Ageing management of Nuclear Power Plants is an essential issue for utilities, in term of safety and availability and corresponding economical consequences. Practically all nuclear countries have developed a systematic program to deal with ageing of components on their plants. This paper presents the ageing management program developed by EDF (Electricite´ de France) that are compared with different approaches in other countries, like IAEA (International Atomic Energy Agency)guidelines and GALL (Generic Ageing Lessons Learned) report. The paper presents an example of application to large diameter safety class piping. Different degradation mechanisms are considered fatigue, corrosion and thermal ageing. Maintenance and surveillance actions are also discussed in the paper.
Skip Nav Destination
ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference
July 23–27, 2006
Vancouver, BC, Canada
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
0-7918-4758-6
PROCEEDINGS PAPER
Aging Management Program of Large Diameter Safety Class Piping
Claude Faidy
Claude Faidy
Electricite´ de France (EDF)-SEPTEN, Villeurbanne Cedex, France
Search for other works by this author on:
Claude Faidy
Electricite´ de France (EDF)-SEPTEN, Villeurbanne Cedex, France
Paper No:
PVP2006-ICPVT-11-93179, pp. 41-48; 8 pages
Published Online:
July 23, 2008
Citation
Faidy, C. "Aging Management Program of Large Diameter Safety Class Piping." Proceedings of the ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference. Volume 7: Operations, Applications, and Components. Vancouver, BC, Canada. July 23–27, 2006. pp. 41-48. ASME. https://doi.org/10.1115/PVP2006-ICPVT-11-93179
Download citation file:
3
Views
0
Citations
Related Proceedings Papers
Related Articles
The History of Allowable Damping Values for U.S. Nuclear Plant Piping
J. Pressure Vessel Technol (May,1991)
Improving Nuclear Power Plant's Operational Efficiencies in the U.S.A.
Mechanical Engineering (January,2011)
Life Prediction and Monitoring of Nuclear Power Plant Components for Service-Related Degradation
J. Pressure Vessel Technol (February,2001)
Related Chapters
Development and Structure of the German Common Cause Failure Data Pool (PSAM-0020)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Iwe and Iwl
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 2, Third Edition
Global Harmonization of Flaw Modeling/Characterization
Global Applications of the ASME Boiler & Pressure Vessel Code