Article | REF: BN3282 V1

Design of pressurized enclosures

Author: Jean-Marie granDEMANGE

Publication date: January 10, 2008

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ABSTRACT

This article deals with the design of pressurized enclosures, more specifically, damage modes and the classification of strains to which they are submitted. Their various design stages are developed, up to monitoring during operation. Responsibilities, design conditions and materials selections are all discussed. To conclude, regulatory tests are set in context and modalities of equivalency between industrial construction codes are also analyzed (for example, codes applicable to nuclear reactor equipment).

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AUTHOR

  • Jean-Marie granDEMANGE: AREVA-NP, Secretary of the RCC-M Sub-Committee of the French Association for the Design, Construction and Operational Supervision of Nuclear Power Boilers (AFCEN)

 INTRODUCTION

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.

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Pressure vessel design