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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.
Author | AFCEN |
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Editor | AFCEN |
Document type | Rules |
Format | File |
ICS | 27.120 : Nuclear energy engineering
|
Year | 2007 |
Country | France |
Keyword | AFCEN rccm rccmr RCC-MR (MRx) |