The steam generator is one of the key equipment in the pressurized water reactor nuclear power device, and it has a significant impact on the performance and safety reliability of the entire nuclear power system. Although a lot of work has been done in the structural design, material performance, manufacturing process, water quality, water treatment methods, and operation and maintenance of the steam generator, many problems still remain, and heat transfer tube damage accidents often occur. Statistics from 2009 showed that the number of units with blocked tubes reached more than 40%, which means that the integrity of the steam generator largely depends on the reliability of the heat transfer tubes—that is, their structural integrity. According to operating management regulations, if the leakage rate of the steam generator tube exceeds the maximum allowable value, the power plant must shut down the reactor. Japan has the strictest regulations, requiring an immediate shutdown as soon as a leak is detected. France generally stipulates a limit of 72 L/h. The primary and secondary working media in the steam generator are isolated by the heat transfer tube wall and the tube plate. Currently, the wall thickness of the heat transfer tube is generally 1.0–1.2 mm, and the surface area of the heat transfer tube accounts for nearly 80% of the pressure boundary area of the primary loop system. Therefore, the heat transfer tube of the steam generator is the weakest part of the entire primary loop pressure boundary. Actual use also shows that it is the “accident-prone area” in the steam generator. Thus, the main problem of the steam generator now is that the reliability of the heat transfer tube is relatively low, which causes nuclear power system accidents and seriously affects the safety, reliability, and economy of the nuclear power device’s operation [24].