NDLI: Stress and Fatigue Analysis Considering Thermal Stratification With the THERMAXS Code

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Diaby, Adama Smet, Michel De
Copyright Year	2009
Abstract	This paper describes the stress and fatigue analysis of the feed water nozzles of the replacement steam generators of the Doel 2 NPP in Belgium. In the framework of the steam generators replacement, thermal stratification transients were considered in the stress and fatigue analyses of the feed water system components such as the feed water lines, their reactor building penetrations and the steam generator feed water nozzles. To do so, long term external wall temperature measurement have been performed on one feed water line of Doel 2 between the steam generator replacement in 2004 and December 2007. From those measurements a number of typical stratification phenomena were identified. For each phenomenon, a design stratification transient and its number of occurrences were derived from the measurements. A fatigue analysis and primary+secondary stress intensity analysis of the feed water nozzles of the Doel 2 NPP was performed taking into account the presence of the design thermal stratification transients in the feed water lines and feed water nozzles. The fatigue analysis was performed according to the rules of the ASME Boiler & Pressure Vessel Code, Section III, Division 1 – Subsection NB-3200 using the in-house developed computer code THERMAXS that is capable of dealing with measured stratification transients. For the analysis, one may finally conclude that the fatigue, P+Q stress intensity range and thermal ratcheting criteria are respected throughout the 40 years of plant life.
Sponsorship	Pressure Vessels and Piping
Starting Page	849
Ending Page	853
Page Count	5
File Format	PDF
ISBN	9780791843666
DOI	10.1115/PVP2009-77912
e-ISBN	9780791838549
Volume Number	Volume 3: Design and Analysis
Conference Proceedings	ASME 2009 Pressure Vessels and Piping Conference
Language	English
Publisher Date	2009-07-26
Publisher Place	Prague, Czech Republic
Access Restriction	Subscribed
Subject Keyword	Computers Boilers Fatigue Fatigue analysis Thermal stratification Stress Transients (dynamics) Design Wall temperature Pressure vessels Feedwater Nozzles Nuclear power stations
Content Type	Text
Resource Type	Article

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