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Irradiation Hardening of Austenitic Stainless Steels: From Field Experience to Modeling

[+] Author Affiliations
C. Pokor, Y. Thebault

Electricité de France, Avoine Cedex, France

C. Pujol, E. Lemaire

Electricité de France, Saint Denis Cedex, France

J.-P. Massoud, D. Loisnard

Electricité de France, Moret Sur Loing, France

Ph. Dubuisson

CEA Saclay, Gif Sur Yvette Cedex, France

Y. Brechet

Domaine Universitaire de Grenoble, Saint Martin d’Heres Cedex, France

Paper No. PVP2004-3052, pp. 7-17; 11 pages
doi:10.1115/PVP2004-3052
From:
  • ASME/JSME 2004 Pressure Vessels and Piping Conference
  • Storage Tank Integrity and Materials Evaluation
  • San Diego, California, USA, July 25–29, 2004
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-4685-7
  • Copyright © 2004 by ASME

abstract

Materials for the core internals of Pressurized Water Reactors (austenitic stainless steels) are submitted to neutron irradiation. To understand the ageing mechanisms associated to irradiation and propose life predictions of the component, a multi step iterative approach consisting in particular in modeling the evolution of the hardening has been undertaken. Combination of characterization and modeling of simplified situations and field expertise is proposed.

Copyright © 2004 by ASME

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