Oxide growth and dissolution on 316L stainless steel during irradiation in high temperature water
Source abstract
Abstract
Abstract Helium was implanted in 316L stainless steel to produce a marker layer of bubbles to provide a reference for the assessment of oxidation and dissolution during proton irradiation in 320 °C hydrogenated water for 24 h and 72 h. Inner oxide thickness characterized by TEM dropped by a factor of 4.5 with irradiation. Marker layer measurements reveal a factor of 3 lower metal loss with irradiation. Metal loss increased without inner oxide growth between 24 h and 72 h of irradiation. Greater enrichment of chromium in the oxide under irradiation yields a more protective oxide film despite evidence of oxide dissolution.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Hydrogen embrittlement and corrosion behaviors in metals
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
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