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Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor

Abstract Grain boundary (GB) oxidation of proton-irradiated 304 nuclear grade stainless steel in primary water of pressurized water reactor was investigated. The investigation was conducted by studying microstructure of the oxide and oxide precursor formed at GB on an "atom-by-atom" basis by a combi...

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Bibliographic Details
Main Authors: Ping Deng, Qunjia Peng, En-Hou Han
Format: Artigo
Language:Inglês
Published: Nature Portfolio 2021-01-01
Series:Scientific Reports
Online Access:https://doi.org/10.1038/s41598-020-80600-x
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