Design and Construction Rules for mechanical components of nuclear installations : high-temperature, research and fusion reactors
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Purpose and scope
The RCC-MRx code was developed for sodium-cooled fast reactors (SFR), research reactors (RR) and fusion reactors (FR-ITER).
It describes the rules for designing and building mechanical components involved in areas subject to significant creep and/or significant irradiation. In particular, it incorporates an extensive range of materials (aluminium and zirconium alloys in response to the need for transparency to neutrons), sizing rules for thin shells and box structures, and new modern welding processes: electron beam, laser beam, diffusion and brazing.
A new edition of the RCC-MRx code was released in 2015. This edition reflects feedback on the use of the 2012 edition and/or its 2013 addendum, especially in current projects and mainly the Jules Horowitz reactor and the Astrid project. Examples include the inspection and welding procedures for aluminum, as well as the code’s improvements and new structure relating to components used at high temperatures (design rules, welded assemblies and material properties). Initial feedback on the code’s application also helped analyze and integrate additional data on the Eurofer material used by the fusion community.
Furthermore, this edition pays special attention to ensuring consistency between RCC-MRx and the other reference documents that interact with the code, including RCCM, European and international standards.
An erratum for RCC-MR 2007, RCC-MRx 2012 and 2015 has been published, it is available for download here after : Erratum Appendix A16.
An erratum for RCC-MRx 2012 has been published, it is available for download here after :
RCC-MRx 2015 - ENDesign and Construction Rules for mechanical components of nuclear installations : high-temperature, research and fusion reactors
Erratum RCC-MRx 2015 appendix A16 - ENDesign and Construction Rules for mechanical components of nuclear installations : high-temperature, research and fusion reactors
Let’s take part in codes update
AFCEN codes continuously improve considering experience feedback of code users. Do you have a question about interpretation of one code paragraph ? Do you propose a code modification ? or you simply want to share with the industry your experience feedback ? The floor is yours. You may download the corresponding form, fill it and then send it to the concerned sub committee who provides answer. Our target is to answer 100% of request within a delay no longer than 3 months.