Japanese manufacturers like Mitsubishi, Hitachi, and Toshiba have (or did have) licensing arrangements with US manufacturers like Westinghouse and GE to build US designed nuclear generating systems for the Japanese market. When Babcock and Wilcox sold Loose Part Monitoring systems to a utility in Japan, I grabbed the job because I like Japan. The plants were on the northwest coast in Fukui Prefecture, but we needed to assemble the systems in Japan, so that was done at the Babcock Hitachi facility in Kure near Hiroshima. I had the opportunity to look around - impressive. It seems like the Babcock Hitachi plant was one of the first manufacturing plants to have the ability to roll large vessels and weld seems as the assembly rotated.
Steam Generators (SG) are large heat exchangers with primary coolant on one side of the tube and secondary water on the other. The tubing is one of the boundaries between water that flows through the reactor (primary) and water that flows through the turbine/generator (secondary). With a SG tube leak, you have leakage from the primary to secondary loop because of the differential pressure. Westinghouse and Combustion plants use a U-tube configuration, so the primary coolant enters one side of the tube bundle at the bottom and exits at the other side of the tube bundle at the bottom of the SG. B&W uses Once Through Steam Generators (straight tubes in a counterflow design); primary coolant from the reactor enters the SG at the top and exits at the bottom - secondary coolant enters from the bottom and exits at the top. THE OTSG design allows for boiling along a larger region in the SG and for superheated (dry steam above the vapor point) steam to the turbine driving the generator. That makes it more responsive to load - it also make it easier to get things wrong if secondary flow to the SG is interrupted like at TMI. Like the difference between driving a sports car vs a bus.
Tube cracking and denting first showed up in the U-tube SGs - the first I remember was in the mid-late 1970s. The problem was basically flow induced vibration causing fretting and wear - movement of the tubes in the supports; denting was caused by the buildup of deposits in the spaces between the tubes and tube supports causing the tubes to impact the buildup rather than move as intended - some tubes were "necked" down with some flow restriction. The problems didn't show up in OTSGs until a few years later. The industry then responded by retubing or replacing steam generators. I've never seen it done, but it's a huge undertaking. Steam generators are massive and space inside containment (especially the Westinghouse ice condenser types) is limited.
Flow induced vibration is a problem anytime you have moving flow. There is a large body of work concerning tube lengths in heat exchangers, how tubes are supported and restrained, etc - that's all coupled with decades and decades of experience; but vibration never goes away when there is flow of liquid or gas. It's a lot harder to measure vibration in a heat exchanger than vibration of piping or other components subject to flow induced vibration. In the testing I did over the years, we used specially built accelerometers that were placed inside the heat exchanger tube and then the tube was blocked at each end; the accelerometer signal cables were metal coaxial types - center conductor in generally something like a SS outer conductor with a mineral oxide dielectric. A very expensive and time consuming process to figure out what went wrong.