Experience from the performance of the steam generator at the Bohunice V-2 nuclear power plant

The design and operating conditions of the steam generator are characterized in detail. The manufacture tolerances, ways of their elimination and types of in-service repairs are described for six steam generators of unit 3 of the V-2 nuclear power plant. Particular attention is paid to problems of heat transfer tube leaks. The principle of the leak detection method is outlined, and recommendations are given for existing steam generators. (E.J.). 5 refs