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

Ping Deng; Qunjia Peng; En-Hou Han

doi:10.1038/s41598-020-80600-x

Scientific Reports (Jan 2021)

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

Ping Deng,
Qunjia Peng,
En-Hou Han

Affiliations

Ping Deng: Nuclear Power Institute of China
Qunjia Peng: Nuclear Power Institute of China
En-Hou Han: Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences

DOI: https://doi.org/10.1038/s41598-020-80600-x
Journal volume & issue: Vol. 11, no. 1
pp. 1 – 9

Abstract

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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 combination of atom-probe tomography and transmission electron microscope. The results revealed that increasing irradiation dose promoted the GB oxidation, in correspondence with a different oxide and oxide precursor formed at the GB. Correlation of the oxide and oxide precursor with the GB oxidation behavior has been discussed in detail.

Published in Scientific Reports

ISSN: 2045-2322 (Online)
Publisher: Nature Portfolio
Country of publisher: United Kingdom
LCC subjects: Medicine; Science
Website: https://www.nature.com/srep/

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