Introduction
Below is a practical workflow you can follow, whether you are using a CAD system (CATIA, SolidWorks, Siemens NX) or a dedicated nuclear‑engineering tool (ANSYS, ABAQUS, Code‑Aster). The steps are organized to reflect the RCC‑M design cycle:
The RCC-M is a technical code published by the AFCEN (Association Française pour les règles de Conception et de Construction des Matériels des Chaudières Electro-nucléaires). It specifies the rules for designing and manufacturing mechanical components of Pressurized Water Reactors (PWRs), such as: rcc-m pdf download
Section I (Nuclear Island Components): The "key" to the code, classifying components into safety classes (1, 2, and 3) and providing specific design requirements for each.
Section V (Fabrication): Governs the manufacturing operations, including forming and assembly processes, to ensure compliance with design specifications. 3. Global Application and Access Introduction 2️⃣ Preparing a Solid Feature in Accordance
RCC-M Code Overview (AFCEN): A helpful 2-page fact sheet summarizing the subsections (A, B, C, etc.) and the scope of the code.
: Technical papers and overviews of the code’s evolution (such as the 2024 edition) are available for academic reference. Public Technical Annexes RCC-M Code Overview (AFCEN) : A helpful 2-page
| Title | Why it helps | |-------|--------------| | “Finite‑Element Modelling for Nuclear Pressure Vessels – Annex D of RCC‑M” (public‑access paper) | Walk‑through of mesh‑convergence and verification steps. | | ASME Boiler & Pressure Vessel Code, Section III | Covers similar design concepts; useful for cross‑checking calculations. | | “Design of Nuclear Components – A Practical Handbook” (IAEA‑TECDOC 1504) | Provides case studies and illustrative examples that map well onto RCC‑M requirements. | | “Guide to Fatigue Design for Nuclear Power Plant Components” (NRC NUREG‑0800) | Gives the fatigue methodology (Goodman, Gerber) that RCC‑M references. |