Steam generator materials degradation
Conference
·
OSTI ID:48030
- EDF-GDL, Saint Denis (France)
- Framatome, Paris (France)
This paper presents an update of available information on the materials degradation observed in PWR steam generators. Primary water stress corrosion of INCONEL 6(O)(O) tube bundle has certainly been the most important mechanism of degradation experienced by many steam generators in the last ten years. Effectiveness of repairs such as thermal treatment of rows 1 and 2 U bends and peening of roll transition zones is also performed for roll transition zones to anticipate expected life of affected steam generators.
- OSTI ID:
- 48030
- Report Number(s):
- CONF-910808--
- Country of Publication:
- United States
- Language:
- English
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