Corrosion fatigue crack growth behavior of 316NG heat affected zone in simulated pressurized water reactor environment
Source abstract
Abstract
Abstract The corrosion fatigue crack growth (FCG) behavior of the 316NG heat affected zone (HAZ) exposed to simulated pressurized water reactor (PWR) environment has been investigated. The results show that significant residual strains and lattice misorientations exist in the HAZ near the welding root. Z-phase precipitates are present in both the HAZ and annealed 316NG base metal. The FCG rate of the HAZ is much higher than that of the base metal. In PWR water, the corrosion FCG rate of the HAZ is strongly dependent on the cyclic loading frequency, but the effect of dissolved oxygen is negligible.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · Fatigue and fracture mechanics · High Temperature Alloys and Creep
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
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