Nuclear Materials Research in EU: present status and future perspectives Concetta Fazio

Transcription

1 Seminar on Generation IV Nuclear Energy Systems Risø, Denmark October, 2012 Nuclear Materials Research in EU: present status and future perspectives Program Nuclear Saftey Research KIT Universität des Landes Baden-Württemberg und nationales Forschungszentrum in der Helmholtz-Gemeinschaft

2 Outline Evolution within SNETP Materials R&D needs: can cross-cutting items be identified? Evolutions within the European Energy Research Alliance (EERA) Joint Program Nuclear Materials (JPNM) Results: JPNM and relevant FP7 projects Future prospect October 2012

3 Evolution within SNETP NUGENIA NC2I NUGENIA: NUclear GENeration II & III Association NC2I: Nuclear Cogeneration Industrial Initiative EERA JPNM ESNII ESNII: European Sustainable Nuclear Industrial Initiative SFR (ASTRID) LFR (MYRRHA, ALFRED) GFR (ALLEGRO) October 2012 Nr.

4 Materials research needs: can crosscutting items be identified? Operational parameter driven LWR - NUGENIA (8 technical areas)* areas related to materials: Integrity assessment and aging (SCC) n.b. aging is also related to higher dose Fuel waste management and dismantling (new cladding material here included) HTR NC2I materials R&D need high strength at high temperature application corrosive environment FR ESNII high fuel-burn up (cladding) and high dose / dose rate high temperature corrosive environment *Topics taken from V. Prunier SNETP GA Warsaw Nov 29, October 2012

5 Cross-cutting R&D: parameter driven however High temperature window NC2I ESNII (GFR) however Different neutron spectra and dose rate Chemical Environment: corrosion NUGENIA (SCC) NC21 (He) ESNII (He, Na, HLM) Different chemistries (even different among HTR and GFR) Irradiation damage: doses NUGENIA (aging) ESNII however Different neutron spectra and dose rate October 2012

6 Cross-cutting R&D: driven by classes of materials Austenitic steels ESNII, NUGENIA F and F/M steels NUGENIA (F), ESNII, NC2I Ni alloys ESNII, NUGENIA, NC2I ODS alloys beyond ESNII SiCSiC NUGENIA(?) beyond ESNII October 2012

7 Cross-cutting R&D: driven by classes of materials however Austenitic steels F and F/M steels Ni alloys ODS alloys SiCSiC ESNII, NUGENIA NUGENIA (F), ESNII, NC2I ESNII, NUGENIA, NC2I beyond ESNII NUGENIA(?) beyond ESNII The components thus the operational window are essential parameters to be considered in this frame: Grade properties required etc October 2012

8 Generic Cross-Cutting R&D items* *The objective of this table is to start the discussion and it is by far not complete Classes of material NUGENIA ESNII NC2I Austenitic steels AISI 316 (L, L(N)) Internals Vessel/Internals/SG Internals? AISI 304 Internals - - AISI 308 RPV clad (or liner) Cr-15Ni Ti stab 321 Ti stab - Piping (D-BWR) Fuel cladding - Ferritic and Ferritic / Martensitic steels Low alloy Ferritic RPVessel - - 9Cr F/M - Vessel/Wrapper/SG Vessel Alloy 800 / 690 Steam Generator, penetrations Ni Alloys - - Alloy 800 H / Haynes Steam Generator Steam Generator Other materials ODS / SiCSiC SiCSiC/fuel clad(?) SiCSiC/fuel clad (GFR) ODS fuel clad (SFR/LFR) October 2012

9 Generic Cross-Cutting R&D items Classes of material NUGENIA ESNII NC2I Austenitic steels AISI 316 (L, L(N)) Internals Max T < 300 C B/P water (water chemistry Irradiation dose: low flux high fluence Vessel/Internals/SG: T up to 550 C LM or gas chemistry Irradiation dose: high flux high fluence Internals? T up to 900 C Gas chemistry Irradiation dose low flux high fluence The identification of cross-cutting items implies: The knowledge of the reactor design The component design The component operational conditions (Temperature, loads, doses, chemical environment) October 2012

10 Generic Cross-Cutting R&D items The output of such an analysis might show that generic materials data / materials performance knowledge might be considered as cross-cutting e.g.: Investigation of Microstructural / Metallurgical changes under thermal aging (wide temperature range) -> use of advanced investigation techniques Mechanical performance in a wide temperature range (without environmental effects) -> development of small size specimen testing for standardisation Irradiation behavior in a wide irradiation dose and temperature range (energy/ flux - fluence effects to be considered) First principle approaches for the development of predictive models Experiences in fabrication and manufacturing of components (including forming and welding) Generic experiences on environmental effects / corrosion and environmental properties degradation of materials October 2012

11 Materials R&D needs for implementation However, dedicated test programs are needed for the materials selection validation: Operational and Safety margins to be identified Reactor specific Component specific How to identify the generic and the dedicated R&D programs: A workshop(?) with different group of materials, reactor/component designer and safety experts with the objective to create such a program October 2012

12 Wind energy Photovoltaic Concentrated Solar Power Geothermal energy Electricity storage Electricity grids Bioenergy Carbon capture and storage Hydrogen and fuel cells Nuclear fission Buildings And as further step: Synergies with other low carbon energy technologies Structural materials Fibre reinforced materials X X X X X High temperature, low temperature and corrosionresistant materials X X X X X X X Structural steel components and related joining techniques X X X X X X X Advanced concretes X X X X X Functional materials Separation membranes X X X X Catalyst and electrolytes X X X X High temperature superconducting materials X X High temperature heat storage materials (High temperature) insulating materials X X X Materials for power electronics X X X X X X X X X X Heat transfer fluids X X X Manufacturing techniques Coatings and coating techniques X X X X X X X X X X Condition monitoring techniques X X X X X X X October 2012

13 EERA Joint Program Nuclear Materials Objectives Address and solve key issues within the main identified research themes (Material development and screening; Experimental characterisation and qualification/validation; Fabrication issues (welding, joining, etc); Pre-normative Research). Availability of appropriate structural and clad materials which are able to withstand severe conditions and requirements foreseen for Gen-IV systems (high temperature, high fuel burn-up, long life time, corrosive environment). Reach scientific excellence in materials science, both in the experimental and first principles modelling areas. Support EII launched for nuclear energy and more in general the implementation strategies October 2012

14 EERA Joint Program Nuclear Materials JP on Materials for Nuclear (, KIT) SP1 Support to the European Sustainable Nuclear Industrial Initiative (ESNII) Karl Fredrik Nilsson, JRC MATTER Project GETMAT Project MatISSE proposal SP2 Oxide Dispersed Strengthened (ODS) Steels Yann de Carlan, CEA GETMAT Project MATTER Project MatISSE proposal SP3 Refractory materials: ceramic composites and metal-based alloys Marie-Francoise Maday, ENEA MatISSE proposal SP4 Modelling: Correlation, Simulation and Experimental Validation Lorenzo Malerba, SCK-CEN GETMAT Project MatISSE proposal October 2012

15 Brief summary of EURATOM FP7 projects GETMAT MATTER and link to the Joint Program Nuclear Material October 2012

16 WP1: Metallurgical and mechanical behaviour F/M ODS ODS WP2: Materials compatibility with coolant ODS steel Fusion Welding TIG (filler wire) EB (without filler) Solid State Welding Diffusion Explosive EMP Friction Stir Oxidation in He Oxidation in LBE Oxidation in SCW WP3: Irradiation behaviour of Structure materials PIE Program Experiment Environment Spectra Matrix/Phénix Na fast neutron Lexur/BOR 60 Pb, gas fast neutron ASTIR/BR2 LBE, gas mixed neutron IBIS,SUMO/HFR LBE, Na mixed neutron STIP/SINQ gas proton/neutron MEGAPIE LBE proton/neutron WP4: Multiscale modelling and model experiments Pure Fe Fe-7%Cr Fe-12% Cr [110] [111] Cluster of self-interstitials in Fe and FeCr alloys. Green = Fe, blue = Cr, red = lattice site October 2012

17 Coordinator of MATTER: P. Agostini ENEA, Italy DM3: EERA JPNM Scheme, implementation and priorities Coordination and Management of the JPNM; Provide guidelines for JPNM implementation; Update description of Work Follow up of experimental results of DM1 and DM2 -> belonging to SP1 (Support to the European Sustainable Nuclear Industrial Initiative (ESNII)) of JPNM DM1: Development of test & evaluation guidelines for structural materials DM2: pre-normative R&D for codes and standards Investigated systems MYRRHA ASTRID Key issues addressed Identification of key properties to be investigated; Develop or update existing guidelines; Round robin exercises; Analytical and physically-based support; Screening test techniques that can address specific questions October ODS Investigated materials AISI 316LN 9Cr-1Mo Key issues addressed Ratcheting 60 years lifetime duration Creep and creep-fatigue Weldability Integration of current industrial practices

18 SP1 Support to ESNII Validation and (pre)-normative research on materials selected for ESNII facilities Classes of materials 9Cr Ferritic / martensitic steels Austenitic steels Ni - alloys GETMAT: Post irradiation examination of 9Cr F/M steels MATTER: Pre-normative research on 9Cr F/M and austenitic steels; corrosion effects in HLM MatISSE Proposal: Fuel/clad interaction, creep-fatigue tests and corrosion protection October 2012

19 GETMAT PIE Program Tasks T3.1 T3.2 T3.3 T3.4 T3.5 T3.6 Experiment/ Reactor Spectra Materials Tests Examinations Irradiation Temperature Dose Range BOITIX9 and SUPERNOVA Phenix Fast neutrons EM10 (9Cr-1Mo) MA957 ODS Tensile Impact CT TEM STIP 4-5 SINQ High energy protons and neutrons 9-12 Cr Welds ODS (9-20Cr) Tensile Bending Charpy, SPT TEM C C dpa dpa MEGAPIE High energy protons and neutrons T91 SS 316L Tensile, Bending, SPT, SIMS, XPS, XRD SEM, TEM C (T91 beam window) ~7 dpa (T91 beam window) Environment Na Inert gas Pb-Bi ASTIR BR2 Thermal & fast neutrons T91, SS316L CT, tensile C LEXUR II BOR60 Fast neutrons T91, T91 coated 15-15Ti SS316L Tensile Corrosion Pressurized tubes 350 C (LBE): 316L, T91, 15-15Ti 550 C (Pb): T91,T91 coated ODS 14Cr IBIS & SUMO HFR Thermal & fast neutrons T91, Eur-ODS T91 coated, SS316L, welds Tensile KLST SEM, TEM 300, 500 C ~ 2.5 dpa Up to 16 dpa 2 dpa PWR water, tests in LBE Pb, LBE Pb-Bi Na (SUMO) Partners CEA PSI, CEA PSI, CEA, CNRS, KIT, SCK-CEN, ENEA SCK-CEN ENEA SCK-CEN NRG October 2012

20 SP2 ODS as fuel clad for innovative FRs Operational conditions of clad in e.g. SFR Temperature: 400~700 C Irradiation doses: higher than 150 dpa Applied stress: 100 MPa (%) Average 316 Ti Average 15/15Ti Best lot of 15/15Ti Phénix Courtesy Y. de Carlan, CEA Ferritic-martensitic (F/M) 2 steels, ODS included 0 dose (dpa) GETMAT: 9Cr-ODS, 12Cr-ODS, 14Cr-ODS production, analysis of welds and characterization at high temperature, in environment MATTER: Characterization of ODS production routes MatISSE: Metallurgical characterization of GETMAT ODS and 14Cr ODS tubes characterization October 2012

21 SP3: SiCfSiC examples of issues Non linear response to thermomechanical sollicitations dependant from SiCf/SiC architecture, constituents, type of sollicitation. Thermal conductivity drops with Matrix cracking and irradiation SiCf/SiC shows Matrix cracking in the elastic domain 3 domains related to damage occurrence in the composite Leak tightness is lost with Matrix cracking: can be addressed through the sandwich concept (CEA) Source: M. Le Flem, CEA October 2012

22 SP4 Modelling, experiments and validation Molecular dynamics Kinetic Monte Carlo Mean-field models Dislocation dynamics Crystal plasticity Ab initio & potentials Info collectorexchanger Tests on technological materials Tests on model alloys Microstructure studies Semi-empirical correlations Artificial intelligence Use of information to: Get global picture and make decisions Design new experiments Refine specific models Finite element calculations Phase field models October 2012 Thermodynamic packages Courtesy L. Malerba, SCK-CEN

23 What is the future prospect? At present a project proposal for EURATOM FP7 WP2013 is under preparation. The name of the proposal is Materials Innovation for Safe and Sustainable nuclear Energy (MatISSE) The proposal is made out of five Work Packages 1. Modelling activities Deepen investigation on irradiation hardening of F/M alloys Investigation on irradiation induced creep 3. SiCSiC SiCSiC sandwich tube fabrication and correlation between their mechanical properties / leak tightness and microstructure Thermal property characterisation and compatibility with He October 2012

24 What is the future prospect? At present a project proposal for EURATOM FP7 WP2013 is under preparation. The name of the proposal is Materials Innovation for Safe and Sustainable nuclear Energy (MatISSE) The proposal is made out of five Work Packages 3. ODS Role of microstructure on the mechanical behavior Characterization of ODS cladding tubes in normal operation and under safety relevant conditions 4. Support to ESNII Creep-fatigue of austenitic and martensitic steels Functional coatings and modified surface layer Fuel cladding interaction Environmental assisted degradation of materials in liquid metals October 2012

25 What is the future prospect? At present a project proposal for EURATOM FP7 WP2013 is under preparation. The name of the proposal is Materials Innovation for Safe and Sustainable nuclear Energy (MatISSE) The proposal is made out of five Work Packages 5. Coordination and Support Action to build enforce the integration of the research program through the definition of a legal entity Selection of best option legal entity Definition of management and governance structure Financial aspects and business plan Road-map and Strategic research agenda: materials, fuel and facilities Training, Education, Networking, Communication, Dissemination October 2012

26 Thank you for your attention October 2012

27 Back-up The RPVs are exposed to fast neutron fluxes (E>1.0 MeV) in the range of 10 12, corresponding to atomic displacement rates in the range of displacements per atom (dpa)/s October 2012

28 JPNM Partners and resources Sub-programme SP1 - Support to the European Sustainable Nuclear Industrial Initiative SP2 - Oxide Dispersed Strengthened (ODS) Steels SP3 - Refractory materials: ceramic composites and metal-based alloys SP4 - Modelling: Correlation, Simulation and Experimental Validation Resources Person*year ~ 59 ~ 41 ~ 14 ~ 20 Total Resources ~ 144 Participants: CEA, CIEMAT, CNR, CNRS ENEA, HZDR, JRC, KIT, KTH, NRG, INR, PSI, RCR Ltd, SCK-CEN, UKERC, VTT Associated: IFE, POLITO, MPA Stuttgart, EDF, CSM, Uni Alicante, Poli Catalunya October 2012