Shaping the rules for a sustainable nuclear technology How to introduce new materials in design codes Cécile PÉTESCH RCC-MRx chairwoman CEA - Senior Expert in design codes and standards for mechanical components SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 1 Shaping the rules for a sustainable nuclear technology Design codes vs new material Why? Interest to connect R&D to standardisation What? Example of RCC-MRx code How? Difficulties to introduce a new material Conclusion SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 2 Shaping the rules for a sustainable nuclear technology Design codes vs new material Why? Interest to connect R&D to standardisation What? Example of RCC-MRx code How? Difficulties to introduce a new material Conclusion SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 3 Why? Codes and standards Modification request Material file Nuclear Industry New Material SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 4 Why? Codes and standards DMRx Material file REGULATOR New Material SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 5 Why? For innovative reactors, standardization is one way to reach a highest technology readiness level, giving a frame and a direction for research Need for the users to have a public document as a tool for discussion with other developers, industries, regulators, notified bodies or third parties A more and more strong willingness of the users to be involved in the developments of rules adapted to their needs The earlier the standardization is integrated in the design process, the easier to transfer a concept to an industrial component is SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 6 Shaping the rules for a sustainable nuclear technology Design codes vs new material Why? Interest to connect R&D to standardisation What? Example of RCC-MRx code How? Difficulties to introduce a new material Conclusion SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 7 What? RCC-MRx: DESIGN & CONSTRUCTION RULES FOR MECHANICAL COMPONENTS OF NUCLEAR INSTALLATIONS: HIGH TEMPERATURE, RESEARCH AND FUSION REACTORS VOLUME I VOLUME II VOLUME III VOLUME IV VOLUME V Design Materials Examination Welding Manufacturing Methods operations SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 8 What? RCC-MR Design & Construction Rules 1985 -1993 – 2002 – 2007 Mechanical Components High-Temperature Indian ITER Vacuum Experimental Vessel PFBR RCC-MR 2007 edition Fusion RCC-MR 2002 edition Nuclear Installations 2012 – 2015 - 2018 RCC-MX 2005 – 2008 MYRRHA ASTRID Primary Cooling European Spallation Source Jules Horowitz Reactor system target SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 9 What? RCC-MRx 2018 structure RCC-MRx Scope Common Section I (RDG) • Materials and Design rules have part • General provisions • Entrance Keys – Applicable sts of rules been extended in order to be • Equipment specification • Management system applicable for nuclear components Section II (REC) likely to operate: Additional requirements For class 3 components – in creep conditions (significant creep) • application of Standard NF EN 13445 • application of Standard NF EN 13480 Optional • application of Standard NF EN 1993-1-1: EUROCODE 3 – in irradiated conditions (significant Special requirements parts • French regulation ESP/ESPN irradiation) • European regulation REACH Section III Negligible creep curve Tome 1 : DESIGN Tome 2 (RM): MATERIAL PROCUREMENT SPECIFICATIONS Negligible Irradiation Negligible Irradiation Tom e 3 (RMC) : TESTING AND Negligible creep Significant creep EXAMINATION METHODS Negligible Technical irradiation Tome 4 (RS) : WELDING modules curve Significant Irradiation Significant Irradiation Tome 5 (RF) :FABRICATION Negligible creep Significant creep Tome 6 (RPP ) : Probationary Phase rules Maximum irradiation curve Multi-reactor type (SFR – RR – FR – GEN IV) SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 10 Shaping the rules for a sustainable nuclear technology Design codes vs new material Why? Interest to connect R&D to standardisation What? Example of RCC-MRx code How? Difficulties to introduce a new material Conclusion SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 11 How? RCC-MR RCC-MR RCC-MRx RCC-MRx RCC-MRx 1983-2002 2007 2012 2018 XXX Fast Neutron Fast Neutron Fast Neutron Fast Neutron Reactors Reactors Reactors Reactors Fast Neutron ITER ITER ITER Reactors Vacuum Vessel Vacuum Vessel Vacuum Vessel ITER Irradiation Irradiation Vacuum Vessel Facility Facility Irradiation Facility Innovative Coolant Innovative Coolant ?? SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 12 How? •Non conventional systems •Common approach to Code Innovative be adapted organisation concept •Diversity of the research world •No industrial feedback • New damages Innovative Probationary • New designs components Phase • New rules Rules •Damages to be identified •Behavior of materials to Code Innovative be evaluated coolants opening •Adequacy of the rules questionable •To be characterised Innovative •To be industrialised materials Guideline •To be standardised Needs for innovative/research concept SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 13 How? Prior to the code In the code • Pre-codification step • Define a material prior to its introduction in a code • Based on mechanical Procurement tests • Second step of the code • First step of the code • Define the component • Demonstration of the using the material conformity of the properties Characterisation selected material to • Based on design data the code materials • Chemical composition • Based on mechanical • Fabrication main tests Design parameters • Mechanical properties Stability , reproductability Introduction of a new material in RCC-MRx Material: general process SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 14 How? Introduction of a new material in RCC-MRx : Material file required • The use of new materials and products shall be Prior to preceded by a Material File including: the code – Technical Qualification Report (RB 2210 - RM 014-0) on the part or product qualification and on the shop qualification , if required by the Equipment Specification , – new Reference Procurement Specification (s) with the same table of contents as the present RPS in Tome 2, possible with a reference to a published product standard, – if necessary a new Properties Group (A3 and A9) with the same table of contents as the present Properties Groups. SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 15 How? The table of contents of the Material File shall be: 1. Introduction - Presentation of the grades Prior to - Codes and standards dealing with these parts or products the code - Reference Procurement Specifications in Tome 2 - Industrial application and experience 2. Physical properties 3. Base metal and welded joints mechanical properties for design and analysis - Justification of the applicability of the Design Rules (RB 3000) for the specified usage conditions - Basic mechanical properties - Mechanical properties when creep is significant (if necessary) - Mechanical properties when irradiation is significant (if necessary) - Guaranty of the consistency between the properties of the final part laid-on the plant and the material properties used to design the component 4. Manufacturing - Industrial experience - Metallurgy 5. Fabrication - Industrial experience - Forming operation ability 6. Welding - Weldability (RS 1300) - Industrial experience for the welding procedure qualification - Industrial experience for the repair welding procedure qualification 7. Controllability 8. In service behavior - Thermal ageing, corrosion, erosion-corrosion, irradiation, … SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 16 How? Reference Procurement Specification Contents of a RPS In the code ! Welding Fabrication SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 17 How? new Properties Group Prevention of: Design data In the code - Excessive strain Yield stress - Plastic Instability Tensile strength Tensile stress-strain curves - Progressive strain Cyclic curves Fatigue curves - Fatigue - Creep Creep strain curves - Irradiation Same data in irradiated states - Fast fracture JIC and J-R curve, fatigue crack growth curve A3/A9 properties SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 18 How? The table of contents