The Joint Programme on Nuclear Materials of the European Energy Research Alliance (EERA JPNM)

Transcription

1 The Joint Programme on Nuclear Materials of the European Energy Research Alliance (EERA JPNM) Coordinating GenIV reactor materials research for a low carbon Europe L. Malerba, JPNM coordinator SCK CEN, Belgium J. Kalivodova, JPNM MB member CVR, Rez EERA is an official part of the EU SET-Plan.

2 EERA JPNM in the complex European platform landscape EU functioning Treaty Euratom Treaty >175 public research organisations (15 in ExCo) TRL 5 Coordination of low CO 2 energy research in EU TRL 5 Gen IV Gen II/III CoGen Industrial initiatives JP1 JP1JP1 JP energy x 17 JPs JPNM (1 of 17) Signature of MoU between EERA JPNM & SNETP is in the pipeline 2

3 Sustainable nuclear energy: ESNII GenIV reactors and fuel cycle facilities ASTRID ALFRED ALLEGRO Liquid Sodium Cooled Fast Reactor (SFR) Liquid Lead Cooled Fast Reactor (LFR) Gas Cooled Fast Reactor (GFR) MYRRHA (Very) High Temperature Reactor (HTR) SuperCritical Water Cooled Reactor (SCWR) Accelerator Driven System (ADS) European Sustainable Nuclear Industrial Initiative Molten Salt Reactor (MSR) concepts 3

4 Objectives of the JPNM Pursue better knowledge of materials behaviour in operation: - achieve predictive capability (radiation & temperature effects, compatibility with coolants ) - select most suited materials for GenIV systems - support definition of safe design rules JPNM improve safety & sustainability of Nuclear Energy, focusing on materials aspects Develop innovative materials for industrial use with superior capabilities: - resistant to high temperature and irradiation - resistant to aggressive environments Development of physical models coupled to advanced microstructural characterization to achieve high-level understanding and predictive capability 4

5 TRL Structural materials EERA JPNM subprogramme structure to face the challenges of DoW and roadmap 5 Industrial application SP1: support to European Sustainable Nuclear Industrial Initiative (ESNII) (K.-F. Nilsson, JRC-IET) SP5: Advanced fuels (J. Somers, JRC-ITU) SP2: Innovative steels (M. Serrano, CIEMAT) SP3: Refractory materials (A. Rinaldi*, ENEA) Technological Innovation Fuel SP4: Physical modelling of structural materials (C. Pareige, CNRS) Basic & Applied Research SP6: Physical modelling of fuel behaviour (M. Bertolus, CEA) *resigned, replaced ad interim by M. Angiolini, ENEA resigned, to be replaced Coordinator: L. Malerba, SCK CEN Deputy coordinator: A. Bohnstedt, KIT Cross-cutting issues: J. Kalivodová, CVR 5

6 16 full participants + JRC in the Steering Committee (> 5 PY/Y declared, 3 k fee) CEA France 15 Chalmers Sweden 5 CIEMAT Spain 8 CNR Italy 6 CNRS France 6.3 CV Rez Czech Republic 10 ENEA Italy 16.5 HZDR Germany 6 JRC EU - MoU 7.5 KIT Germany 19 KTH Sweden 5.5 NCBJ Poland 6 NRG (ECN) The Netherlands 5 PSI Switzerland 7 SCK CEN Belgium 12.5 UKERC UK 6 VTT Finland 5.3 Participants: 47+JRC, 17 Countries 31 Associates: Industries, ex-full (< 5 PY/Y, 1 k fee, some are FM in other JPs) Aalto U. Finland VTT AGH Poland NCBJ COMTES FTH Czech. Rep. CVR CSIC Spain CIEMAT CSM (industry) Italy ENEA DLR Germany KIT EDF (industry) France CEA ETH Zürich Switzerland PSI ICCRAM Spain CIEMAT IFE Norway VTT (Finland) IIT Italy ENEA IMDEA Mater. Spain CIEMAT Inst. Physics, Zagreb Croatia SCK-CEN KU Leuven Belgium SCK-CEN METU Turkey UKERC (UK) MPA Germany KIT NNL UK UKERC OCAS (industry) Belgium SCK CEN POLIMI Italy ENEA POLITO Italy ENEA RATEN Romania JRC (EU) STUBA Slovakia CVR SUPSI Switzerland PSI TU Delft The Netherlands NRG TU Dresden Germany HZDR UA Spain CIEMAT UH Finland VTT UKAEA UK UKERC ULB (SCK CEN) Belgium SCK CEN UPC (CIEMAT) Spain CIEMAT UTMB France CEA 6

7 SP1 Materials for ESNII demonstrators and prototypes K.-F. Nilsson, JRC-IET Meeting of Fuel SPs of JPNM, Karlsruhe, November 19 th, 2015 Page 7

8 Support to ESNII priorities: construction of European GenIV front-runners Objective: Support Design, Licensing and Construction of ESNII prototypes and demonstrators MYRRHA (ADS), ASTRID (SFR), ALFRED (LFR) and ALLEGRO (GFR) Commercially available materials whose safe performance needs demonstration for the harsh Gen IV conditions austenitic steels (in particular 316SS for structural components and 15-15Ti for fuel claddings) ferritic-martensitic steels, mainly (9Cr, P91/T91) (nickel-based super alloys) coatings and other surface protection engineering Work is primarily pre-normative research Screening of candidate materials Test Procedures Design Codes

9 Support to ESNII priorities: construction of European GenIV front-runners Extension of the operational life to 60 years Extrapolation of laboratory data to operational conditions Gavrilov et al. SCK CEN Understand degradation in heavy liquid metal coolants and mitigation measures Integrity of Welded components

10 SP2 Innovative high temperature resistant steels M. Serrano, CIEMAT Meeting of Fuel SPs of JPNM, Karlsruhe, November 19 th, 2015 Page 10

11 High temperature resistant F/M steels for fuel cladding tubes Development of advanced steels Creep strength enhanced ferritic (CSEF) steels Oxide dispersion strengthened (ODS) Alumina forming Alloys Up to 180 dpa Hardening Up to 180 dpa Max 750ºC Swelling 100 MPa h. Creep Sodium, HLM Up to 750ºC Up to 180 dpa Max 750ºC RIS Coolant Diameter mm, Thickness mm, Several meters long 11

12 SP3 Refractory materials: ceramic composites, cermets and metal-based alloys A. Rinaldi, ENEA Meeting of Fuel SPs of JPNM, Karlsruhe, November 19 th, 2015 Page 12

13 Materials challenges for GFR & LFR GFR assets: Energy efficiency, Generation of process heat GFR clad requirements for safety No melting Leak tightness Structural integrity Heat transfer SiC f /SiC is the only material that fulfills most requirements LFR assets: Inherent high safety features LFR materials issues Corrosion/erosion of materials in lead implying strict control of temperature, dissolved oxygen & speed. Material innovation is required for pump impeller Emerging materials with promising capabilities are MAX phases (ternary carbides, e.g. Ti 3 SiC 2 )

14 SP4 Physical modelling and modelling-oriented experiments for structural materials C. Pareige, CNRS

15 Importance of physical modelling and modelling-oriented experiments High irradiation dose Temperature Structure & composition Synergies Non linear responses Different mechanisms at different length and time scales Aggressive environment Mechanical loading Physical understanding is key to predict the behaviour of materials under envisaged in-service conditions for safe design and operation of present & future nuclear reactors

16 Tools and approach: Multi-scale combination of modelling and experiments 1 c 1 y Time Experimental reactors Model irradiations with charged particles TEM, SEM Mechanical tests Embrittlement Environmental effects 1 s 1 ps Tomographic Atom Probe Positron Annihilation Atomic level properties Small Angle Neutron Scattering Displacement cascades Nanostructural & microchemical evolution Swelling Creep Molecular Dynamic Atomic Monte Carlo Crystal Plasticity Homogenization Dislocations Dynamics, Rate theory Object or Event Monte Carlo Continuum mechanics Electronic structure Ab initio Space 1 nm 1 m 1mm 1m

17 SP5 Synthesis, irradiation and qualification of advanced fuels J. Somers, JRC-ITU Meeting of Fuel SPs of JPNM, Karlsruhe, November 19 th, 2015 Page 17

18 Objectives of SP5 Development of specific fuels for specific reactors Fuel synthesis and characterisation Definition of fuel compositions Synthesis: modification of existing processes, new processes Fuel properties (U,Pu,Am 0.03,Np 0.01 )O 2 Irradiation testing Design and setting experimental conditions Instrumented experiments MTRs in Europe or other reactors beyond Post-irradiation examination Non-destructive and destructive examinations Modelling and Integration with SP6 Modelling of experiments Integration of results in fuel performance and safety codes

19 SP6 Physical modelling and separate effect experiments for fuels M. Bertolus, CEA Meeting of Fuel SPs of JPNM, Karlsruhe, November 19 th, 2015 Page 19

20 Modelling and Separate Effect Experiments for Fuels: What do we study? State-of-the-art experimental and modelling studies from atomic to grain scale on mixed fuels in normal and off-normal conditions Melting behaviour Fission product chemistry and release Microstructure changes under irradiation Mechanical integrity Melting temperatures Phase diagrams High temperature thermochemistry Thermal conductivity Transport properties of defects Gas segregation, precipitation and release Non-gaseous fission product behaviour and compounds Chemical interaction with cladding Consequences of irradiation damage Creation and behaviour of extended defects (cavities, dislocations) Role of grain boundaries Mechanisms governing mechanical properties Creep Fracture Page 20

21 Way of functioning Description of Work Vision Paper & Roadmap Collection of all activities of relevance over a period of five years in each SP, leading to results that belong to the JPNM, i.e. shared results: from Euratom funded projects to national programmes. Provide the position of the JPNM on the energy and nuclear energy arena, the challenges and the pathway to address them. VP available at JPNM website. Roadmap in preparation. Task Forces (TF) Groups of experts appointed to provide specific answer to a question, delivering a report. In charge for ~1 year. Joint Technical Teams (JTT) Pilot Projects (PP) Scientific community involved in each SP that meets regularly in targeted workshops or other meetings to monitor and share results and discuss collaboration. Small projects (~2-3 M ) focused on precise topics included in DoW that result from convergence of plans of a few labs from different MS. Typical duration: 3-4 years. Pilot projects are the main instrument used by the JPNM to align national programmes in EERA 21

22 23 Pilot Projects: Total value ~48 M Total PY ~332 Several PPs involve 2 SPs Pilot projects call 2015: Result SP5; 3.49 M SP6; M SP4; 7.44 M SP1; M Budget per SP SP3; 5.60 M SP2; 5.66 M PY per SP SP5; 15 SP4; 52 Modelling of SM SP6; 74 SP3; 63 S. materials for prototypes SP1; 85 SP2; 43 Approved PP started on institutional funding (to be monitored in 2017) Some MAY receive partial EC funding from mid-2017 Next PP call probably in

23 International position The EERA JPNM is not yet clearly known outside Europe, but Americans, Koreans & Japanese start to become aware of it A few PP include US partners; a Korean institute participates in MatISSE; American reviewers were used for PPs: the JPNM research received appreciation as being of high international standard Publications appear with EERA JPNM mentioned in the acknowledgments INERI scheme will be made use of in the M4F proposal If the EERA JPNM participates together with OECD-NEA in the organisation of SMINS 2016, workshop on Structural Materials for Innovative Nuclear Systems (which we can sponsor via MatISSE), we ll get a clear international status MoU with OECD Recently, some international resonance was obtained with the joint NuFuel & MMSNF 2015 (Materials Modeling and Simulation for Nuclear Fuels) workshops NuFuel = European workshop on nuclear fuel, annual meeting for SP5&6 23

24 Thank you for listening Any question? 24