Uniform corrosion behavior of Zr-1Sn-0.35Fe-0.15Cr-xNb alloys in 400 ℃ super-heated steam with oxygen
Source abstract
Abstract
Zr-1Sn-0.35Fe-0.15Cr- x Nb ( x = 0.05, 0.10, 0.15, wt%) alloys were designed to explore the effect of oxygen concentrations and Nb contents on the uniform corrosion behavior of the alloys. Results showed that the effect of trace Nb content on the uniform corrosion behavior of Zr alloys is related to the DO concentrations in steam; DO can accelerate the corrosion of the alloys, and this effect is enhanced with the increase of the DO concentrations. A mechanism of the accelerated corrosion rate by Nb and DO was proposed, which provides theoretical guidance for the selection of fuel cladding materials for small nuclear reactors.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
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