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이은희,김경모,김우철,황성식,김홍표 한국부식학회 1998 Corrosion Science and Technology Vol.27 No.3
A steam generator(SG) is one of key components of a nuclear power plant (NPP) and a SG has thousands thin tubes to make efficient heat transfer. Several kinds of degradation have been reported on these tubes since they should be used under the high pressure conditions at high temperatures. Experiences in corrosion and stress corrosion cracking are explained for domestic and foreign NPPs. Domains for stress corrosion cracking are analyzed in a pH-potential diagram and changes of electrochemical potential are shown in the crevices between tubes and tube sheets/tube support plates. Test results are reviewed and remedial measures are summarized. In addition, research items are descrived in order to enhance the integrity of SGs and to extend their lifetime.