Published September 1993 | Version v1
Journal article

Corrosion lead effect in secondary coolant circuits of PWR steam generator tubes

  • 1. Electricite de France (EDF), 77 - Ecuelles (France)
  • 2. Electricite de France (EDF), 37 - Chinon (France)

Description

In most of working PWR reactors, steam generator tubes are composed of alloy 600. Because of corrosion, this alloy is replaced by alloy 690. Many tests showed that damages included an abnormal content in lead oxide. Tests have been conducted to determine the influence of lead on alloy 600 and 690 corrosion. The resistance of alloy 800 has been also studied. To test the lead effect, we studied the behaviour of these alloys with or without lead oxide. The lead oxide presence in sodium hydroxide accelerates the stress corrosion cracking and the general corrosion of these alloys. Moreover lead oxide accelerates the general corrosion of alloys 600 and 690. An analysis of the corroded layer showed a lead enrichment. In sodium hydroxide solution added with lead the alloy 800 seems less resistant than the alloys 600 and 690. 2 figs

Additional details

Additional titles

Original title (French)
Effet du plomb sur la corrosion en milieu secondaire des tubes de generateurs de vapeur des centrales nucleaires a eau pressurisee

Publishing Information

Journal Title
Revue de Metallurgie (Paris)
Journal Volume
90
Journal Issue
9
Journal Page Range
p. 1169.
ISSN
0035-1563
CODEN
REMEAH

Conference

Title
Autumn Days of the Societe Francaise de Metallurgie et de Materiaux.
Original Conference Title
Journees d'Automne 1993 de la Societe Francaise de Metallurgie et de Materiaux
Dates
12-14 Oct 1993.
Place
Paris (France).