Lead-induced stress corrosion cracking of Alloy 600 and 690 in high temperature water
- Nuclear Fuel Industries, Ltd., Osaka (Japan)
Lead is one of the potential contributing impurities to the degradation of PWR steam generator tubing. Recent laboratory testing has shown that lead is a corrosive material for Alloy 600 steam generator tubing. However, it is still unknown how lead influences the corrosion of steam generator tubing, including the effect of lead concentration, solution pH, stress level and material characteristics. In this study, two kinds of experiments were performed. One was to investigate the thin film characteristic and selectively dissolved base metal elements of Alloy 600MA in high temperature solutions of different lead concentrations and pH. The other investigated the dependency of degradation of Alloy 600MA and Alloy 690TT on lead concentration and stress level in mild acidic environment, at 340{degrees}C for 2500 hrs. It was firstly demonstrated that lead-enhanced selective dissolution of nickel from alloy base metal, as a result of electrochemical reaction between lead and nickel, might cause the initiation and propagation of corrosion. Secondly, we showed that Alloy 690TT, generally very corrosion resistant material, also suffered from Pb-induced corrosion. The difference of the lead-induced stress corrosion morphology of Alloy 600MA and Alloy 690TT was also clarified.
- OSTI ID:
- 48112
- Report Number(s):
- CONF-910808-; TRN: 95:011546
- Resource Relation:
- Conference: 5. international symposium on environmental degradation of materials in nuclear power systems - water reactors, Monterey, CA (United States), 25-29 Aug 1991; Other Information: PBD: 1992; Related Information: Is Part Of Proceedings of the fifth international symposium on environmental degradation of materials in nuclear power systems - water reactors; PB: 995 p.
- Country of Publication:
- United States
- Language:
- English
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