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An Introduction to RCC-C: An AFCEN Code for Design and Construction of PWR Fuel Assemblies

[+] Author Affiliations
Christine Vauglin

AREVA NP Fuel, Lyon, France

Marc Ton-That

EDF - SEPTEN, Villeurbanne, France

Morello Sperandio

AREVA NP, Lyon, France

Denis Buisine

EDF - CEIDRE, Saint Denis, France

Paper No. ICONE21-16810, pp. V003T07A025; 6 pages
doi:10.1115/ICONE21-16810
From:
  • 2013 21st International Conference on Nuclear Engineering
  • Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes
  • Chengdu, China, July 29–August 2, 2013
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5580-5
  • Copyright © 2013 by ASME

abstract

AFCEN is the French society which publishes codes for design, construction and in-service inspection rules for Pressurized Water Reactors. The fields covered by theses codes are: mechanical components, in-service surveillance of mechanical components, electrical equipments, nuclear fuel, and more recently, civil works and fire protection.

After a brief global presentation of AFCEN history and current position, we set out the technical content of one of these codes: RCC-C. This code is dedicated to fuel assemblies and associated core components. It sets forth minimum generic requirements to be met by the supplier and by the manufacturer for the design justifications and for the manufacturing and inspection operations of PWR fuel assemblies and rod cluster control assemblies.

We go over the different chapters of RCC-C: product and part characteristics; manufacturing and inspection processes and methods and associated qualifications; inspection requirements for the different items; design characteristics and requirements which the design justification shall meet; methods for demonstrating that design requirements are met.

Copyright © 2013 by ASME

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