1. www.eera-jpnm.eu www.eera-set.eu EERA is an official part of the EU SET-Plan. http://setis.ec.europa.eu/ Austenitic and Ferritic-Martensitic steels for ESNII prototypes: open issues, challenges and JPNM SP1 work-programme First ESNII+ Workshop on Joint Programming 22 and 23 October 2015, Brussels K-F Nilsson, JPNM Sub-programme coordinator JRC, Institute for Energy and Transport Karl-fredrik.nilsson@ec.europa.eu

2. www.eera-jpnm.eu Intro EERA JPNM Sub-programme 1 Objectives General requirements Materials Work Programme 2011 - 2015 Priorities Work done and achievements Work Programme from 2016 - Priorities Planned Activities (Pilot Projects) Conclusions Outline

3. www.eera-jpnm.eu Objectives Support Design, Licensing and Construction of ESNII prototypes and demonstrators ‒MYRRHA, ASTRID, ALFRED and ALLEGRO Short-term perspective! 2025 Commercially available nuclear materials whose safe performance needs demonstration for the harsh Gen IV conditions − austenitic and ferritic-martensitic steels − nickel-based super alloys Work Programme is based on engineering priorities from reactor designers and developers www.eera-set.eu

4. www.eera-jpnm.eu Why and how? www.eera-set.eu But we need to demonstrate that these materials and components operate safely in harsher environment ‒Resist higher temperature; ‒Resist higher irradiation levels; ‒Resistant to degradation from coolant; ‒Design life > 60 years. Why use "commercial" nuclear materials? − Industrial experience and qualified for nuclear applications − Cost low and predictable; Work is primarily pre-normative research: − Screening of candidate materials; − Development Test Procedures; − Updated Design Rules and Codes.

5. www.eera-jpnm.eu SP1 Materials www.eera-set.eu 15-15Ti 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 15-15Ti Fuel Pin irradiated pristine Coatings; − Wear and corrosion resistance

6. www.eera-jpnm.eu Work programme 2011-15 Emphasis on P91 Ferritic-Martensitic Steel Bulk of joint work was performed as part of the MATTER project and support to the "front-runners" ASTRID and MYRRHA Two main areas: ‒Development of Test Procedures o miniature tests o HLM environmental effects ‒Design Rules o High Temperature (creep-fatigue, negligible creep, ratcheting) o Weld procedures and coefficients o 60-years design life (thermal ageing)

7. www.eera-jpnm.eu Work programme 2011-15 The main conclusions regarding for ESNII design are summarized in the MATTER Deliverable D9.1: The Relevance of MATTER results for the Design of the ESNII Reactors"

8. www.eera-jpnm.eu MATTER Achievements Miniature test such as small punch test and nano-indentation can be used to screen materials Test procedures have been developed for tests in HLM (e.g. pre-wetting and very careful reporting and control) Small punch test LBE & air T91 Nano-indentation hardness, unirradiated, radiated ions and neutrons Crack growth resistance P91 (JR-curve in LBE and air)

9. www.eera-jpnm.eu MATTER Achievements A large set of consistent corrosion data for 316L and P91 P91 is rules out as for structural components in HLM due to liquid Metal embrittlement Gavrilov (SCKCEN) Load-displacement fracture test Corrosion mechanisms vs. oxygen content and temperature T91 Ductility vs. temperature in air and LBE

10. www.eera-jpnm.eu MATTER Achievements New Proposed Design Rules for ratchetting, creep-fatigue and negligible creep for P91 New weld factors for weld P91 New efficiency diagram proposed for P91 steels Negligible creep curve P91 Computed strain evolution in weld Fatigue curves weld and base material

11. www.eera-jpnm.eu SP1 Related activities - EURATOM EURATOM funded project MaTISSE (2014 – 2017) ‒High temperature degradation (cyclic softening and crack propagation) ‒Evaluation of functional coatings (from laboratory to industrial scale) ‒Fuel-pin integrity: fuel-cladding interaction (chemical and mechanical) ‒Environment Assisted Degradation of materials in liquid lead alloys www.eera-jpnm.eu clad fuel EURATOM Budget 2M€, EC/MS = 50/50, but significant additional national in-kind funding

12. www.eera-jpnm.eu SP1 Related activities – Pilot Projects Stand-alone Pilot Projects ‒Evaluation of test procedures for thin-walled cladding tubes (TASTE) (started 2014) ‒Integrity of nuclear welds with emphasis on residual stress assessment (INuW-Res). www.eera-jpnm.eu Ring-tensile Ring-compression Segmented cone-mandrel

13. www.eera-jpnm.eu Directions for Work Programme 2016 - Emphasis on austenitic steels: 316L(N), 316L; 15-15Ti Methodology* to predict and mitigate material degradation in lead and lead-bismuth − Corrosion, liquid-metal embrittlement, material data ………. Methodology 60 years Design-Life Methodology life assessment welded components, e.g type IV cracking − Residual stresses, material properties of welds, weld defects, weld procedures, * Methodology = Design Codes, Assessment Codes and Test Procedures

14. www.eera-jpnm.eu Directions for Work Programme 2016 - High-temperature: degradation and life assessment − Creep-fatigue, thermal fatigue, thermal buckling (MATTER iso-thermal conditions), long-term material data, non-isothermal Development of innovative miniature tests for material characterization − Small Punch Test, nano-indentation, ….. Safety margins beyond design cases − High temperature material properties, Dynamic loads, nonlinear deformation, rate effects, material data, fuel-pin * Methodology = Design Codes, Assessment Codes and Test Procedures

15. www.eera-jpnm.eu Proposed SP1 Pilot Projects CERBERUS: Corrosion ERosion BEhaviour of nucleaR materials in heavy liqUid metal coolantS −Liquid Metal Corrosion (LMC) for austenitic and feritic-martensitic steels included coatings and welds and MaxPhase −Test procedures, data, life-predictions WELLMET: Corrosion ERosion BEhaviour of nucleaR materials in heavy liqUid metal coolantS −Liquid Metal Embrittlement & weld qualification for 316L welded component in HLM −Test Procedures, Quantify LEM degradation, Design Methodology MOSEL (SP1&4) −Modelling of LME MOLECOS (SP1&4) −Modelling of LMC

16. www.eera-jpnm.eu Proposed SP1 Pilot Projects RESTRESS: Assessment of residual stresses for nuclear components and its impact on weld integrity −MATTER 316L and P91 welded components −Residual stress measurement and computation, RS mitigation ALCORE: Alumina forming steels and modified surface layers for lead-cooled fast reactors (SP1&2) − Development of HLM resistant steels NINA: Nano-indentation for Nuclear Application (SP1,2,4) −Test procedures and applications of nano-indentation SLIPLOC: SLIP LOCalization in irradiated steels and consequences on mechanical damage (SP1&4) FRACTO: Fracture Mechanics Testing of Ferritic/Martensitic and ODS Steels (SP1&2)

17. www.eera-jpnm.eu Not included in Pilot Projects Design and Assessment Methodology for 60-years Design life is a key issue but not included as PP −must be to a large extent be based on testing and characterization of components exposed to long-term service conditions −accelerated tests + physics based model that include the degradation mechanisms to extrapolate to operational conditions To address this a Task Force has been proposed. −Synthesis of knowledge ageing mechanisms; −Review existing data and agree on how data can be shared; −Propose an Activity e.g. Pilot Project Members of this TF should include reactor designers and operators, experimentalists, design code specialists, and modellers Kick-off meeting September 21 in Paris.

18. www.eera-jpnm.eu Conclusions The work in EERA JPNM 1 addresses Materials for ESNII demonstrators and prototypes The Work Programme is therefore based on ESNII priorities The work is mainly pre-normative We welcome an even closer interaction with designers of ESNII. The Work Programme 2011-2015 has to a large extent been based on the EURATOM projects MATTER and MATISSE much focus on 9%Cr Ferritic-Martensitic Steels Significant progress done with respect to Test Procedures and Design Rules

19. www.eera-jpnm.eu Conclusions The Work Programme from 2016 is an evolution of the previous work. Key areas are: HLM degradation and life assessment 60-years Design-life Welded components Other areas include: −Miniature specimens −High temperature life assessment The concrete work plans for most of the areas have been worked out as Pilot Projects

20. www.eera-jpnm.eu Thank you for listening Any question?