Root cause analysis of SG tube leakage at Fessenheim unit 2 in 2008
- 1. EDF - SEPTEN, 12-14, Avenue Dutrievoz, 69628 Villeurbanne Cedex (France)
- 2. EDF - UNIE, 1, Place Pleyel, 93282 Saint-Denis Cedex (France)
Description
In February 2008, a primary-to-secondary leak caused an unscheduled shutdown at Fessenheim Unit 2 NPP. A circumferential crack was observed just above the top support plate of Row 12 Column 62 U-bend tube on Steam Generator (SG) number 3, which has been attributed to high cycle fatigue. This tube was pulled out in 2011, just before the SG replacement at the third decenal outage, in order to perform exhaustive metallurgical investigations. The destructive examinations revealed that the circumferential crack (70 degrees of extension) was due to high cycle fatigue, with several external initiation areas associated with the presence of small piles of Intergranular Attack (IGA) (600 MA tube) and with very low stress intensity factors ΔK (close to the non-propagating threshold region). This paper complements the metallurgical investigations by carrying out numerical analyses (thermal-hydraulic computation, fluid-elastic instability evaluation, tube vibratory response analysis and fatigue evaluation). The first objective of the study is to attempt to clarify the effect of IGA and the role of several competing factors that could be involved in the tube vibration induced fatigue failure. From these results, a root cause analysis of the R12C62 tube fatigue failure is then provided. It appears that a combination of various factors led to the failure of the tube
Files
Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 33 p.
- Report number
- INIS-FR--15-0384
Conference
- Title
- Conference on Contribution of Materials Investigations and Operating Experience to LWRs' Safety, Performance and Reliability
- Acronym
- Fontevraud 8
- Dates
- 15-18 Sep 2014
- Place
- Avignon (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 46081684
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CRACK PROPAGATION; CRACKS; FATIGUE; FESSENHEIM-2 REACTOR; INCONEL 600; INTERGRANULAR CORROSION; LEAKS; MECHANICAL VIBRATIONS; STEAM GENERATORS
- Descriptors DEC
- ALLOY-NI76CR15FE8; ALLOYS; ALUMINIUM ADDITIONS; ALUMINIUM ALLOYS; BOILERS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CORROSION; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INCONEL ALLOYS; IRON ALLOYS; MATERIALS; MECHANICAL PROPERTIES; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 22 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/INIS/contacts/