarily stabilize the Pu stock-pile, seems possible.

4. Past, present and planned technology demonstrations support the robust scenarios considered for the management of Minor Actinides.


An alternative route for MA transmutation

•• SubcriticalSubcritical AcceleratorAccelerator DrivenDriven SystemsSystems ddedicatededicated to to transmute M.A.transmute M.A.

High content

M.A. fuels Economical as part of a large fleet of reactors

R&D for Sc. & Tech. feasability

Fast spectrum cores, fast reactortechnologies

Open technologicalissues


Conclusion

• Nuclear Energy is competitive and will still improve its profitability

• Nuclear Energy is already safe and reliable ; however new generationswill be even safer

• Sustainability objectives to be met in a vision of a large expansion :

- nuclear waste minimization- preservation of natural resources- resistance to proliferation- capability to penetrate new markets- capability to target new applications

Closed Cycles and Fast Reactors are the appropriate answer

• Innovative technologies and international cooperation are thepillars of sustainable nuclear developmentSource EDF

Nuclear Fuel Cycle and sustainable development ...

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