Transport processes in steam generator crevices Ⅲ. Experimental resutls

摘要

Corrosion within the tube/support plate crevices of pressurized water reactor steam gen- erators (SGs) has proven to be an important operating problem in the nuclear power industry. In order to explore the electrochemical nature of SG crevice corrosion, and to evaluate our Previously published theoretical models (Parts Ⅰ and Ⅱ), a SG simulator was developed to Perform selected experiments. These experiments involved three different bulk solution en- Vironments (acidic, neutral, and alkaline), a bulk water temperature of 200 deg. C at a pressure of 21 Kg cm~-2, and experimental times of up to 15 days.