Corrosion behavior of Alloy 690 after cessation of zinc addition in simulated PWR primary water at 330 °C
Source abstract
Abstract
Abstract The purpose of this work is to quantify the effect of zinc cessation on corrosion and release rates from Alloy 690 steam generator tubes that were previously oxidized in zinc-containing water. The corrosion tests were performed in 2 ppm Li and 1000 ppm B water with and without 60 ppb zinc at 330 °C. The corrosion rates, release rates, and oxide thicknesses were determined based on descaling and gravimetric analysis methods and the results showed only a slight increase even after cessation of zinc addition. This is attributed to the zinc-containing chromium-rich inner oxide layer still remaining after the cessation of zinc addition.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Non-Destructive Testing Techniques · Hydrogen embrittlement and corrosion behaviors in metals
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
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