Steam generator (SG) tubes in pressurized water reactors have been extensively studied; however, investigations using tubular specimens under simulated operating conditions, dual-loop environments of high-flowing high-temperature and high-pressure waters, remain scarce. In this work, a slow strain rate tensile test was conducted on a 316 stainless steel tube under such dual‑loop conditions that simulated a temperature difference of > 30 °C and a pressure difference of 7 MPa between the primary and secondary sides. The corrosion damage behavior on the inner and outer surfaces of the tube was systematically compared. The results show that oxidation was more severe on the inner surface, while cracks on the outer surface penetrated deeper, exhibiting typical intergranular stress corrosion cracking (IGSCC) characteristics. In contrast, cracks on the inner surface were shallower (average depth about one‑third of that on the outer surface) but significantly denser (2.3 times that on the outer surface). The average crack spacing (35.3 μm) was close to the average grain size excluding twins (29.3 μm), suggesting that the majority of random high-angle grain boundaries in inner surface experienced cracking. Comprehensive analysis reveals that the dominant failure mechanism on the outer surface is IGSCC, whereas intergranular corrosion is the predominant failure mechanism on the inner surface.


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