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Interpretive Comparison of the Requirements Relating to Welding and Non-Destructive Examination in the French and US Codes for Nuclear Components

[+] Author Affiliations
Marcello Consonni, Peter Mudge

TWI Ltd., Cambridge, UK

Paper No. ICONE20-POWER2012-54190, pp. 35-49; 15 pages
  • 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference
  • Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes
  • Anaheim, California, USA, July 30–August 3, 2012
  • Conference Sponsors: Nuclear Engineering Division, Power Division
  • ISBN: 978-0-7918-4498-4
  • Copyright © 2012 by ASME


The two main designs currently being applied worldwide for pressurized water reactors (PWR) are the EPR™ and the AP-1000®, respectively based on the Design and Construction Rules for Mechanical Components of PWR Nuclear Islands code (Règles de Conception et de Construction des Matériels Mécaniques des Ilots Nucléaires des réacteurs à eau sous pression, RCC-M), the French nuclear construction code, and on the ASME Boiler and Pressure Vessel Code (referred to hereafter as ‘ASME’).

This paper presents an interpretive comparison between the RCC-M and ASME requirements for welding and non-destructive testing (NDT), limited to components within the ‘nuclear island’. Differences that might have an impact on manufacturing operations or on the long term integrity of the Class 1 welds are discussed. The results are presented in the form of text and tables. In addition, individual clauses are compared to establish if they can be considered equivalent and if not, which code provides the most stringent requirements.

Copyright © 2012 by ASME
Topics: Welding



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