OVERVIEW OF CEA STUDIES ON FUTURE NUCLEAR · PDF fileOverview of CEA studies on Future Nuclear Energy Systems. ... PMR R & D • Fast neutron ... Overview of CEA studies. Nuclear Development

NEA workshop on « R&D needs for current and future nuclear systems »November 6-8, 2002 – Paris

1Nuclear Development & Innovation Division

OVERVIEW OF CEA STUDIESON FUTURE NUCLEAR ENERGY SYSTEMS

Frank CARREFuture Nuclear Systems Project Manager



Outline

Advanced LWRs with improved fuel cycles

Sodium Cooled Fast Reactors

Assets of high temperature gas cooled systems

Significance of international cooperation

Overview of CEA studieson Future Nuclear Energy Systems



Future Nuclear Energy Systems

Save naturalresources

Extract most ofthe fuel energy

Reduceproliferation risks

Pu burning,integration of fuel cycle

Minimize Wasteproduction

Integral recycling ofactinides

SAFETYECONOMICS

5 fundamental criteria



Advanced LWRs with improved fuel cycles

Containmentdesigned towithstandhydrogendeflagration

Spreading AreaProtection of the Basemat

Prevention of highpressure core melt bydepressurisationmeans

Containment HeatRemoval System

In Containment RefuelingWater Storage Tank (IRWST)Save natural

resourcesExtract most ofthe fuel energy

APA (Advanced Pu Assembly)

UO2 standard rodsGuide tubes

Pu rods

CORAIL Assembly

UO2 standard rodsGuide tubes

MOX rods (with depleted U)

Spent fuel

U Pu

DIAMEX SANEXAn + Ln

Am Cm

{F.P.}.

Ln

NpNp I I

PUREX

Am + Cm

SESAME

PF+AM

Glass

Minimize waste radiotoxicity bypartitioning minor actinides

Advanced subassemblies for Pu recycling

A new generation of PWR : EPR



Potential improvement of LWR highradioactive waste management

Radio toxicity of wastes

1,00E+03

1,00E+04

1,00E+05

1,00E+06

1,00E+07

1,00E+08

1,00E+09

1 2 3 4 5 6

log(years)

Sv/T

Wh

Open cycle

Plutonium multi recycling

Initial Natural Uranium

Pu multi recycling & MA separation



A vision of advanced LWR systems in the 21st century

SAFETY

Save naturalresources

Extract more energyfrom the fuel

ECONOMICS


Recycling,transmutation of MA

Minimize proliferation risk

Pu burning,

IMPROVEDREPROCESSING



Preservation of past experience on Phenix and SuperphenixData base on reactors + Operation of Superphenix + RCC - MR

Some effort on sodium technology to support Superphenix dismantling

Irradiations programs in Phenix (2003-2008, 720 EFPD at 350 MWth)Basic data + material testing + MA & LLFP transmutation + Pu burning + Innovative fuels

Studies and code validations (SIMMER III) for recriticality risk analysisBall-trap experiments for molten and boiling mixed pool behavior analysis

Analysis of CABRI/Raft TPA2 test

Application on gas cooled reactors

CEA Program on Sodium Cooled Fast Reactors (1)

(+ Rapsodie & EFR)



International collaborations (JNC, MINATOM, Generation IV)OECD/IAEA : Nuclear data

IAEA : Preservation of knowledges + CRPs

Japan : Support to restart Monju

Russia : Irradiations program BORA-BORA in BOR 60

Support to BN600 life extension project

China & Korea : Support to CEFR and KALIMER project

Generation IV

CEA Program on Sodium Cooled Fast Reactors (2)




Save naturalresources (U, Th)

Reuse (U, Pu) fromexisting reactors

Enhanceproliferation resistance

Pu burning,Integration of fuel cycle


Integral recycling ofactinides

SAFETY

Operation/AccidentsSevere conditions

ECONOMICS

CompetitivenessInvestment cost

5 fundamental criteria Missions andadditional criteria

Electricity generation

Hydrogen production/HT process heat

Long-lived radioactive wasteburning

High sustainability

Symbiosis with existing LWRs

Flexible adaptation to diversefuel cycles




CEA technology roadmap

LWRLight Water Reactors

GCRGas Cooled Reactors

LMFRLiquid Metal Fast Reactors

MSRMolten Salts Reactors

PWRBWR

+ advancedfuel

Supercritical Water,Vapor

Na

Improvements(ISIR)

&Alternative :* Pb (Russia)* Pb-Bi : EU

ADS

?BasicR&D

SaltsMaterials

Pyrochemistry

+ Evaluations

HTR ~ 2025

« HTR » technology+ recycling+ harderspectrum ~ 2035

GCADS # GCFR+ spallation neutrons≥ 2050

LMC-ADS

LWRLight Water Reactors

GCRGas Cooled Reactors

LMFRLiquid Metal Fast Reactors

MSRMolten Salts Reactors

PWRBWR

+ advancedfuel

Supercritical Water,Vapor

Na

Improvements(ISIR)

&Alternative :* Pb (Russia)* Pb-Bi : EU

ADS

?BasicR&D

SaltsMaterials

Pyrochemistry

+ Evaluations

HTR ~ 2025

« HTR » technology+ recycling+ harderspectrum ~ 2035

GCADS # GCFR+ spallation neutrons≥ 2050

LMC-ADS



R & D• Fuel particles• Materials• He systems technology (850°C)• Computer codes• Fuel cycle

R & D•VHT materials• IHX for heat process• ZrC coated fuel• I-S cycle H2 production

PMRR & D

• Fast neutron fuel• Fuel cycle processes• Safety systems

VHTR

GFR

> 950°C for VHTheat process

Fast neutronsIntegral fuel cyclefor highsustainability

Sequenced development of high temperatureGas cooled nuclear energy systems



Gas cooled reactors (GCR) :an evolutive range of nuclear systems

• For the short term : first configuration direct cycle HTRConcept of the 1970 ’s-1980 ’sDirect conversion with gas turbine

• For the medium term : specialized GCRVery high temperatures and high efficiencyRobust « export » versionsOptimized configurations for waste transmutation

• For the long term : sustainable energy developmentFast spectrumComplete uranium consumptionIntegrated cycle transmuting all the actinides



300 MWe Modular High Temperature Reactor

• EconomicsSimple concept : a simple, direct-cyclesystemHigh conversion efficiency : 48 % for850°CModular design : in factory manufacturedstandard modulesModerate overnight cost (300 MWe) andfast construction (36 months)

• Safety and reliabilityRobust particle fuel (1600°C and beyond)Passive decay heat removal, even indamaged plant conditionsFavorable fuel form for proliferationresistance



Restoration of CEA R&D capabilitieson updated HTR technologies

ZrO2

Porous PyC(72 µm)

Dense PyC(53 µm)

Manufacturing and quality control of TRISO fuel particles (2004)



Development of structural materials

Fuel elementInner core structures(1000-1600°C, irradiation,stress)Turbine(850 °C, stress)

• AFM ODS• Refractory metals and alloys• Ceramics

Primary system(250 – 850 °C, stress)

Vessel(250 – 500 °C, irradiation)

• Ni based super-alloys• 32Ni-25Cr-20Fe-12.5W-0.05C

(German HTR)• Ni-23Cr-18 W-0.2C (Japanese HTTR)• AFM + Thermal barriers

AFM 9 – 12% Cr

• Graphites• PyC, SiC, ZrC

Ni based alloys or ODS

Reactor componentDirect cycle Fast RCG HTR



High Temperature Gas-Cooled System Technology

TECHNOLOGY TEST LOOP~ 1 MW

ComponentsCircuits

InstrumentationOperation training

Accumulating feedback

Heat Exchanger recuperator

L.T. Cooler

Circulator

TurbineHeater

H.T. Cooler

50 °C

450 °C

950 °C

Test Sections

550 °C

200 °C

PHe > 70 barQHe = 0,4 kg/s

900 °C

100 °C



Gas-Cooled Fast Reactor (GFR)Example of candidate design options

Composite ceramicsfuel element

Corelayout

Core vessel



Gas-Cooled Fast Reactor (GFR)Candidate fuel technologies

Dispersed fuels

particles Composite ceramics Solid solutions

% of Actinides compoundin the core

Advanced particles fuel

0 20 5010 30 40



GFR candidate fuel technologies

<<1µm, collisionRecoil nuclei

20µm, ionisationParticles α, He

10µm, ionisationFission products

>1cm, collisionNeutrons

Composite ceramics fuel with coated actinides elements and high actinidescontents

Achieve comparable performances with coated fuel particles in terms of hightemperature resistance and FP confinement

Preserve inert matrix coatings from generalized damage by fast neutrons and FP



HNO3 - H2O2Dissolution

FPHLW Confinement

SiC

NaOH/O2Dissolution

Si

Gas treatment

Powdermetallurgy

An groupseparation

PVDCoating An

U adjustment

AnC SolgelProcess

Exemple of processes for the treatment and refabrication ofAnC/SiC composite fuel



GFR conceptual design studiesCandidate decay heat removal strategies

FORCED CONVECTION NATURAL CONVECTION

250°C

1100°C à

1400°C

1400°C

250°C

250°C

200°C

200°C

150°C

Rayonnement

250°C

200°C

80°C

30°C

6 MPa

4 x 25 kW

25% rendement

70°C

40°C

4 boucles de 25 kWe chacune

Tour de réfrigération

sèche

DIESEL

RESEAU



Key technology fields for a sequencedDevelopment of gas cooled nuclear systems

PMR → VHTR → GFR• Fuels

Standard and improved TRISO particles + TreatmentComposite ceramics fuel technologies for fast neutron systems

• Integrated treatment and refabrication of the spent fuelSimple, compact and symbiotic processesAqueous, pyrometallurgical or other dry processes

• Materials resisting to high temperatures and fast neutrons

• Technology of high temperature helium systemsTribology, impurity control, thermal barriers, componentsRecuperator, VHT IHX

• Systems studies, calculation tools



Development plan for future nuclear energy systems



• An experimental Fuel Testing Reactor by 2012 at Cadarache20 to 40 MWTo qualify fuel technologies for VHTR, Actinides-Burner, GFR

• An integral test loop of gas systemsTest of GCR components and systemsInvestigation of normal and abnormal operating transients

• An integrated fuel cycle test facilityDemonstration of processes scientific feasibility in ATALANTEDemonstration of related technologies in a small scale inactive integrated pilot plant

A prototype of GFR (100-300 MWe) could be built around 2020, as an international project

3 major experimental demonstrations for thedevelopment of gas cooled nuclear systems



Candidate scenario for the possible deployment of gas cooled nuclear systems in France2000 2010 2020 2030 2040 2050

63 GWe operating LWRs

EPR

PMR

GFR

1450 MWe

300 MWe

300 MWe

U

Pu

U, Pu + AM

TRANSMUTATION

DEDICATED SYSTEMS

Pu + AM

Pu +AM

Pu

Pu

AM

(+ Am ?Np ?)

Pu

U

U



Iodine-sulfur process for the thermochemical productionOf H2 (Source : ORNL)



Principle of current desalination processes

Distillation processes

Vertical tube evaporator

VTE

Multiple effect

Membrane processes

Horizont. tube evaporator

HTE

Vaporcompression

VC

Reverseosmosis

RO

Electro-dialysis

ED

MultistageflashMSF

Heat consuming processes Power consuming processes



Generation IV overall mission

Deployable by 2030

With significant advances in :• Sustainability• Safety and reliability• Proliferation and physical

protection• Economics

Competitive in various markets

Designed for different applications : Electricity, Hydrogen,

Clean water, Heat

Development of one or more nuclear energy systems



LLXXLXLXNN

HLHXHMMH*NN

H*HHMLMHXNN

MHMMMHH*XNN

MXH*XLLLXNN

MMXXHH*HXNN

GIFSELECTION

Interests for GEN IV Concepts

High, AnimHighMediumLowNoNeutral

H*HMLXN



• Generation IV International Forum• European network

HTR-TN Network with some 20 organizations

• Bilateral French/USA agreements2 bilateral agreements signed on GEN IV research in 2000 & 2001Common projects (International NERI)

• Bilateral French/Japanese agreementsJNC: Agreement extended to Gas cooled fast reactorsJAERI : Agreement extended on HTTR and Hydrogen production

• Bilateral French/Russian agreementsMinatom : Agreement based on LMFRs and Gas cooled reactors

Active international collaboration onFuture Nuclear Energy Systems



• Minimising long-lived waste and saving natural resources are key issues for 21st

century nuclear energy systems

• Major R&D focus for sustainable energy policies :- Optimisation of LWR fuel cycle back-end- Phased development of gas cooled nuclear systems (PMR, VHTR, GFR…)- Preserve expertise on sodium cooled fast reactors

• Active and innovative R&D work on key technologies for the reactors, fuels, andfuel cycle :

- High performance materials- Input from non nuclear technologies and basic research for breakthoughs

• Active international cooperation on goals and roadmaping of promisingtechnologies for future nuclear energy systems :

- Generation IV International Forum- Bilateral cooperation : DOE, JNC, JAERI , Minatom- European networks and R&D Framework Programmes

Summary

Overview of CEA studieson Future Nuclear Energy Systems



Documents

OVERVIEW OF CEA STUDIES ON FUTURE NUCLEAR · PDF fileOverview of CEA studies on Future Nuclear Energy Systems. ... PMR R & D • Fast neutron ... Overview of CEA studies. Nuclear Development