JP Nuclear Materials The Joint Programme for Nuclear Materials - JPNM Sub-programme1: Support to ESNII Karl-Fredrik Nilsson(JRC-IET) EERA JP MS Stakeholder Meeting 10 th of September 2014, Brussels

JP Nuclear Materials Objectives in line with ESNII priorities: Construction of GenIV front-runners Support Design, Licensing and Construction of ESNII prototypes and demonstrators − MYRRHA, ASTRID, ALFRED and ALLEGRO Short-term perspective! Commercially available materials whose safe performance needs demonstration for the harsh Gen IV conditions − austenitic and ferritic-martensitic steels − nickel-based super alloys Work is primarily pre-normative research: − Screening of candidate materials; − Test Procedures; − Design Codes. Work Programme is based on engineering priorities from reactor designers and developers

JP Nuclear Materials Basic Challenges & Requirements Materials and components need to operate safely in harsher environment − High temperatures; − High Irradiation levels; − Coolant compatibility. Other Requirements, e.g. − Design Life > 60 years; − Cost; − In-service Inspection; − Decommissioning and Waste Management.

JP Nuclear Materials SP1 Materials Coatings −wear and corrosion resistance Ti exposed to PbBi at 550°C Al-surface coated alloyed steel exposed to PbBi at 550°C Ferritic-Martensitic steels; −Grade 91 structural components Austenitic steels − 316 SS structural components − 15-15Ti Fuel cladding Nickel-based superalloys; −800H, Inconel 617 structural components Also fusion + non-nuclear Also LWR+ non-nuclear Also HTR+ non-nuclear 15-15Ti Fuel Pin irradiated pristine

JP Nuclear Materials SP1 Related activities - EURATOM EURATOM funded project MATTER (2011 – 2014) − Pre-normative test procedures (miniature tests and environmental effects) − Design Code Development (high temperature and 60 years design life) − Welding of ferritic-martensitic steel components (procedures and assessment) Small Punch Test EURATOM Budget ~8 M€, EC/MS = 50/50

JP Nuclear Materials SP1 Related activities - EURATOM EURATOM funded project MaTISSE (2014 – 2017) − Creep-fatigue of F-M and austenitic steels (cyclic softening and crack propagation) − Functional coatings and modified surface layers − Fuel-cladding interaction (chemical and mechanical) − Environment Assisted Degradation of materials in liquid lead alloys clad fuel EURATOM Budget 2M€, EC/MS = 50/50, but significant additional national in-kind funding

JP Nuclear Materials SP1 Related activities – Pilot Projects Linked to MaTISSE − Creep-fatigue of F/M and austenitic steels with emphasis on cyclic softening for P91 and crack propagation (ILAM-CF); − Functional coatings and modified surface layers (SAFE-COAT); − Fuel-cladding interaction for Advanced Nuclear Systems (FCI-ANS); − Investigation of Environment Assisted Degradation of materials in liquid lead alloys (IEAD-LL). These Pilot Project support the MaTISSE Projects by additional resources from national programmes

JP Nuclear Materials SP1 Related activities – Pilot Projects Stand-alone projects −Testing and ASsessment methodologies for material characterization of thin-walled cladding TubEs (TASTE) (started 2014) −Integrity of nuclear welds with emphasis on residual stress assessment (INuW-Res). (final preparation) Ring-tensile Ring-compression Segmented cone-mandrel

JP Nuclear Materials Some Future R&D Challenges Methodology* to predict long-term degradation by extrapolation of accelerated tests to operational conditions − Creep, irradiation effects, environmental effects, thermal ageing,… Methodology* to predict and mitigate material degradation in lead and lead-bismuth − Corrosion, liquid-metal embrittlement. ………. Development of innovative miniature tests for material characterization − Small Punch Test, nano-indentation, ….. * Methodology = Design Codes, Assessment Codes and Test Procedures