Recommendation for linearization procedure in nuclear pressure vessel-nozzle intersections

The pressure vessel design is a fundamental step during the construction of new pressurized water reactors (PWRs). In these facilities, several safety requirements are necessary to guarantee protection workers, community and environment against release radioactive materials. Design by Analysis procedure present in ASME Code, Section III, for nuclear components, which consist rigorous analysis classification all types stresses loading conditions incorporate smaller coefficients. limits were based on shell theory. However, precise rules achieving various stress categories, solid finite element analysis, have not been implemented code. For this reason, work presents methodology linearization elastic vessel-nozzle intersections. So was modeling tridimensional elements, analyzed verified as component. Then, discussion how perform code verifications presented, well mapping stresses. lines that constructed between transition structural elements longitudinal plane (0º) nozzle transversal (90º) higher compared with III limits.