Design of pressurized enclosures

In the [BN 3 280] file, we have defined the various damage modes that can affect the integrity of pressure vessels, and the criteria in the codes applicable to pressurized water nuclear reactors that enable them to be prevented.

The present dossier completes the [BN 3 280] dossier by covering the classification of constraints required to implement these criteria, as well as the general approach to design, analysis and monitoring in operation, regulatory tests and the procedures for equivalence between industrial construction codes. The acronyms used throughout the two dossiers are defined in [BN 3 280] .

In the Pour en Savoir Plus section [Doc. BN 3 282] , readers will find all the regulatory texts, standards and codes cited in this dossier.