Overview of CEA R&D Programme For Future Nuclear Systems G. Cognet

September 2006Visit to Romania 1CEA R&D for Future Nuclear Systems

Overview of CEA R&D ProgrammeFor

Future Nuclear Systems

G. Cognet


Considerations on future systems & closed fuel cycle

Future systems should materialize the vision of nuclear energy best suited to contribute, with other energy sources, to secure a sustainable energy development in Europe

Sustainability means here: best use (saving) of natural uranium resources minimization of long-lived waste production minimization of radioactive release guarantee of safety resistance to proliferation


Evolution of the Spent Fuel Radiotoxic Content

0,1

1

10

100

1000

10000

10 100 1000 10000 100000 1000000

Time after irradiation or spent fuel processing (year)

Rel

ativ

e ra

diot

oxic

ity le

vel -

Ref

eren

ce :

extr

acte

d na

tura

l ura

nium

(U

OX

fuel

)

Spent UOX fuelStandard vitrified waste (MA + FP)Vitrified waste without MA (only FP)One Pu recycling (MOX in PWR)Multiple Pu recycling in PWRMultiple Pu recycling in Gen IV FNRGlobal recycling (Pu+MA) in Gen IV FNRNatural Uranium for PWR UOX (same energy produced)

Spent UOX fuel: direct disposal of the irradiated fuelStandard vitrified waste: glasses with MA and FP from the UOX spent fuel processing (as produced today at La Hague facility)Vitrified waste without MA: standard vitrified waste (see upper) but without any M.A. (only FP from the UOX spent fuel processing)One Pu recycling: All TRU after single Pu recycling in PWRMultiple Pu recycling in PWR: M.A. and F.P. from the UOX and MOX spent fuel processing in case of a scenario with multiple Pu recycling in PWRMultiple Pu recycling in FR: M.A. and F.P. from the FR spent fuel processing in case of a scenario with multiple Pu recycling in FRGlobal recycling (Pu+M.A.) in Gen IV FR: F.P. from the FR spent fuel processing in case of a scenario with multiple Pu and M.A. recycling in FR


Partitioning and TransmutationPartitioning technological demonstrationTransmutation & evaluation report in 2005

Atalante laboratory shielded process line CBP • 15 kg of spent fuel• Np separated

Phenix FBR Dedicated irradiation experiments are in

progress until 2009

P&T offer the opportunity to reduce considerably the long-lived inventory in radioactive waste

R&D on Nuclear Waste Management


A 2 to 6% cost increase in the kWh priceA 2 to 6% cost increase in the kWh price of reprocessing and recycling against the once-through option (based on real costs and on a long lasting industrial experience in France)

… … to be balanced with clear benefits of to be balanced with clear benefits of recycling :recycling : reduction of the volume of final waste more effective use of natural resources (up to 25% reduction of natural uranium consumption) better route to more advanced and efficient nuclear systems (advanced partitioning, transmutation, breeding…)

Spent Fuel Management : Closing the fuel cycle

Closed cycle: A more sustainable policy satisfying the present needs without impairing the capacities of the next generations

Mines Enrichment

FuelFabric.

Reactors& Services

Recycling :MOX Fuelfabrication

EnrichedUranium

UltimateWasteDisposal

Front-End Sector

Reactors & Services Sector Back-End Sector

Uranium recyclable

Plutonium

ChemistryNatural Uranium

Spent FuelReprocessing


If the world nuclear park is based on “current” technology with an installed capacity which will remain stable until 2020 and then could grow linearly until 2050, the uranium resources consumed and earmarked in 2050 would be :

What nuclear reactors for future ?

Nuclear primary energy in 2050 (Gtoe) 0.7 1.8 2.5 3.2

Installed capacity in 2050 (GWe) 400 1000 1400 1700

Unat consumed and earmarked in 2050 (Mt)

6 12 16 19

The resources of U (15 million tons) will have been earmarked once the installed capacity reaches 1300 GWe Breeding, or at least iso-generation, reactors will therefore be

needed before this time.

Technological breakthroughs are needed


Very High Temperature Reactor

GEN-IV Initiative: 6 Innovative concepts with technological breakthroughs

Sodium Fast reactor

Closed Fuel Cycle

Once Through

Supercritical Water Reactor

Once/Closed

Molten Salt Reactor

Closed Fuel Cycle

Closed Fuel Cycle

Lead Fast ReactorGas Fast Reactor

Closed Fuel Cycle


Most Promising Future Systems for CEA

Sodium technology is the reference technology : Innovations are needed Possibility to build a prototype (300/600 MWe) by 2020

An alternative technology is needed : Viability and performances to be assessed in 2010, to decide

for an experimental reactor (50/100 MWth)

VHTR technology development in link with process heat needs (synthetic oil, hydrogen…)


R&D Strategy of France for Future Nuclear Energy Systems

1 – Development of Fast Reactors with closed fuel cycles, along 2 tracks:

Sodium Fast Reactor (SFR) Gas Fast Reactor (GFR) New processes for spent fuel treatment and recycling

Industrial deployment around 2040

2 –Hydrogen production and high temperature process heat supply to the industry Very / High Temperature Reactor (V/HTR) High Temperature Electrolysis and Water splitting

processes

3 – Innovations for LWRs (Fuel, Systems…)

Approved by the French Government in March 2005


A Prototype Reactor in 2020

President Chirac statement (Jan 06) : « A number of countries are working on future generation reactors, to become operational in 2030-2040, which will produce less waste and will make a better use of fissile materials. I have decided to launch, starting today, the design work by CEA of a prototype of the 4th generation reactor, which will be commissioned in 2020. We will naturally welcome industrial or international partners who would like to get involved. »


France has a large experience in SFRs

60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03595857

RAPSODIE

PHENIX

SUPERPHENIX

EFR

Studies & design Construction DecommissioningOperation

1st criticality

1st connection to the grid Final shutdown

01/67

02/98

08/73 12/73

09/85 01/86

40 MWth

250 MWe

1200 MWe

1500 MWe

10/83

SPX 2

60’s 70’s 80’s 90’s


R&D on Sodium Cooled Reactors

- Goals : investment cost, safety, operating conditions - System simplification : architecture, conversion system - CO2sc,

direct cycle or combined (nitrogen-helium)

- In-service inspection and repair, - Advanced materials for structures and fuel,

- Core safety and notably issues associated with criticality control (void-effect, re-criticality)

- Definition of 2 concepts for a sodium cooled reactor :

- to illustrate proposed innovations within a global design,

- to evaluate resulting economics and associated risks,

- to best target the most promising R&D paths,


Innovative SFR Sketches

Échangeur

dégazeur

Circuit primaire à boucle

PEM

Simple bouchon tournant

Échangeur puissance résiduelle

Échangeur intermédiaire à faible dimension radiale

Large pool type

1500 MWe optimized size

Modular concept with gas conversion system


R&D on GFR

Second FNR path with inert and transparent coolant

- Technological Challenges : - nuclear fuel- residual power management - materials

- High power GFR feasibility

- Experimental Reactor design studies- global design, consistent with GFR- safety assessment report (SAR)


ETDR and 2400 MWth GFR Sketches

GFR 2400 MWth

Experimental Reactor50 MWth


Nuclear Fuel Cycle Goals

R T

Ude

FP

U Pu MA

R T

Ude

MAU Pu

FPR T

Ude

FP MA

U Pu

Homogeneous recycling (GenIV)

Heterogeneousrecycling

U & Pu recycling

Natural resources conservation Waste minimisation

Proliferation resistanceAll paths should be kept available, they could be used in a sequence.


A European strategy for nuclear energy ?

The Green Paper

The effective participation of EURATOM in the GEN-IV International Forum since September 2003

The “International Partnership for the Hydrogen Economy” signed in Washington in November 2003

The European awareness of energy dependency (oil or gas)

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

GIF

Some recent events could stimulate a change in the perception of the role of nuclear energy in Europe :


What stakes in the involvement of Europe in future nuclear energy systems ?

Be ready for the Gen II/III reactors fleet renewal stage by 2040 in 2015-2020 be able to choose a fast neutron system technology with an optimized management of actinides

Join the international effort to meet future hydrogen needs in 2015-20 be able to choose a nuclear production process

Preserve our role of European leader on the international scene

Enhance past European experience into innovative technologies (sodium fast reactors, fuel cycle processes…) Develop new technologies to preserve our leadership

Share the same view and a common strategyShare the same view and a common strategy


A European R & D parallel to Gen-IV

Possibilities of direct contributions of Euratom countries to Forum Generation IV, but needs of a coordination

European 5th Framework Programme

European 6th Framework Programme

Generation IV International Forum

Michelangelo Network HTR – Technology

Network RAPHAEL (ex V/HTR-IP)

(Integrated project) Very High Temperature

Reactor (VHTR) Gas Cooled Fast

Reactor (GCFR) GCFR: Gas Cooled Fast

Reactor (Strep) Gas Fast Reactor (GFR)

High Performance LWR (HPLWR)

HPLWR-II(Strep)

Supercritical Water Reactor (SCWR)

Molten Salt Technology review (MOST)

Sodium Fast Reactor(SSA under preparation)

Molten Salt Reactor (MSR)

Sodium Fast Reactor (SFR)

Lead Fast reactor (LFR)

Molten Salt Reactor(SSA under preparation)

VELLA(I3 for lead technologies)


Sustainable Nuclear Fission Technology Platform (SNF-TP)

LWR(current & Gen-3) Competitiveness

and Safety Optimization

VHTRProcess Heat,

Electricity & H2

Fast Neutron Systems & Closed

Fuel Cycle Critical Reactors

ADS

Materials & Fuel Development

Reactor Design & Safety

Fuel Cycle and Waste Processes

System Integration (Economy, non proliferation …)

Training and R&D Infrastructures

Geological Disposal

Technologies, design, safety assessment

Launching in 2007


Report of the Group of

Personalities

SRA

GoP

Vision2020

CA:SNF-TP

Stakeholders

ResearchPrograms

ResearchProjects

The Strategic Planning Route

The Strategic Research Agenda

- Revision every 2 years -

Public (EU, National, Euro-control, etc.)

andPrivate (Industry)

The Implementation Route

Establishing SNF-TP: Typical Road Map

2004 2006 2007

SNF-TP startingSNF-TP starting


Structural materials for nuclear fission and fusion

Research and technology development in material science is a key stake for a sustainable development of fission and fusion nuclear energy :

SFR (Sodium Fast Reactor) economical competitiveness has a direct link with the fuel cladding material and the circuits material;

Viability and performance of GFR (Gas Fast Reactor) is relying on the development of a refractory fuel.

Viability and performances of a fusion reactor have a direct link with blanket and divertor materials

A common issue : high temperature & high fast neutron flux


Reactorpool

Access tostorage pools& hot cells

JHR,a 100MW testing reactor

JHR characteristics

51,12m x 46,75m + Φ 36,6 m

In core:High fast neutron flux

(up to 1015 n/cm²/s>0,1 MeV)

Material ageing(up to 16 dpa/y)

Gen IV fuels (GFR)

In reflector:High thermal neutron flux(up to 5.5 1014 n/cm²/s)

Fuel studies(up to 600 W/cm with a 1% 235U

PWR rod)

Displacement systemsTo adjust the fissile power

20 simultaneous experiments coupled with 4 cells, bunkers, fission product on line laboratory, …

Advanced metallic alloys and Ceramic Matrix Composites raise challenging breakthroughs in material science that require a high performance experimental irradiation infrastructure, Jules Horowitz Reactor (JHR).

JHR MTR project

Overview of CEA R&D Programme For Future Nuclear Systems G. Cognet

Documents

Transcript of Overview of CEA R&D Programme For Future Nuclear Systems G. Cognet