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...

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Autores principales:	Ping Deng, Qunjia Peng, En-Hou Han
Formato:	article
Lenguaje:	EN
Publicado:	Nature Portfolio 2021
Materias:	Medicine R Science Q
Acceso en línea:	https://doaj.org/article/b0e862a7d8e44bd7a032a32a59cf03b8
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spelling	oai:doaj.org-article:b0e862a7d8e44bd7a032a32a59cf03b82021-12-02T14:12:42ZGrain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor10.1038/s41598-020-80600-x2045-2322https://doaj.org/article/b0e862a7d8e44bd7a032a32a59cf03b82021-01-01T00:00:00Zhttps://doi.org/10.1038/s41598-020-80600-xhttps://doaj.org/toc/2045-2322Abstract 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.Ping DengQunjia PengEn-Hou HanNature PortfolioarticleMedicineRScienceQENScientific Reports, Vol 11, Iss 1, Pp 1-9 (2021)
institution	DOAJ
collection	DOAJ
language	EN
topic	Medicine R Science Q
spellingShingle	Medicine R Science Q Ping Deng Qunjia Peng En-Hou Han Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor
description	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.
format	article
author	Ping Deng Qunjia Peng En-Hou Han
author_facet	Ping Deng Qunjia Peng En-Hou Han
author_sort	Ping Deng
title	Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor
title_short	Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor
title_full	Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor
title_fullStr	Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor
title_full_unstemmed	Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor
title_sort	grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor
publisher	Nature Portfolio
publishDate	2021
url	https://doaj.org/article/b0e862a7d8e44bd7a032a32a59cf03b8
work_keys_str_mv	AT pingdeng grainboundaryoxidationofprotonirradiatednucleargradestainlesssteelinsimulatedprimarywaterofpressurizedwaterreactor AT qunjiapeng grainboundaryoxidationofprotonirradiatednucleargradestainlesssteelinsimulatedprimarywaterofpressurizedwaterreactor AT enhouhan grainboundaryoxidationofprotonirradiatednucleargradestainlesssteelinsimulatedprimarywaterofpressurizedwaterreactor
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Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor

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