european activity on ads - nuclear energy agency · fuels, petrochemical/ steelmaking/ paper/...

European Activity on ADS

D. HaasJoint Research Centre

Thanks to the contributions of DG RTD (R. Garbil, M. Hugon & al.)

The EURATOM Research Framework Programme

OECD Nuclear AgencyTCADS-2 International WorkshopNantes, France, 21-23 may 2013

I

TCADS-2 International Workshop

Content

• Introduction: motivation and challenges

• EURATOM Framework Programmes

• The Joint Research Centre contribution

• The way forward


Impact of nuclear electricity production

on the environment

• Negligible greenhouse gases generation

• Small infrastructure footprint (but mining)

• Negligible radiation in the environment in normal operation

• Fuel cycle waste (extraction, enrichment, spent fuel)

• Industrial facilities exist for LLW handling and storage

• HLW (spent fuel, vitrified waste) in geological disposal

• Reduction of HLW volumes (footprint) and radiotoxicity through plutonium recycling, minor actinides transmutation

The ADS helps burning the minor actinides and thus contributes to reducing the impact of nuclear on the environment


Arguments in favour of transmutation

Challenges

Reduction of the long-term waste radiotoxicity

Impact on final repository needs (heat aspects)

Long-term dose exposure reduction

Answer to a major nuclear-related societal question

Increased physical protection

Technological difficulties: fabrication, irradiation, reprocessing

Industrial feasibility: facilities, reactors, costs

Short-term dose exposure and additional waste streams

Selection of P&T strategy

Minor Actinide Partitioning and Transmutation

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w.S

NETP

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Maintain safety and competitiveness of today’s technologies

Fukushima impact: SNETP gives nuclear safety the highest priority in its vision and research agenda

Enlarge the nuclear fission portfolio beyond electricity production (H2, synthetic fuels, petrochemical/ steelmaking/ paper/ cement industries, seawater desalination, etc.)

Develop advanced reactors with closed cycle to enhance sustainability

ESNII

ESNII = European Sustainable

Nuclear Industrial Initiative

3 main pillars + key cross-cutting issues


ALLEGROExperimental reactor

(GFR)

ASTRID

Prototype

(SFR)

2008 2012 2020

SFR

Supporting infrastructures, research facilities

MYRRHAETPP European

demonstration reactor (LFR)

Reference

technology

Alternative technology

LFR

GFR

MYRRHAFast spectrum

irradiation facility

MYRRHA part of … SETPLAN and ESNII


2. Heterogeneous transmutation in fast reactors (high MA concentration in

blanket regions)MA separation by advanced partitioning (DIAMEX-SANEX, EXAM)

Low concentration of MA in the transmutation fuel (France: 10% Am in UO2)

Need for a FR fleet

Licensing of new fuel types

Remote fabrication/radioprotection issues on part of fuel only

1. Homogeneous transmutation in fast reactors

MA separation by co-extraction (GANEX)

Reduced MA content in the FR fuel (<5%)

Need for a FR fleet

Remote fabrication on whole fuel

Radioprotection issues on whole fuel cycle

Partitioning and Minor Actinides Transmutation

3. Heterogeneous transmutation in dedicated reactors (high MA concentration

in ADS systems)MA separation by advanced partitioning

High MA concentration in the ADS fuel (IMF)

Fuel licensing

Remote fabrication/radioprotection on part of fuel

Need for specific reactor design and construction


Reactor

• Subcritical or Critical modes

• 65 to 100 MWth

Accelerator

(600 MeV - 4 mA proton)

Fast

Neutron

Source

Spallation Source

Lead-Bismuth

coolant

Multipurpose

Flexible

Irradiation

Facility

MA Transmutation in ADS: MYRRHA Project in Belgium

SCK.CEN presentation ESNII Conference

June 2012, Brussels

MAXSIMA FP7 (2012-2013) Project

Euratom Framework Programme for

“Nuclear Research and Training Activities”

Euratom Programme

°°°

JRC participation as project partner in indirect actions


http://www.homme-economique.com/wp-content/uploads/2009/02/drapeau_europe_et_27_.jpg


TRANSMUTATION (6.5 MEuro)

Basic Studies:MUSE

HINDAS

N-TOF_ND_ADS


Technological Support:SPIRE

TECLA

MEGAPIE-TEST

ASCHLIM

PARTITIONING (5 MEuro)PYROREP

PARTNEW

CALIXPART


Fuels:CONFIRM

THORIUM CYCLE

FUTURE

TRANSMUTATION (6 MEuro)

Preliminary Design Studies

for an Experimental ADS:

PDS-XADS

FP5 (1998-2002) Projects on Advanced Optionsfor Partitioning and Transmutation

FP5 ADOPTCoordination Network

EUROTRANS FP6 Project


DM2 TRADE-PLUS

TRADE Experiment

DM4 DEMETRA

HLM Technologies

DM1 DESIGN

ETD Design

DM5 NUDATRA

Nuclear Data

Scientific ConsultancyCommittee

Governing Council

DM3 AFTRA

Fuels

EC

Project Co-ordination Committee

Co-ordinator

IP EUROPART

RedImpact

Related FP6 Projects:

Related National and

International

Programmes

DM0 Management

Project Office

DM2 TRADE-PLUS

TRADE Experiment

DM4 DEMETRA

HLM Technologies

DM1 DESIGN

ETD Design

DM5 NUDATRA

Nuclear Data

Scientific ConsultancyCommittee

Governing Council

DM3 AFTRA

Fuels

ECEC

Project Co-ordination Committee

Co-ordinator

IP EUROPART

RedImpact



International

Programmes

IP EUROPART

RedImpact


IP EUROPART

RedImpact



International

Programmes

DM0 Management

Project Office

FP6 EUROTRANS (2005-2011) Project Organization (43 M€)

Main goal:

Design and feasibility assessment of an industrial ADS prototype dedicated to transmutation

ECATS


Main achievements of the FP6 EUROTRANS Project (1)

Domain 1: DESIGN

• Conceptual design of Design of EFIT (European Facility on Industrialscale Transmuter) of several 100 MWth, Pb (or He)-cooled

• Design of the XT-ADS (eXperimental Transmuter based on ADS concept), 57 MWth Pb-Bi cooled, allowing to reach a high fast flux

• Superconducting LINAC identified (600 MeV), with reduced number ofbeam trips

• Design of the windowless spallation target• Safety analyses: major improvements in the response to severe

accidents as compared to previous (FP5) designs• Construction cost evaluation of XT-ADS (800M€)



Domain 2: ECATS

• Qualification of sub-criticality monitoring• Validation of the beam current/core power monitoring• Start-up and shut-down procedures, instrumentation validation• Code validation• YALINA experiment: pulsed and continuous neutron source in a

HEU assembly• RACE experiments in two configurations (TRIGA and HEU assembly)• GUINEVERE: 0-power fast core (HEU and solid Pb) coupled to a

GENEPI-3 accelerator (D, T) n source• Main conclusions: FP5 MUSE experiments confirmed within the

RACE thermal spectrum; critical vs sub-critical reactivity addressedin GUINEVERE; ADS scheme for reactivity monitoring validatedin YALINA


• GUINEVERE (zero power Mock-up of MYRRHA)

• Criticality reached in February 2011 - Subcritical coupling performed in October 2011



Domain 3: AFTRA

• Neutronic, thermo-mechanical and transmutation performancecalculations of an EFIT (DM1) reference core with Mo-CERMET fuel

• Assessment of the safety behaviour for various accident conditions for MgO-CERCER and Mo-CERMET fuels. Safety marginsare higher for the CERMET core

• Behaviour of ADS fuels under irradiation: FUTURIX-FTA in Phenix,HELIOS in HFR, BODEX in HFR, PIE on nitride fuels (CONFIRM)

• Experimental data on relevant fuel properties: thermal conductivity, vaporization and melting (CERCER), chemical compatibility tests, phase diagrams

Generation of Fuel Data Base (JRC-ITU)

TCADS-2, Nantes, France, May 21-23, 2013

Selection Criteria

Fabrication Feasibility: matrix volume

fraction > 50% Clad and coolant compatibility Margin to melt: thermal

conductivity + melting T Safety and high temperature

behaviour Coolant void worth Reactivity loss Burn-up Transmutation capability Reprocessing (aqueous)

Solid Solution Fuel (Pu,Am,Cm,Zr)O2-x or (Pu,Am,Cm,Th)O2-x

CERMET (Pu,Am,Cm)O2-x+Mo, Mo92, W, Cr or V

CERCER (Pu,Am,Cm)O2-x+MgO

Final AFTRA Recommendation

Mo-92 CERMET because of superiorsafety behaviour.

MgO CERCER because of better neutronic performance.

IKET (Institute for Nuclear and Energy Technologies)

Hottest Fuel Rod Performance

TCADS-2, Nantes, France, May 21-23, 201317

200

400

600

800

1000

1200

1400

1600

-50 -40 -30 -20 -10 0 10 20 30 40 50

Axial coordinate (cm)

Tem

pera

ture

(C

)

fuel centre fuel surface

clad inner clad outer

coolant

CerCER

24 h after start

Tlimit = 2130 °C

vPb = 1 m/s200

400

600

800

1000

1200

1400

1600

-50 -40 -30 -20 -10 0 10 20 30 40 50

Axial coordinate (cm)

Tem

pera

ture

(°C

)

pellet centre pellet surface

inner clad outer clad

coolant

CERMET:

24 h after startTlimit ~ 2380 °C

600

800

1000

1200

1400

1600

1800

2000

0 500 1000 1500 2000 2500 3000

Time (d)

Tem

peratu

re (

K)

0

30

60

90

120

150

180

210

Pell

et-

cla

d g

ap (

mic

rons)

Gas

rele

ase

(%

)

Fuel temperature

Pellet-clad gap

Gas release

600

700

800

900

1000

1100

1200

1300

0 500 1000 1500 2000 2500 3000

Time (d)

Tem

peratu

re (

K)

0

30

60

90

120

150

180

210

Pell

et-

cla

d g

ap (

mic

rons)

Gas

rele

ase

(%

)

Fuel temperature Pellet-clad gap

Gas release

A. Rineiski (KIT), V. Sobolev (SCK•CEN), J. Wallenius (KTH), WP3.1: Design, Modelling and Selection of Fuel for MA

Transmutation in EFIT (normal operation), 2nd Joint Workshop EUROTRANS-JAEA on ADS activities, KIT, March 18-19,

2010.



Domain 4: DEMETRA

• Materials : AISI 316L, FM T91 corrosion and mechanical properties• Coolant chemistry and handling: oxygen sensors and control

systems, filters development• Thermal-hydraulics experiments and code validation: single pin

and bundle, validation of stable free surface windowless spallationtarget

Preparation of the FP7 GETMAT project with materials irradiations



Domain 5: NUDATRA

• Codes development to simulate transmutation fuel cycles• Validation of codes using integral experiments for spallation

models, minor actinides and Pb/Bi data• Evalution of nuclear data sensitivity to industrially relevant

parameters in case of transmutaion• Optimization of future nuclear data measurements and evaluation

of required accuracy on new data needs

Topic FP5 FP6EUROTRANS DM.

FP7

Coupling - DM2-ECATS FREYA

Fuels CONFIRMFUTURE

DM3-AFTRA FAIRFUELS, F-BRIDGE,ASGARD, ALICE

Thermal-Hydraulics

ASCHLIM THINS, SEARCH, MAXSIMA

Materials MEGAPIE, SPIRE, TECLA

DM4-DEMETRA MATTER, GETMAT, (MATISSE)

Design PDS-XADS DM1-DESIGN CDT, MAX, SARGEN-IV, SILER

LFR - ELSY LEADER

Infrastructures - VELLA, MTR-I3 HELIMNET, ADRIANA, DELOITTE Study

Scenario studies - PATEROS ARCAS, (MARISA)

Partitioning PYROREP,PARTNEW

EUROPART ACSEPT, SACSESS

Total budget / EU contribution

~€51M/€20M ~€71M/€36M ~€145M/€74M

MYRRHA Strongly embedded in Euratom FP

(..): under negotiation

EU SARGEN_IV project: brings together the main European stakeholders

to propose a European harmonized safety assessment practice for innovative

reactors with fast neutron spectrum planned to be built in Europe.

22 Participants from 12 MSs + EU [TSOs, the JRC, national research organizations, designers, utility, universities]: IRSN (co-ordinator), JRC-IET (Petten), GRS, BelV, ENEA, LEI, CEA, ANSALDO, EdF, UJV, VTT, PSI, MTA EK, AREVA, AMEC, UNIMAN, KIT, HZDR, VUJE, RWTH, SCK-CEN, UPM

Duration: 24 Months Start: 01/01/2012

SARGEN_IV objectives and outcomes:

1. Identification of critical safety features for technical systems of reference

2. Review of safety methodologies for innovative reactors and proposal for a European harmonized safety assessment practice

3. Pilot application of the harmonized European safety assessment practices

4. Development of a European roadmap for fast reactors safety R&D5. Dissemination and Communication of the outcomes to

stakeholders

• Molten LBE is corrosive as well as might erode structural materials

• Lead (as well as bismuth) vapours are chemically toxic

• Accumulation of corrosion products or coolant solidification might lead to coolant

blockages

• In case LBE freezes (< 125ºC), mechanical stresses on structures might be

exerted both during solidification and melting

• Ruptures of heat exchanger tubes might lead to over-pressurisation of the primary

side, sloshing and steam/water entrainment resulting in a positive reactivity

insertion

• Rupture of the accelerator beam window might lead to a containment bypass

SARGEN_IV:

Identification of critical safety features for MYRRHA


EURATOM Direct Actions on P&T (JRC-ITU)

• Fuel cycle safety studies and experiments

- Mixed fuels and targets preparation with Pu, Minor Actinides

- MOX, nitride, carbide, metallic fuel properties

• Partitioning

- Advanced aqueous methods

- Electrochemistry in molten salts

• Safeguards and proliferation resistance studies

Minor Actinide

Fabrication Laboratory

CERMET (Mo) fuel with Pu,

Am irradiated in Phenix

CERCER vaporization measurements

250 µm


Conclusion and way forward

• Since more than 15 years, the EURATOM RTD research contributesto the P&T and ADS developments through Indirect Actions

• The Joint Research Centre main efforts are in the area of the minor actinide fuels and targets properties, advanced partitioning,neutron data and reactor safety

• This programme will be pursued, in support of national efforts inADS design and construction

• A specific new project, called MARISA, intends to support theestablishment of the MYRRHA facility consortium


Conclusion and way forward

• Since more than 15 years, the EURATOM RTD research contributesto the P&T and ADS developments through Indirect Actions

• The Joint Research Centre main efforts are in the area of the minor actinide fuels and targets properties, advanced partitioning,neutron data and reactor safety

• This programme will be pursued, in support of national efforts inADS design and construction

• A specific new project, called MARISA, intends to support theestablishment of the MYRRHA facility consortium

Time horizon: full operation ~ 2023

Costs: ~ EUR 960 million

Thank you for your attention

european activity on ads - nuclear energy agency · fuels, petrochemical/ steelmaking/ paper/...

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